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1

Next Generation Safeguards Initiative Workshop on Enhanced Recruiting for International Safeguards  

SciTech Connect (OSTI)

In 2007, the National Nuclear Security Administration's Office of Nonproliferation and International Security (NA-24) completed a yearlong review of the challenges facing the international safeguards system today and over the next 25 years. The study found that without new investment in international safeguards, the U.S. safeguards technology base, and our ability to support International Atomic Energy Agency (IAEA) safeguards, will continue to erode and soon may be at risk. To reverse this trend, the then U.S. Secretary of Energy, Samuel Bodman, announced at the 2007 IAEA General Conference that the Department of Energy (DOE) would launch the Next Generation Safeguards Initiative (NGSI). He stated 'IAEA safeguards must be robust and capable of addressing proliferation threats. Full confidence in IAEA safeguards is essential for nuclear power to grow safely and securely. To this end, the U.S. Department of Energy will seek to ensure that modern technology, the best scientific expertise, and adequate resources are available to keep pace with expanding IAEA responsibilities.' To meet this goal, the NGSI objectives include the recruitment of international safeguards experts to work at the U.S. national laboratories and to serve at the IAEA's headquarters. Part of the latter effort will involve enhancing our existing efforts to place well-qualified Americans in a sufficient number of key safeguards positions within the IAEA's Department of Safeguards. Accordingly, the International Safeguards Project Office (ISPO) at Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards (ERIS) on October 22 and 23, 2008. The ISPO used a workshop format developed earlier with Sonalysts, Inc., that was followed at the U.S. Support Program's (USSP's) technology road-mapping sessions. ISPO invited participants from the U.S. DOE, the IAEA, the U.S. national laboratories, private industry, academia, and professional societies who either are experts in international safeguards, or understand the challenges of recruiting for technical positions. The 44 participants represented eight national laboratories, four universities, three government organizations, two international organizations, two professional organizations, and three small companies. The goal of the ERIS workshop was to improve efforts to engage U.S. citizens for IAEA positions in the Department of Safeguards. The participants considered the specific challenges of recruiting professional staff, safeguards inspectors, and managers. At the workshop's conclusion, participants presented their findings to the NNSA Office of International Regimes and Agreements (NA-243). The report's major findings are summarized.

Pepper,S.; Rosenthal, M.; Fishbone, L.; Occhiogrosso, D.; Carroll, C.; Dreicer, M.; Wallace, R.; Rankhauser, J.

2008-10-22T23:59:59.000Z

2

Next Generation Safeguards Initiative Workshop on Enhanced Recruiting for International Safeguards  

SciTech Connect (OSTI)

Brookhaven National Laboratory (BNL) hosted a Workshop on Enhanced Recruiting for International Safeguards October 22 and 23, 2008. The workshop was sponsored by DOE/NA-243 under the Next Generation Safeguards Initiative (NGSI). Placing well-qualified Americans in sufficient number and in key safeguards positions within the International Atomic Energy Agency’s (IAEA’s) Department of Safeguards is an important U.S. non-proliferation objective. The goal of the NGSI Workshop on Enhanced Recruiting for International Safeguards was to improve U.S. efforts to recruit U.S. citizens for IAEA positions in the Department of Safeguards. The participants considered the specific challenges of recruiting professional staff, safeguards inspectors, and managers. BNL’s International Safeguards Project Office invited participants from the U.S. Department of Energy, the IAEA, U.S. national laboratories, private industry, academia, and professional societies who are either experts in international safeguards or who understand the challenges of recruiting for technical positions. A final report for the workshop will be finalized and distributed in early 2009. The main finding of the workshop was the need for an integrated recruitment plan to take into account pools of potential candidates, various government and private agency stakeholders, the needs of the IAEA, and the NGSI human capital development plan. There were numerous findings related to and recommendations for maximizing the placement of U.S. experts in IAEA Safeguards positions. The workshop participants offered many ideas for increasing the pool of candidates and increasing the placement rate. This paper will provide details on these findings and recommendations

Pepper,S.E.; Rosenthal, M.D.; Fishbone, L.G.; Occhogrosso, D.M.; Lockwood, D.; Carroll, C.J.; Dreicer, M.; Wallace, R.; Fankhauser, J.

2009-07-12T23:59:59.000Z

3

Fiscal Year 2014 Annual Report on BNLs Next Generation Safeguards Initiative Human Capital Development Activities  

SciTech Connect (OSTI)

Brookhaven National Laboratory’s (BNL’s) Nonproliferation and National Security Department contributes to the National Nuclear Security Administration Office of Nonproliferation and International Security Next Generation Safeguards Initiative (NGSI) through university engagement, safeguards internships, safeguards courses, professional development, recruitment, and other activities aimed at ensuring the next generation of international safeguards professionals is adequately prepared to support the U.S. safeguards mission. This report is a summary of BNL s work under the NGSI program in Fiscal Year 2014.

Pepper S. E.

2014-10-10T23:59:59.000Z

4

Next Generations Safeguards Initiative: The Life of a Cylinder  

SciTech Connect (OSTI)

The U.S. Department of Energy/National Nuclear Security Administration Office of Nonproliferation and International Security's Next Generation Safeguards Initiative (NGSI) has begun a program based on a five-year plan to investigate the concept of a global monitoring scheme that uniquely identifies uranium hexafluoride (UF6) cylinders and their locations throughout the life cycle. A key initial activity in the NGSI program is to understand and document the 'life of a UF6 cylinder' from cradle to grave. This document describes the life of a UF6 cylinder and includes cylinder manufacture and procurement processes as well as cylinder-handling and operational practices at conversion, enrichment, fuel fabrication, and depleted UF6 conversion facilities. The NGSI multiple-laboratory team is using this document as a building block for subsequent tasks in the five-year plan, including development of the functional requirements for cylinder-tagging and tracking devices.

Morgan, James B [ORNL; White-Horton, Jessica L [ORNL

2012-01-01T23:59:59.000Z

5

FY 2008 Next Generation Safeguards Initiative International Safeguards Education and Training Pilot Progerams Summary Report  

SciTech Connect (OSTI)

Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure to nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A&M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students were senior classmen or new master's degree graduates from MIIS specializing in nonproliferation policy studies. Other university/organizations represented: University of California in LA, Stanford University, and the IAEA. Four of the students that completed this intensive course participated in a 2-month internship at LLNL. The conclusions of the two pilot courses and internships was a NGSI Summer Student Symposium, held at LLNL, where 20 students participated in LLNL facility tours and poster sessions. The Poster sessions were designed to provide a forum for sharing the results of their summer projects and providing experience in presenting their work to a varied audience of students, faculty and laboratory staff. The success of bringing together the students from the technical and policy pilots was notable and will factor into the planning for the continued refinement of their two pilot efforts in the coming years.

Dreicer, M; Anzelon, G; Essner, J; Dougan, A; Doyle, J; Boyer, B; Hypes, P; Sokova, E; Wehling, F

2008-10-17T23:59:59.000Z

6

Next Generation Safeguards Initiatives at Los Alamos National Laboratory  

National Nuclear Security Administration (NNSA)

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7

Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiative’s Plutonium Assay Challenge  

SciTech Connect (OSTI)

This is an end-of-year report for a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The first-year goals for this project were modest and included: 1) developing a zero-order MCNP model for the NRTA technique, simulating data results presented in the literature, 2) completing a preliminary set of studies investigating important design and performance characteristics for the NRTA measurement technique, and 3) documentation of this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes a nine month period of work.

J. W. Sterbentz; D. L. Chichester

2010-12-01T23:59:59.000Z

8

Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program  

SciTech Connect (OSTI)

Thousands of cylinders containing uranium hexafluoride (UF{sub 6}) move around the world from conversion plants to enrichment plants to fuel fabrication plants, and their contents could be very useful to a country intent on diverting uranium for clandestine use. Each of these large cylinders can contain close to a significant quantity of natural uranium (48Y cylinder) or low-enriched uranium (LEU) (30B cylinder) defined as 75 kg {sup 235}U which can be further clandestinely enriched to produce 1.5 to 2 significant quantities of high enriched uranium (HEU) within weeks or months depending on the scale of the clandestine facility. The National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) kicked off a 5-year plan in April 2011 to investigate the concept of a unique identification system for UF{sub 6} cylinders and potentially to develop a cylinder tracking system that could be used by facility operators and the International Atomic Energy Agency (IAEA). The goal is to design an integrated solution beneficial to both industry and inspectorates that would improve cylinder operations at the facilities and provide enhanced capabilities to deter and detect both diversion of low-enriched uranium and undeclared enriched uranium production. The 5-year plan consists of six separate incremental tasks: (1) define the problem and establish the requirements for a unique identification (UID) and monitoring system; (2) develop a concept of operations for the identification and monitoring system; (3) determine cylinder monitoring devices and technology; (4) develop a registry database to support proof-of-concept demonstration; (5) integrate that system for the demonstration; and (6) demonstrate proof-of-concept. Throughout NNSA's performance of the tasks outlined in this program, the multi-laboratory team emphasizes that extensive engagement with industry stakeholders, regulatory authorities and inspectorates is essential to its success.

Boyer, Brian D [Los Alamos National Laboratory; Whitaker, J. Michael [ORNL; White-Horton, Jessica L. [ORNL; Durbin, Karyn R. [NNSA

2012-07-12T23:59:59.000Z

9

Oak Ridge National Laboratory Next-Generation Safeguards Initiative: Human Capital Development  

SciTech Connect (OSTI)

In 2007, the US Department of Energy National Nuclear Security Administration (DOE/NNSA) Office of Nonproliferation and International Security (NA-24) completed a comprehensive review of the current and potential future challenges facing the international safeguards system. The review examined • trends and events that have an effect on the mission of international safeguards; • the implications of expanding and evolving mission requirements of the legal authorities and institutions that serve as the foundation of the international safeguards system; and • the technological, financial, and human resources required for effective safeguards implementation. The review’s findings and recommendations were summarized in the report International Safeguards: Challenges and Opportunities for the 21st Century (October 2007).1 The executive summary is available at the following link: http://nnsa.energy.gov/sites/default/files/nnsa/inlinefiles/NGSI_Report.pdf.

Gilligan, Kimberly [ORNL

2014-01-01T23:59:59.000Z

10

Next Generation Safeguards Initiative: Analysis of Probability of Detection of Plausible Diversion Scenarios at Gas Centrifuge Enrichment Plants Using Advanced Safeguards  

SciTech Connect (OSTI)

Over the last decade, efforts by the safeguards community, including inspectorates, governments, operators and owners of centrifuge facilities, have given rise to new possibilities for safeguards approaches in enrichment plants. Many of these efforts have involved development of new instrumentation to measure uranium mass and uranium-235 enrichment and inspection schemes using unannounced and random site inspections. We have chosen select diversion scenarios and put together a reasonable system of safeguards equipment and safeguards approaches and analyzed the effectiveness and efficiency of the proposed safeguards approach by predicting the probability of detection of diversion in the chosen safeguards approaches. We analyzed the effect of redundancy in instrumentation, cross verification of operator instrumentation by inspector instrumentation, and the effects of failures or anomalous readings on verification data. Armed with these esults we were able to quantify the technical cost benefit of the addition of certain instrument suites and show the promise of these new systems.

Hase, Kevin R. [Los Alamos National Laboratory; Hawkins Erpenbeck, Heather [Los Alamos National Laboratory; Boyer, Brian D. [Los Alamos National Laboratory

2012-07-10T23:59:59.000Z

11

Safeguards First Principles Initiative at the Nevada Test Site  

SciTech Connect (OSTI)

The Material Control and Accountability (MC&A) program at the Nevada Test Site (NTS) was selected as a test bed for the Safeguards First Principles Initiative (SFPI). The implementation of the SFPI is evaluated using the system effectiveness model and the program is managed under an approved MC&A Plan. The effectiveness model consists of an evaluation of the critical elements necessary to detect, deter, and/or prevent the theft or diversion of Special Nuclear Material (SNM). The modeled results indicate that the MC&A program established under this variance is still effective, without creating unacceptable risk. Extensive performance testing is conducted through the duration of the pilot to ensure the protection system is effective and no material is at an unacceptable risk. The pilot was conducted from January 1, 2007, through May 30, 2007. This paper will discuss the following activities in association with SFPI: 1. Development of Timeline 2. Crosswalk of DOE Order and SFPI 3. Peer Review 4. Deviation 5. MC&A Plan and Procedure changes 6. Changes implemented at NTS 7. Training 8. Performance Test

Geneva Johnson

2007-07-08T23:59:59.000Z

12

Initial Evaluation of a New Electromechanical Cooler for Safeguards Applications  

SciTech Connect (OSTI)

The use of liquid nitrogen (LN{sub 2}) constitutes the current state of the art in cryogenic cooling for high-purity germanium (HPGe) detectors, which are widely used for {gamma}-ray and characteristic X-ray spectroscopy because of their excellent energy discrimination. Use of LN{sub 2} requires a liquid nitrogen supply, cumbersome storage tanks and plumbing, and the frequent attention of personnel to be sure that nitrogen levels are sufficient to maintain the detectors at a sufficiently low operating temperature. Safety hazards also are associated with the use of LN{sub 2}, both because of the potential for severe frostbite on exposure to skin and because it displaces ambient oxygen when it evaporates in closed spaces. Existing electromechanical coolers have, until now, been more expensive to procure and maintain than LN{sub 2} systems. Performance and reliability have also been serious issues because of microphonic degradation of photon energy peak resolution and cooler failures due to compressor oil becoming entrained in the refrigerant. This report describes the results of tests of a new HPGe detector cooling technology, the PerkinElmer ORTEC{reg_sign} Products X-Cooler{trademark} that, according to the manufacturer, significantly reduces the lifetime cost of the cooling system without degradation of the output signal. The manufacturer claims to have overcome cost, performance and reliability problems of older-generation electromechanical coolers, but the product has no significant history of use, and this project is the first independent evaluation of its performance for Total cost savings for the DOE and other agencies that use HPGe systems extensively for safeguards monitoring is expected to be quite significant if the new electromechanical cooler technology is shown to be reliable and if performance characteristics indicate its usefulness for this application. The technology also promises to make HPGe monitoring, characterization and detection available for unattended or covert operation and in remote or inaccessible locations where the unavailability of LN{sub 2} and signal degradation from existing mechanical coolers prevent its use at the present time.

Coleman, RL

2002-10-21T23:59:59.000Z

13

Building safeguards infrastructure  

SciTech Connect (OSTI)

Much has been written in recent years about the nuclear renaissance - the rebirth of nuclear power as a clean and safe source of electricity around the world. Those who question the nuclear renaissance often cite the risk of proliferation, accidents or an attack on a facility as concerns, all of which merit serious consideration. The integration of these three areas - sometimes referred to as 3S, for safety, security and safeguards - is essential to supporting the growth of nuclear power, and the infrastructure that supports them should be strengthened. The focus of this paper will be on the role safeguards plays in the 3S concept and how to support the development of the infrastructure necessary to support safeguards. The objective of this paper has been to provide a working definition of safeguards infrastructure, and to discuss xamples of how building safeguards infrastructure is presented in several models. The guidelines outlined in the milestones document provide a clear path for establishing both the safeguards and the related infrastructures needed to support the development of nuclear power. The model employed by the INSEP program of engaging with partner states on safeguards-related topics that are of current interest to the level of nuclear development in that state provides another way of approaching the concept of building safeguards infrastructure. The Next Generation Safeguards Initiative is yet another approach that underscored five principal areas for growth, and the United States commitment to working with partners to promote this growth both at home and abroad.

Stevens, Rebecca S [Los Alamos National Laboratory; Mcclelland - Kerr, John [NNSA/NA-242

2009-01-01T23:59:59.000Z

14

Developing the Next Generation of International Safeguards and Nonproliferation Experts: Highlights of Select Activities at the National Laboratories  

SciTech Connect (OSTI)

With many safeguards experts in the United States at or near retirement age, and with the growing and evolving mission of international safeguards, attracting and educating a new generation of safeguards experts is an important element of maintaining a credible and capable international safeguards system. The United States National Laboratories, with their rich experience in addressing the technical and policy challenges of international safeguards, are an important resource for attracting, educating, and training future safeguards experts. This presentation highlights some of the safeguards education and professional development activities underway at the National Laboratories. These include university outreach, summer courses, internships, mid-career transition, knowledge retention, and other projects. The presentation concludes with thoughts on the challenge of interdisciplinary education and the recruitment of individuals with the right balance of skills and backgrounds are recruited to meet tomorrow's needs.

Reed, J; Mathews, C; Kirk, B; Lynch, P; Doyle, J; Meek, E; Pepper, S; Metcalf, R

2010-03-31T23:59:59.000Z

15

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)  

SciTech Connect (OSTI)

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

16

Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative  

SciTech Connect (OSTI)

A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

2009-01-01T23:59:59.000Z

17

BN-350 unattended safeguards system current status and initial fuel movement data  

SciTech Connect (OSTI)

The Unattended and Remote Monitoring (UNARM) system at the BN-350 fast breeder reactor facility in Aktau, Kazakhstan continues to provide safeguards monitoring data as the spent fuel disposition project transitions from wet fuel storage to dry storage casks. Qualitative data from the initial cask loading procedures has been released by the International Atomic Energy Agency (IAEA) and is presented here for the first time. The BN-350 fast breeder reactor in Aktau, Kazakhstan, operated as a plutonium-producing facility from 1973 W1til 1999. Kazakhstan signed the Nonproliferation Treaty (NPT) in February 1994, and shortly afterwards the IAEA began safeguarding the reactor facility and its nuclear material. Slnce the cessation of reactor operations ten years ago, the chief proliferation concern has been the spent fuel assemblies stored in the pond on-site. By 2002, all fuel assemblies in wet storage had been repackaged into proliferation-resistant canisters. From the beginning, the IAEA's safeguards campaign at the BN-350 included a constant unattended sensor presence in the form of UNARM which monitors nuclear material activities at the facility in the absence of inspector presence. The UNARM equipment at the BN-350 was designed to be modular and extensible, allowing the system to adapt as the safeguards requirements change. This has been particularly important at the BN-350 due to the prolonged wet storage phase of the project. The primary function of the BN-350 UNARM system is to provide the IAEA with an independent, radiation-centric Containment and Surveillance (C&S) layer in addition to the standard seals and video systems. The UNARM system has provided continuous Continuity of Knowledge (COK) data for the BN-350's nuclear material storage areas in order to ensure the validity of the attended measurements during the lifetime of the project. The first of these attended measurements was characterization of the spent fuel assemblies. This characterization utilized the Spent Fuel Coincidence Counter (SFCC) instrument [ref] to measure neutron multiplicity and calculate Pu mass. These calculated masses were then compared to modeling simulation of the assemblies as well as declarations from the facility in order to baseline the amount of material under IAEA safeguards [ref]. Once the baseline was established, bundles of four or six assemblies were repackaged into proliferati n-resistant canisters. This provided an additional physical barrier to material diversion and provided further protection by choosing assemblies for each canister so that the overall dose rate met self-protection requirements. Each of the canisters were then characterized using a similar technique to the SFCC, but with the Spent Fuel Attribute Monitor (SPAM) instnunent (ref). The data from these measurements were then used to calculate an attribute proportional to the total Pu mass in each canister. This attribute was then compared to the know Pu mass of each assembly in order to verify the accuracy of SPAM. In the event that COK is lost, the SPAM detector remains positioned to reverify Pu content of individual canisters without requiring the canister to be opened.

Williams, Richard Brady [Los Alamos National Laboratory; Browne, Michael C [Los Alamos National Laboratory; Parker, Robert F [Los Alamos National Laboratory; Ingegneri, Maurizio [IAEA

2009-01-01T23:59:59.000Z

18

NNSA Next Generation Safeguards Initiative | National Nuclear Security  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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19

Next Generation Safeguards Initiative Inaugural Conference | Department of  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

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20

FUTURE POWER GRID INITIATIVE Next Generation Network  

E-Print Network [OSTI]

FUTURE POWER GRID INITIATIVE Next Generation Network Simulations for Power System Applications MANAGEMENT The Next Generation Network Simulator is a framework for the partitioning, distribution, and run Grid Initiative (FPGI) will deliver next-generation concepts and tools for grid operation and planning

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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21

Safeguards Culture  

SciTech Connect (OSTI)

The concepts of nuclear safety and security culture are well established; however, a common understanding of safeguards culture is not internationally recognized. Supported by the National Nuclear Security Administration, the authors prepared this report, an analysis of the concept of safeguards culture, and gauged its value to the safeguards community. The authors explored distinctions between safeguards culture, safeguards compliance, and safeguards performance, and evaluated synergies and differences between safeguards culture and safety/security culture. The report concludes with suggested next steps.

Frazar, Sarah L.; Mladineo, Stephen V.

2012-07-01T23:59:59.000Z

22

Achieving the Benefits of Safeguards by Design  

SciTech Connect (OSTI)

The overarching driver for developing a formalized process to achieve safeguards by design is to support the global growth of nuclear power while reducing ‘nuclear security’ risks. This paper discusses an institutional approach to the design process for a nuclear facility, for designing proliferation resistance, international safeguards and U.S. national safeguards and security into new nuclear facilities. In the United States, the need exists to develop a simple, concise, formalized, and integrated approach for incorporating international safeguards and other non-proliferation considerations into the facility design process. An effective and efficient design process is one which clearly defines the functional requirements at the beginning of the project and provides for the execution of the project to achieve a reasonable balance among competing objectives in a cost effective manner. Safeguards by Design is defined as “the integration of international and national safeguards, physical security and non-proliferation features as full and equal partners in the design process of a nuclear energy system or facility,” with the objective to achieve facilities that are intrinsically more robust while being less expensive to safeguard and protect. This Safeguards by Design process has been developed such that it: • Provides improved safeguards, security, and stronger proliferation barriers, while reducing the life cycle costs to the operator and regulatory agencies, • Can be translated to any international context as a model for nuclear facility design, • Fosters a culture change to ensure the treatment of ‘nuclear security’ considerations as “full and equal” partners in the design process, • Provides a useful tool for the project manager responsible for the design, construction, and start-up of nuclear facilities, and • Addresses the key integration activities necessary to efficiently incorporate International Atomic Energy Agency safeguards into the design of nuclear facilities. This paper describes the work that has been completed in the development of a Safeguards by Design process for a project, illustrated by flow diagrams based upon the project phases described in U.S. Department of Energy Order 413.3A, Program and Project Management for the Acquisition of Capital Assets. The institutionalization of the Safeguards by Design process directly supports the goals of the Next Generation Safeguards Initiative and also aligns with goals and objectives of the International Atomic Energy Agency. Other benefits from institutionalizing this Safeguards by Design process are discussed within this paper.

Trond Bjornard; Robert Bean; David Hebditch; Jim Morgan; Bruce Meppen; Scott DeMuth; Michael Ehinger; John Hockert

2008-07-01T23:59:59.000Z

23

The safeguards options study  

SciTech Connect (OSTI)

The Safeguards Options Study was initiated to aid the International Safeguards Division (ISD) of the DOE Office of Arms Control and Nonproliferation in developing its programs in enhanced international safeguards. The goal was to provide a technical basis for the ISD program in this area. The Safeguards Options Study has been a cooperative effort among ten organizations. These are Argonne National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Mound Laboratory, Oak Ridge National Laboratory, Pacific Northwest Laboratories, Sandia National Laboratories, and Special Technologies Laboratory. Much of the Motivation for the Safeguards Options Study is the recognition after the Iraq experience that there are deficiencies in the present approach to international safeguards. While under International Atomic Energy Agency (IAEA) safeguards at their declared facilities, Iraq was able to develop a significant weapons program without being noticed. This is because negotiated safeguards only applied at declared sites. Even so, their nuclear weapons program clearly conflicted with Iraq`s obligations under the Nuclear Nonproliferation Treaty (NPT) as a nonnuclear weapon state.

Hakkila, E.A.; Mullen, M.F.; Olinger, C.T.; Stanbro, W.D. [Los Alamos National Lab., NM (United States); Olsen, A.P.; Roche, C.T.; Rudolph, R.R. [Argonne National Lab., IL (United States); Bieber, A.M.; Lemley, J. [Brookhaven National Lab., Upton, NY (United States); Filby, E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

1995-04-01T23:59:59.000Z

24

Training in Environmental Analyses for Safeguards  

SciTech Connect (OSTI)

Responding to recommendations of the DOE/NNSA's Next Generation Safeguards Initiative, a new course, Training in Environmental Sample Analysis for IAEA Safeguards, is being offered as a summer internship opportunity at Lawrence Livermore National Laboratory. The first students completed the 8 week program during the summer of 2008. Interns are given training in the analysis of bulk environmental samples for safeguards through hands-on experience working in a clean laboratory, purifying U and Pu from bulk environmental samples, and measuring U and Pu isotope ratios by multi-collector ICP mass spectrometry. A series of lectures by invited safeguards and non-proliferation experts gives the students a broad picture of the safeguards work of the IAEA. At the end of the course, the students prepare a poster of their work to showcase at LLNL's summer student poster symposium. Both undergraduate and graduate students are recruited and hired as paid interns under the aegis of the Glenn T. Seaborg Institute in the Physical and Life Sciences Directorate at LLNL. This training course seeks to introduce students to analytical and interpretive skill-sets that are not generally taught at universities, and to encourage them to pursue careers with the IAEA.

Williams, R W; Gaffney, A M; Hutcheon, N A; Kersting, A B

2009-05-28T23:59:59.000Z

25

Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities  

SciTech Connect (OSTI)

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

2009-09-01T23:59:59.000Z

26

Improving the Safeguardability of Nuclear Facilities  

SciTech Connect (OSTI)

The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to reduce security risks and proliferation hazards while improving the synergy of major design features and raising operational efficiency, in a world where significant expansion of nuclear energy use may occur. Correspondingly, the U.S. DOE’s Next Generation Safeguards Initiative (NGSI) includes objectives to contribute to international efforts to develop SBD, and to apply SBD in the development of new U.S. nuclear infrastructure. Here, SBD is defined as a structured approach to ensure the timely, efficient and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The SBD process, in its simplest form, may be applied usefully today within most national regulatory environments. Development of a mature approach to implementing SBD requires work in the areas of requirements definition, design processes, technology and methodology, and institutionalization. The U.S. efforts described in this paper are supportive of SBD work for international safeguards that has recently been initiated by the IAEA with the participation of many stakeholders including member States, the IAEA, nuclear technology suppliers, nuclear utilities, and the broader international nonproliferation community.

T. Bjornard; R. Bari; D. Hebditch; P. Peterson; M. Schanfein

2009-07-01T23:59:59.000Z

27

Measuring Safeguards Culture  

SciTech Connect (OSTI)

As the International Atomic Energy Agency (IAEA) implements a State Level Approach to its safeguards verification responsibilities, a number of countries are beginning new nuclear power programs and building new nuclear fuel cycle faculties. The State Level approach is holistic and investigatory in nature, creating a need for transparent, non-discriminatory judgments about a state's nonproliferation posture. In support of this need, the authors previously explored the value of defining and measuring a state's safeguards culture. We argued that a clear definition of safeguards culture and an accompanying set of metrics could be applied to provide an objective evaluation and demonstration of a country's nonproliferation posture. As part of this research, we outlined four high-level metrics that could be used to evaluate a state's nuclear posture. We identified general data points. This paper elaborates on those metrics, further refining the data points to generate a measurable scale of safeguards cultures. We believe that this work could advance the IAEA's goals of implementing a safeguards system that is fully information driven, while strengthening confidence in its safeguards conclusions.

Frazar, Sarah L.; Mladineo, Stephen V.

2011-07-19T23:59:59.000Z

28

Next GeNeratioN SafeGuardS iNitiative  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of the Yucca0Administration

29

Safeguards and security by design (SSBD) for the domestic threat - theft and sabotage  

SciTech Connect (OSTI)

Safeguards by Design (SBD) is receiving significant interest with respect to international safeguards objectives. However, less attention has been focused on the equally important topic of domestic Safeguards and Security by Design (SSBD), which addresses requirements such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful to nuclear explosives purposes, domestic Material Protection, Control and Accounting measures (MPC&A) are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (SBD) concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE) and more specifically its Fuel Cycle Research and Development (FCRD) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA for international safeguards. This activity includes the participation of industry (through DOE-sponsored contracts) and DOE National Laboratories. This paper will identify the key domestic safeguards and security requirements (i.e. MC&A and physical protection) and explain how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems.

Demuth, Scott F [Los Alamos National Laboratory; Mullen, Mark [Los Alamos National Laboratory

2011-10-05T23:59:59.000Z

30

Safeguards-by-Design: An Element of 3S Integration  

SciTech Connect (OSTI)

In 2008, the “20/20 Vision for the Future” background report by the IAEA Director General identified the possibility of integrating certain activities related to safeguards, safety, and security. Later in the year, the independent Commission report prepared at the request of the IAEA Director General noted that the Agency’s roles in nuclear safeguards, safety, and security (3S) complement and can mutually reinforce each other. Safeguards-by-design (SBD) is a practical measure that strengthens 3S integration, especially for the stage of nuclear facility design and construction, but also with ramifications for other stages of the facility life-cycle. This paper describes the SBD concept, with examples for diverse regulatory environments, being developed in the U.S under the U.S. Department of Energy (DOE) Next Generation Safeguards Initiative and the Advanced Fuel Cycle Initiative. This is compared with related international SBD work performed in the recent IAEA workshop on “Facility Design and Plant Operation Features that Facilitate the Implementation of IAEA Safeguards”. Potential future directions for further development of SBD and its integration within 3S are identified.

R. S. Bean; T. A. Bjornard; D. J. Hebdich

2009-04-01T23:59:59.000Z

31

Integrating Safeguards and Security with Safety into Design  

SciTech Connect (OSTI)

There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed as a structured approach to ensure the timely, efficient, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

Robert S. Bean; John W. Hockert; David J. Hebditch

2009-05-01T23:59:59.000Z

32

Future challenges and DOE/NNSA-JAEA cooperation for the development of advanced safeguards  

SciTech Connect (OSTI)

The United States Department of Energy/National Nuclear Security Administration (DOE/NNSA) has been cooperating with Japan on nuclear safeguards for over thirty years. DOE/NNSA has collaborated with the Japan Atomic Energy Agency (JAEA) and its predecessors in addressing the need for innovative solutions to nuclear transparency and verification issues in one of the world's most advanced nuclear fuel cycle states. This collaboration includes over ninety activities that have involved nearly every facility in the JAEA complex and many national laboratories in the U.S. complex. The partnership has yielded new technologies and approaches that have benefited international safeguards not only in Japan, but around the world. The International Atomic Energy Agency uses a number of safeguards solutions developed under this collaboration to improve its inspection efforts in Japan and elsewhere. Japanese facilities serve as test beds for emerging safeguards technologies and are setting the trend for new nuclear energy and fuel cycle development worldwide. The collaboration continues to be an essential component of U.S. safeguards outreach and is integral to the DOE/NNSA's Next Generation Safeguards Initiative. In addition to fostering international safeguards development, the cooperation is an opportunity for U.S. scientists to work in facilities that have no analog in the United States, thus providing crucial real-life experience for and aiding development of the next generation of U.S. safeguards specialists. It is also an important element of promoting regional transparency thereby building confidence in the peaceful nature of nuclear programs in the region. The successes engendered by this partnership provide a strong basis for addressing future safeguards challenges, in Japan and elsewhere. This paper summarizes these challenges and the associated cooperative efforts that are either underway or anticipated.

Stevens, Rebecca S [Los Alamos National Laboratory; Mc Clelland - Kerr, John [NNSA-NA-242; Senzaki, Masao [JAEA; Hori, Masato [JAEA

2009-01-01T23:59:59.000Z

33

Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors  

SciTech Connect (OSTI)

Safeguards by Design (SbD) is a well-known paradigm for consideration and incorporation of safeguards approaches and associated design features early in the nuclear facility development process. This paradigm has been developed as part of the Next Generation Safeguards Initiative (NGSI), and has been accepted as beneficial in many discussions and papers on NGSI or specific technologies under development within NGSI. The Office of Nuclear Safeguards and Security funded the Pacific Northwest National Laboratory to examine the business case justification of SbD for nuclear power reactors. Ultimately, the implementation of SbD will rely on the designers of nuclear facilities. Therefore, it is important to assess the incentives which will lead designers to adopt SbD as a standard practice for nuclear facility design. This report details the extent to which designers will have compelling economic incentives to adopt SbD.

Wood, Thomas W.; Seward, Amy M.; Lewis, Valerie A.; Gitau, Ernest TN; Zentner, Michael D.

2012-12-01T23:59:59.000Z

34

The U.S./IAEA Workshop on Software Sustainability for Safeguards Instrumentation  

SciTech Connect (OSTI)

The U.S. National Nuclear Security Administration’s Next Generation Safeguards Initiative, the U.S. Department of State, and the International Atomic Energy Agency (IAEA) organized a a workshop on the subject of ”Software Sustainability for Safeguards Instrumentation.” The workshop was held at the Vienna International Centre in Vienna, Austria, May 6-8, 2014. The workshop participants included software and hardware experts from national laboratories, industry, government, and IAEA member states who were specially selected by the workshop organizers based on their experience with software that is developed for the control and operation of safeguards instrumentation. The workshop included presentations, to orient the participants to the IAEA Department of Safeguards software activities related to instrumentation data collection and processing, and case studies that were designed to inspire discussion of software development, use, maintenance, and upgrades in breakout sessions and to result in recommendations for effective software practices and management. This report summarizes the results of the workshop.

Pepper S. E.; .; Worrall, L.; Pickett, C.; Bachner, K.; Queirolo, A.

2014-08-08T23:59:59.000Z

35

International Safeguards Technology and Policy Education and Training Pilot Programs  

SciTech Connect (OSTI)

A major focus of the National Nuclear Security Administration-led Next Generation Safeguards Initiative (NGSI) is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. NNSA launched two pilot programs in 2008 to develop university level courses and internships in association with James, Martin Center for Nonproliferation Studies (CNS) at the Monterey Institute of International Studies (MIIS) and Texas A&M University (TAMU). These pilot efforts involved 44 students in total and were closely linked to hands-on internships at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). The Safeguards and Nuclear Material Management pilot program was a collaboration between TAMU, LANL, and LLNL. The LANL-based coursework was shared with the students undertaking internships at LLNL via video teleconferencing. A weeklong hands-on exercise was also conducted at LANL. A second pilot effort, the International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at MIIS in cooperation with LLNL. Speakers from MIIS, LLNL, and other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students were senior classmen or new master's degree graduates from MIIS specializing in nonproliferation policy studies. The two pilots programs concluded with an NGSI Summer Student Symposium, held at LLNL, where 20 students participated in LLNL facility tours and poster sessions. The value of bringing together the students from the technical and policy pilots was notable and will factor into the planning for the continued refinement of the two programs in the coming years.

Dreicer, M; Anzelon, G A; Essner, J T; Dougan, A D; Doyle, J; Boyer, B; Hypes, P; Sokava, E; Wehling, F; Martin, J; Charlton, W

2009-06-16T23:59:59.000Z

36

REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS  

SciTech Connect (OSTI)

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future. Consequently, the NNSA Office of International Regimes and Agreements (NA-243) sponsored a team of U.S. Department of Energy National Laboratory nuclear safeguards experts and technologists to conduct a workshop on methods and technologies for improving this activity, under the ASA-100 Advanced Safeguards Approaches Project. The workshop focused on reviewing and discussing the fundamental safeguards needs, and presented technology and/or methods that could potentially address those needs more effectively and efficiently. Conclusions and Recommendations for technology to enhance the performance of DIV inspections are presented by the workshop team.

Richard Metcalf; Robert Bean

2009-10-01T23:59:59.000Z

37

Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Pebble Fuel  

SciTech Connect (OSTI)

The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on pebble fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC.

Philip Casey Durst; Mark Schanfein

2012-08-01T23:59:59.000Z

38

Nuclear Resonance Fluorescence for Safeguards Applications  

SciTech Connect (OSTI)

In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of {gamma} rays with specific energies that are characteristic of the emitting isotope. The promise of NRF as a non-destructive analysis technique (NDA) in safeguards applications lies in its potential to directly quantify a specific isotope in an assay target without the need for unfolding the combined responses of several fissile isotopes as often required by other NDA methods. The use of NRF for detection of sensitive nuclear materials and other contraband has been researched in the past. In the safeguards applications considered here one has to go beyond mere detection and precisely quantify the isotopic content, a challenge that is discussed throughout this report. Basic NRF measurement methods, instrumentation, and the analytical calculation of NRF signal strengths are described in Section 2. Well understood modeling and simulation tools are needed for assessing the potential of NRF for safeguards and for designing measurement systems. All our simulations were performed with the radiation transport code MCNPX, a code that is widely used in the safeguards community. Our initial studies showed that MCNPX grossly underestimated the elastically scattered background at backwards angles due to an incorrect treatment of Rayleigh scattering. While new, corrected calculations based on ENDF form factors showed much better agreement with experimental data for the elastic scattering of photons on an uranium target, the elastic backscatter is still not rigorously treated. Photonuclear scattering processes (nuclear Thomson, Delbruck and Giant Dipole Resonance scattering), which are expected to play an important role at higher energies, are not yet included. These missing elastic scattering contributions were studied and their importance evaluated evaluated against data found in the literature as discussed in Section 3. A transmission experiment was performed in September 2009 to test and demonstrate the applicability of the method to the quantitative measurement of an isotope of interest embedded in a thick target. The experiment, data analysis, and results are described in Section 4. The broad goal of our NRF studies is to assess the potential of the technique in safeguards applications. Three examples are analyzed in Section 5: the isotopic assay of spent nuclear fuel (SNF), the measurement of {sup 235}U enrichment in UF{sub 6} cylinders, and the determination of {sup 239}Pu in mixed oxide (MOX) fuel. The study of NRF for the assay of SNF assemblies was supported by the Next Generation Safeguards Initiative (NGSI) of the U.S. Department of Energy as part of a large multi-lab/university effort to quantify the plutonium (Pu) mass in spent nuclear fuel assemblies and to detect the diversion of pins with non-destructive assay (NDA) methods. NRF is one of 14 NDA techniques being researched. The methodology for performing and analyzing quantitative NRF measurements was developed for determining Pu mass in SNF and is extensively discussed in this report. The same methodology was applied to the assessment of NRF for the measurement of {sup 235}U enrichment and the determination of {sup 239}Pu in MOX fuel. The analysis centers on determining suitable NRF measurement methods, measurement capabilities that could be realized with currently available instrumentation, and photon source and detector requirements for achieving useful NDA capabilities.

Ludewigt, Bernhard A; Quiter, Brian J; Ambers, Scott D

2011-02-04T23:59:59.000Z

39

Sustaining International CBRN Centers of Excellence with a Focus on Nuclear Security and Safeguards: Initial Scoping Session London, 23-24 September 2013 SUMMARY REPORT  

SciTech Connect (OSTI)

This report provides a summary-level description of the key information, observations, ideas, and recommendations expressed during the subject meeting. The report is organized to correspond to the meeting agenda provided in Appendix 1 and includes references to several of the participants listed in Appendix 2 .The meeting venue was Lloyd’s Register in the City of London. Lloyd’s Register graciously accommodated the request of The Pacific Northwest Laboratory (PNNL) with whom it works on various safeguards activities commissioned by NNSA. PNNL and NNSA also shared the goal of the meeting/study with the United Kingdom (UK) Foreign and Commonwealth Office (FCO) and the Department of Energy and Climate Change with whom they coordinated the participant list.

Anderson, Roger G.; Frazar, Sarah L.

2013-12-12T23:59:59.000Z

40

Eastern Renewable Generation Integration Study: Initial Results (Poster)  

SciTech Connect (OSTI)

This poster presents an overview of the Eastern Renewable Generation Integration Study, which aims to answer critical questions about the future of the Eastern Interconnection under high levels of solar and wind generation penetration.

Bloom, A.; Townsend, A.; Hummon, M.; Weekley, A.; Clark, K.; King, J.

2013-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

AFCI Safeguards Enhancement Study: Technology Development Roadmap  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Initiative (AFCI) Safeguards Campaign aims to develop safeguards technologies and processes that will significantly reduce the risk of proliferation in the U.S. nuclear fuel cycle of tomorrow. The Safeguards Enhancement Study was chartered with identifying promising research and development (R&D) directions over timescales both near-term and long-term, and under safeguards oversight both domestic and international. This technology development roadmap documents recognized gaps and needs in the safeguarding of nuclear fuel cycles, and outlines corresponding performance targets for each of those needs. Drawing on the collective expertise of technologists and user-representatives, a list of over 30 technologies that have the potential to meet those needs was developed, along with brief summaries of each candidate technology. Each summary describes the potential impact of that technology, key research questions to be addressed, and prospective development milestones that could lead to a definitive viability or performance assessment. Important programmatic linkages between U.S. agencies and offices are also described, reflecting the emergence of several safeguards R&D programs in the U.S. and the reinvigoration of nuclear fuel cycles across the globe.

Smith, Leon E.; Dougan, A.; Tobin, Stephen; Cipiti, B.; Ehinger, Michael H.; Bakel, A. J.; Bean, Robert; Grate, Jay W.; Santi, P.; Bryan, Steven; Kinlaw, M. T.; Schwantes, Jon M.; Burr, Tom; Lehn, Scott A.; Tolk, K.; Chichester, David; Menlove, H.; Vo, D.; Duckworth, Douglas C.; Merkle, P.; Wang, T. F.; Duran, F.; Nakae, L.; Warren, Glen A.; Friedrich, S.; Rabin, M.

2008-12-31T23:59:59.000Z

42

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish the policy and responsibilities for the Department of Energy safeguards and security program. Does not cancel another directive. Canceled by DOE O 5630.11A dated 12-7-92.

1988-01-22T23:59:59.000Z

43

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order establishes roles and responsibilities for the Department of Energy Safeguards and Security Program. Cancels DOE O 470.4. Canceled by DOE O 470.4B

2007-05-25T23:59:59.000Z

44

Safeguards Envelope Methodology  

E-Print Network [OSTI]

Nuclear safeguards are intrinsic and extrinsic features of a facility which reduce probability of the successful acquisition of special nuclear material (SNM) by hostile actors. Future bulk handling facilities in the United States will include both...

Metcalf, Richard

2012-02-14T23:59:59.000Z

45

Technology transfer significance of the International Safeguards Project Office  

SciTech Connect (OSTI)

The safeguards implemented by the International Atomic Energy Agency (IAEA) are of major importance to the non-proliferation objectives of the United States of America and other nations of the world. Assurance of safeguards effectiveness is mandatory to continued peaceful use of nuclear power. To enhance the ability of the IAEA to apply safeguards effectively, and to ensure that the IAEA does not lack technical assistance in critical areas, the US Congress has made available a special authorization for a Program for Technical Assistance to IAEA Safeguards (POTAS). This substantial program of technology transfer was initiated in 1976. The United States Departments of State and Energy, the Arms control and Disarmament Agency and the Nuclear Regulatory Commission have each accepted responsibility for parts of the Program for Technical Assistance to IAEA Safeguards. Funding is provided by state through the Foreign Assistance Act. This report provides a discussion of this program.

Marcuse, W.; Waligura, A.J.

1988-06-01T23:59:59.000Z

46

The future of IAEA safeguards: challenges and responses  

SciTech Connect (OSTI)

For nearly two decades, the International Atomic Energy Agency (lAEA) has been transforming its safeguards system to address the challenges posed by undeclared nuclear programs, the associated revelation of an extensive non-State nuclear procurement network and other issues, including past limits to its verification mandate and the burden of noncompliance issues. Implementing the new measures, including those in the Additional Protocol, and integrating new and old safeguards measures, remains a work in progress. Implementation is complicated by factors including the limited teclmological tools that are available to address such issues as safeguarding bulk handling facilities, detection of undeclared facilities/activities, especially related to enrichment, etc. As this process continues, new challenges are arising, including the demands of expanding nuclear power production worldwide, so-called safeguards by design for a new generation of facilities, the possible IAEA role in a fissile material cutoff treaty and other elements of the arms control and disarmament agenda, the possible role in 'rollback' cases, etc. There is no doubt safeguards will need to evolve in the future, as they have over the last decades. In order for the evolutionary path to proceed, there will inter alia be a need to identify technological gaps, especially with respect to undeclared facilities, and ensure they are filled by adapting old safeguards technologies, by developing and introducing new and novel safeguards teclmologies and/or by developing new procedures and protocols. Safeguards will also need to respond to anticipated emerging threats and to future, unanticipated threats. This will require strategic planning and cooperation among Member States and with the Agency. This paper will address challenges to IAEA safeguards and the technological possibilities and R&D strategies needed to meet those challenges in the context of the forty-year evolution of safeguards, including the ongoing transformation of safeguards by the Agency.

Pilat, Joseph F [Los Alamos National Laboratory; Budlong - Sylvester, Kory W [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

47

Safeguard Security and Awareness Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Provides detailed requirements and procedures to supplement DOE O 470.1, Safeguards and Security Program, Chapter IV.

2002-10-02T23:59:59.000Z

48

Safeguards and Security Program References  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual establishes definitions for terms related to the Department of Energy Safeguards and Security (S&S) Program and includes lists of references and acronyms/abbreviations applicable to S&S Program directives. Cancels the Safeguards and Security Glossary of Terms, dated 12-18-95. Current Safeguards and Security Program References can also be found at Safeguards and Security Policy Information Resource (http://pir.pnl.gov/)

2005-08-26T23:59:59.000Z

49

Safeguards Laboratory (SL) | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGEComplainant,.VisitorSafeguards &Safeguards

50

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish responsibilities for the U.S. Department of Energy (DOE) Safeguards and Security (S&S) Program, and to establish program planning and management requirements for the S&S Program. Cancels DOE O 470.4A, DOE M 470.4-1, Chg. 2, and DOE O 142.1.

2011-07-21T23:59:59.000Z

51

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes roles and responsibilities for the Department of Energy Safeguards and Security Program. Cancels: DOE O 470.1, DOE O 471.2A, DOE O 471.4, DOE O 472.1C, DOE O 473.1, DOE O 473.2, DOE O 474.1A. Canceled by DOE O 470.4A.

2005-08-26T23:59:59.000Z

52

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Safeguards and Security Program ensures that the Department of Energy efficiently and effectively meets all its obligations to protect Special Nuclear Material, other nuclear materials, classified matter, sensitive information, government property, and the safety and security of employees, contractors, and the general public. Cancels DOE P 470.1.

2010-12-29T23:59:59.000Z

53

and Pollutant Safeguarding Buildings  

E-Print Network [OSTI]

commercial buildings, these flows are driven primarily by the building's ventilation system, but natural2004 Airflow and Pollutant Transport Group Safeguarding Buildings Against Chemical and Biological research since 1998 to protect buildings and building occupants from threats posed by airborne chemical

54

Separations and safeguards model integration.  

SciTech Connect (OSTI)

Research and development of advanced reprocessing plant designs can greatly benefit from the development of a reprocessing plant model capable of transient solvent extraction chemistry. This type of model can be used to optimize the operations of a plant as well as the designs for safeguards, security, and safety. Previous work has integrated a transient solvent extraction simulation module, based on the Solvent Extraction Process Having Interaction Solutes (SEPHIS) code developed at Oak Ridge National Laboratory, with the Separations and Safeguards Performance Model (SSPM) developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The goal of this work was to strengthen the integration by linking more variables between the two codes. The results from this integrated model show expected operational performance through plant transients. Additionally, ORIGEN source term files were integrated into the SSPM to provide concentrations, radioactivity, neutron emission rate, and thermal power data for various spent fuels. This data was used to generate measurement blocks that can determine the radioactivity, neutron emission rate, or thermal power of any stream or vessel in the plant model. This work examined how the code could be expanded to integrate other separation steps and benchmark the results to other data. Recommendations for future work will be presented.

Cipiti, Benjamin B.; Zinaman, Owen

2010-09-01T23:59:59.000Z

55

Enhanced safeguards via solution monitoring  

SciTech Connect (OSTI)

Solution monitoring is defined as the essentially continuous monitoring of solution level, density, and temperature in all tanks in the process that contain, or could contain, safeguards-significant quantities of nuclear material. This report describes some of the enhancements that solution monitoring could make to international safeguards. The focus is on the quantifiable benefits of solution monitoring, but qualitatively, solution monitoring can be viewed as a form of surveillance. Quantitatively, solution monitoring can in some cases improve diversion detection probability. For example, the authors show that under certain assumptions, solution monitoring can be used to reduce the standard deviation of the annual material balance, {sigma}{sub MB}, from approximately 17 kg to approximately 4 kg. Such reduction in {sigma}{sub MB} will not always be possible, as they discuss. However, in all cases, solution monitoring would provide assurance that the measurement error models are adequate so that one has confidence in his estimate of {sigma}{sub MB}. Some of the results in this report were generated using data that were simulated with prototype solution monitoring software that they are developing. An accompanying document describes that software.

Burr, T.; Wangen, L.

1996-09-01T23:59:59.000Z

56

Nuclear Safeguards Considerations For The Pebble Bed Modular Reactor (PBMR)  

SciTech Connect (OSTI)

High temperature reactors (HTRs) have been considered since the 1940s, and have been constructed and demonstrated in the United Kingdom (Dragon), United States (Peach Bottom and Fort Saint Vrain), Japan (HTTR), Germany (AVR and THTR-300), and have been the subject of conceptual studies in Russia (VGM). The attraction to these reactors is that they can use a variety of reactor fuels, including abundant thorium, which upon reprocessing of the spent fuel can produce fissile U-233. Hence, they could extend the stocks of available uranium, provided the fuel is reprocessed. Another attractive attribute is that HTRs typically operate at a much higher temperature than conventional light water reactors (LWRs), because of the use of pyrolytic carbon and silicon carbide coated (TRISO) fuel particles embedded in ceramic graphite. Rather than simply discharge most of the unused heat from the working fluid in the power plant to the environment, engineers have been designing reactors for 40 years to recover this heat and make it available for district heating or chemical conversion plants. Demonstrating high-temperature nuclear energy conversion was the purpose behind Fort Saint Vrain in the United States, THTR-300 in Germany, HTTR in Japan, and HTR-10 and HTR-PM, being built in China. This resulted in nuclear reactors at least 30% or more thermodynamically efficient than conventional LWRs, especially if the waste heat can be effectively utilized in chemical processing plants. A modern variant of high temperature reactors is the Pebble Bed Modular Reactor (PBMR). Originally developed in the United States and Germany, it is now being redesigned and marketed by the Republic of South Africa and China. The team examined historical high temperature and high temperature gas reactors (HTR and HTGR) and reviewed safeguards considerations for this reactor. The following is a preliminary report on this topic prepared under the ASA-100 Advanced Safeguards Project in support of the NNSA Next Generation Safeguards Initiative (NGSI).

Phillip Casey Durst; David Beddingfield; Brian Boyer; Robert Bean; Michael Collins; Michael Ehinger; David Hanks; David L. Moses; Lee Refalo

2009-10-01T23:59:59.000Z

57

International Internships in Nuclear Safeguards and Security: Challenges and Successes  

SciTech Connect (OSTI)

All students in the Russian safeguards and security degree programs at the National Research Nuclear University MEPhI and Tomsk Polytechnic University, sponsored by the Material Protection, Control and Accounting (MPC&A) Education Project, take part in a domestic internship at a Russian enterprise or facility. In addition, a select few students are placed in an international internship. These internships provide students with a better view of how MPC&A and nonproliferation in general are addressed outside of Russia. The possibility of an international internship is a significant incentive for students to enroll in the safeguards and security degree programs. The U.S. members of the MPC&A Education Project team interview students who have been nominated by their professors. These students must have initiative and reasonable English skills. The project team and professors then select students to be tentatively placed in various international internships during the summer or fall of their final year of study. Final arrangements are then made with the host organizations. This paper describes the benefits of the joint United States/Russia cooperation for next-generation workforce development, some of the international internships that have been carried out, the benefits of these international internships, and lessons learned in implementing them.

Duncan, Cristen L.; Heinberg, Cynthia L.; Killinger, Mark H.; Goodey, Kent O.; Kryuchkov, Eduard F.; Geraskin, Nikolai I.; Silaev, Maxim E.; Sokova, Elena K.; Ford, David G.

2010-04-20T23:59:59.000Z

58

Statistics applied to safeguards  

SciTech Connect (OSTI)

Statistical methods are central to safeguards work. Measurements forming the basis of much materials accountancy are not perfect - ``perfect`` in the sense of being error free. Other sessions in this course address the destructive and nondestructive measurement of nuclear material, together with the inherent limitations in those measurements. The bottom line is that measurement errors are a fact of life and, since we can`t eliminate them, we have to find a rational way to deal with them. Which leads to the world of statistics. Beyond dealing with measurement errors, another area of statistical application involves the sampling of items for verification. Inspectors from the IAEA and domestic regulatory agencies periodically visit operating facilities and make measurements of selected items. By comparing their own measured values to those declared by the facilities, increased confidence is obtained. If verification measurements were not expensive, time consuming, and disruptive to operations, perhaps verification of 100% of the inventories would be desirable. In reality, many constraints lead to inspection of only a portion of those inventories. Drawing inferences about a larger ``population`` of declared items in a facility based on verification information obtained from a sample of those items is a statistical problem. There are few texts on statistics in safeguards. The lengthy exposition ``IAEA Safeguards: Statistical Concepts and Techniques`` and the US NRC book edited by Bowen and Bennet are two good sources of general information. In the next section, the subject of measurement quality is addressed. The third section covers the evaluation of MUFs, and discusses the related subjects of error propagation and sequential analysis. The final section covers verification, inspection sample size calculations, and the D statistic. The text is written at an elementary level, with references to the safeguards literature for more detailed treatment.

Picard, R.R.

1993-05-01T23:59:59.000Z

59

Statistics applied to safeguards  

SciTech Connect (OSTI)

Statistical methods are central to safeguards work. Measurements forming the basis of much materials accountancy are not perfect - perfect'' in the sense of being error free. Other sessions in this course address the destructive and nondestructive measurement of nuclear material, together with the inherent limitations in those measurements. The bottom line is that measurement errors are a fact of life and, since we can't eliminate them, we have to find a rational way to deal with them. Which leads to the world of statistics. Beyond dealing with measurement errors, another area of statistical application involves the sampling of items for verification. Inspectors from the IAEA and domestic regulatory agencies periodically visit operating facilities and make measurements of selected items. By comparing their own measured values to those declared by the facilities, increased confidence is obtained. If verification measurements were not expensive, time consuming, and disruptive to operations, perhaps verification of 100% of the inventories would be desirable. In reality, many constraints lead to inspection of only a portion of those inventories. Drawing inferences about a larger population'' of declared items in a facility based on verification information obtained from a sample of those items is a statistical problem. There are few texts on statistics in safeguards. The lengthy exposition IAEA Safeguards: Statistical Concepts and Techniques'' and the US NRC book edited by Bowen and Bennet are two good sources of general information. In the next section, the subject of measurement quality is addressed. The third section covers the evaluation of MUFs, and discusses the related subjects of error propagation and sequential analysis. The final section covers verification, inspection sample size calculations, and the D statistic. The text is written at an elementary level, with references to the safeguards literature for more detailed treatment.

Picard, R.R.

1993-01-01T23:59:59.000Z

60

PIA - Savannah River Nuclear Solutions Electronic Safeguards...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Solutions Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions...

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Generation and Initial Evolution of a Mode Water S Anomaly* GREGORY C. JOHNSON  

E-Print Network [OSTI]

Generation and Initial Evolution of a Mode Water ­S Anomaly* GREGORY C. JOHNSON NOAA/Pacific Marine. Corresponding author address: Dr. Gregory C. Johnson, NOAA/PMEL, 7600 Sand Point Way NE, Bldg. 3, Seattle, WA 98115-6349. E-mail: gregory.c.johnson@noaa.gov APRIL 2006

Johnson, Gregory C.

62

Full spectrum optical safeguard  

DOE Patents [OSTI]

An optical safeguard device with two linear variable Fabry-Perot filters aligned relative to a light source with at least one of the filters having a nonlinear dielectric constant material such that, when a light source produces a sufficiently high intensity light, the light alters the characteristics of the nonlinear dielectric constant material to reduce the intensity of light impacting a connected optical sensor. The device can be incorporated into an imaging system on a moving platform, such as an aircraft or satellite.

Ackerman, Mark R. (Albuquerque, NM)

2008-12-02T23:59:59.000Z

63

Us-Japan cooperation on safeguards  

SciTech Connect (OSTI)

There is a long history of collaborative safeguards development between the United States and Japan. Japan has built, and continues to expand, the largest civil nuclear fuel cycle under full-scope IAEA safeguards in world. This development has posed unique challenges to the international safeguards system. Safeguards developments made through the US-Japan cooperation to address these unique challenges have significantly impacted the technologies deployed for international safeguards applications around the world.

Beddingfield, David H [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Hori, Masato [JAEA; Kawakubo, Yoko [JAEA; Mcclelland - Kerr, J [NNSA

2009-01-01T23:59:59.000Z

64

Master Safeguards and Security Agreements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish the Department of Energy policy, requirements, responsibilities, and authorities for the development and implementation of Master Safeguards and Security Agreements (MSSA's). Does not cancel another directive. Canceled by DOE O 5630.13A

1988-02-03T23:59:59.000Z

65

Reactor safeguards against insider sabotage  

SciTech Connect (OSTI)

A conceptual safeguards system is structured to show how both reactor operations and physical protection resources could be integrated to prevent release of radioactive material caused by insider sabotage. Operational recovery capabilities are addressed from the viewpoint of both detection of and response to disabled components. Physical protection capabilities for preventing insider sabotage through the application of work rules are analyzed. Recommendations for further development of safeguards system structures, operational recovery, and sabotage prevention are suggested.

Bennett, H.A.

1982-03-01T23:59:59.000Z

66

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Ensures appropriate levels of protection against unauthorized access; theft, diversion, loss of custody, or destruction of nuclear weapons, or weapons components; espionage; loss or theft of classified matter or Government property; and other hostile acts that may cause unacceptable adverse impacts on national security or on the health and safety of Department of Energy (DOE) and contractor employees, the public, or the environment. DOE O 470.1 Extended until 5-11-06 by DOE N 251.63, dated 5-11-05. Chg 1, Safeguards and Security Program, dated 9/28/95, extended by DOE N 251.57, dated 4/28/2004. Change 1, 5/21/96, revises Chapter IV. Cancels: DOE 5630.11B, DOE 5630.13A, DOE 5630.14A, DOE 5630.15, DOE 5630.16A, DOE 5630.17, DOE 5631.1C, DOE 5631.4A, DOE 5634.1B, DOE 5634.3, DOE 5639.3, DOE M 5632.1C-1 in part.

1995-09-28T23:59:59.000Z

67

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation  

E-Print Network [OSTI]

With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

68

Safeguards and Security Program, acronyms and abbereviations...  

Office of Environmental Management (EM)

Program, acronyms and abbereviations - DOE M 470.4-7 Safeguards and Security Program, acronyms and abbereviations - DOE M 470.4-7 August 26, 2005 Canceled Safeguards and Security...

69

UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...  

National Nuclear Security Administration (NNSA)

UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email:...

70

Long-term proliferation and safeguards issues in future technologies  

SciTech Connect (OSTI)

The purpose of the task was to assess the effect of potential new technologies, nuclear and non-nuclear, on safeguards needs and non-proliferation policies, and to explore possible solutions to some of the problems envisaged. Eight subdivisions were considered: New Enrichment Technologies; Non-Aqueous Reprocessing Technologies; Fusion; Accelerator-Driven Reactor Systems; New Reactor Types; Heavy Water and Deuterium; Long-Term Storage of Spent Fuel; and Other Future Technologies (Non-Nuclear). For each of these subdivisions, a careful review of the current world-wide effort in the field provided a means of subjectively estimating the viability and qualitative probability of fruition of promising technologies. Technologies for which safeguards and non-proliferation requirements have been thoroughly considered by others were not restudied here (e.g., the Fast Breeder Reactor). The time scale considered was 5 to 40 years for possible initial demonstration although, in some cases, a somewhat optimistic viewpoint was embraced. Conventional nuclear-material safeguards are only part of the overall non-proliferation regime. Other aspects are international agreements, export controls on sensitive technologies, classification of information, intelligence gathering, and diplomatic initiatives. The focus here is on safeguards, export controls, and classification.

Keisch, B.; Auerbach, C.; Fainberg, A.; Fiarman, S.; Fishbone, L.G.; Higinbotham, W.A.; Lemley, J.R.; O'Brien, J.

1986-02-01T23:59:59.000Z

71

Generation and focusing of electron beams with initial transverse-longitudinal correlation  

SciTech Connect (OSTI)

In charged particle beams, one of the roles played by space charge is to couple the transverse and longitudinal dynamics of the beam. This can lead to very complex phenomena which are generally studied using computer simulations. However, in some cases models based on phenomenological or analytic approximations can provide valuable insight into the system behavior. In this paper, we employ such approximations to investigate the conditions under which all the slices of a space charge dominated electron beam with slowly varying current could be focused to a waist with the same radius and at the same location, independent of slice current, and show that this can be accomplished approximately if the initial transverse-longitudinal correlation introduced onto the beam by the electron gun is chosen to compensate for the transverse-longitudinal correlation introduced onto the beam in the drift section. The validity of our approximations is assessed by use of progressively more realistic calculations. We also consider several design elements of electron guns that affect the initial correlations in the beams they generate.

Harris, J. R., E-mail: john.harris@colostate.edu [Department of Electrical and Computer Engineering, Colorado State University, Fort Collins, Colorado 80523 (United States); Lewellen, J. W. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Poole, B. R. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)

2014-10-07T23:59:59.000Z

72

Safeguards instrumentation: a computer-based catalog  

SciTech Connect (OSTI)

The information contained in this catalog is needed to provide a data base for safeguards studies and to help establish criteria and procedures for international safeguards for nuclear materials and facilities. The catalog primarily presents information on new safeguards equipment. It also describes entire safeguards systems for certain facilities, but it does not describe the inspection procedures. Because IAEA safeguards do not include physical security, devices for physical protection (as opposed to containment and surveillance) are not included. An attempt has been made to list capital costs, annual maintenance costs, replacement costs, and useful lifetime for the equipment. For equipment which is commercially available, representative sources have been listed whenever available.

Fishbone, L.G.; Keisch, B.

1981-08-01T23:59:59.000Z

73

Nuclear materials safeguards for the future  

SciTech Connect (OSTI)

Basic concepts of domestic and international safeguards are described, with an emphasis on safeguards systems for the fuel cycles of commercial power reactors. Future trends in institutional and technical measures for nuclear materials safeguards are outlined. The conclusion is that continued developments in safeguards approaches and technology, coupled with institutional measures that facilitate the global management and protection of nuclear materials, are up to the challenge of safeguarding the growing inventories of nuclear materials in commercial fuel cycles in technologically advanced States with stable governments that have signed the nonproliferation treaty. These same approaches also show promise for facilitating international inspection of excess weapons materials and verifying a fissile materials cutoff convention.

Tape, J.W.

1995-12-31T23:59:59.000Z

74

Nuclear material safeguards for enrichments plants: Part 4, Gas Centrifuge Enrichment Plant: Diversion scenarios and IAEA safeguards activities: Safeguards training course  

SciTech Connect (OSTI)

This publication is Part 4 of a safeguards training course in Nuclear Material Safeguards for enrichment plants. This part of the course deals with diversion scenarios and safeguards activities at gas centrifuge enrichment plants.

Not Available

1988-10-01T23:59:59.000Z

75

Automatic Generation of Initial Weights and Estimation of Hidden Units for Pattern Classifcation Using Neural Networks   

E-Print Network [OSTI]

This study high lights on the subject of weight initialization in back-propagation feed-forward networks. Training data is analyzed and the notion of critical points is introduced for determining the initial weights and ...

Keeni, Kanad; Nakayama, Kenji; Shimodaira, Hiroshi

76

Simulation Enabled Safeguards Assessment Methodology  

SciTech Connect (OSTI)

It is expected that nuclear energy will be a significant component of future supplies. New facilities, operating under a strengthened international nonproliferation regime will be needed. There is good reason to believe virtual engineering applied to the facility design, as well as to the safeguards system design will reduce total project cost and improve efficiency in the design cycle. Simulation Enabled Safeguards Assessment MEthodology (SESAME) has been developed as a software package to provide this capability for nuclear reprocessing facilities. The software architecture is specifically designed for distributed computing, collaborative design efforts, and modular construction to allow step improvements in functionality. Drag and drop wireframe construction allows the user to select the desired components from a component warehouse, render the system for 3D visualization, and, linked to a set of physics libraries and/or computational codes, conduct process evaluations of the system they have designed.

Robert Bean; Trond Bjornard; Thomas Larson

2007-09-01T23:59:59.000Z

77

Safeguards and Security Program - DOE Directives, Delegations...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

ARCHIVED DOE O 470.1 Chg 1, Safeguards and Security Program by Website Administrator Functional areas: Environment, Safety, and Health, Hazardous Materials, Radiation Protection,...

78

Methodology for predicting torsional fatigue life of turbine generator shafts using crack initiation plus propagation. Final report  

SciTech Connect (OSTI)

An overall methodology now exists that addresses both crack initiation and propagation in predicting the fatigue life of large turbine generator shafts. It can estimate previous torsional transient damage and predict residual life. In short, this improved methodology allows utilities to determine the availability of turbogenerators with greater confidence.

Anderson, A.F.; Williams, R.A.; Wilkening, W.W.; LeFort, P.N.

1985-11-01T23:59:59.000Z

79

ORO Office Safeguards and Security Clearance Tracking System...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Office Safeguards and Security Clearance Tracking System and Visitor Control System PIA, Oak Ridge Operations Office ORO Office Safeguards and Security Clearance Tracking System...

80

Proceedings of the Advisory Committee on Reactor Safeguards Safety...  

Broader source: Energy.gov (indexed) [DOE]

Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop December 16,...

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Safeguards and Security Independent Oversight Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes the DOE Safeguards and Security Independent Oversight Program that provides DOE and contractor managers, Congress, and other stakeholders with an independent evaluation of the effectiveness of DOE safeguards and security policy and programs, and the implementation of those policies and programs. Cancels DOE 5630.12A.

1998-12-23T23:59:59.000Z

82

Nuclear Safeguards and Security Challenge:  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&D ConsortiumNuclearSafeguards and Security Challenge:

83

Safeguards and security issues during facility transition  

SciTech Connect (OSTI)

The transition of Department of Energy (DOE) production facilities to those destined for decontamination and decommissioning (D and D) must consider traditional safeguards and security requirements governing nuclear materials. Current DOE safeguards and security policy establishes specific requirements for the removal of facilities and waste from safeguards. However, the current physical security policy does not differentiate the protection of waste from usable materials. Other transition issues include: access of uncleared individuals, positioning security zones, nuclear material holdup, accounting for difficult-to-measure materials, inventory difference and resolution, and radiological/toxicological sabotage. Safeguards and security goals for facility transitioning must provide a workable, efficient and cost-effective system for accounting and protecting nuclear material. In depth protection strategies utilizing combinations of safeguards and security systems should be developed to meet these goals.

Smith, M.R. [USDOE Office of Safeguards and Security, Washington, DC (United States); Zack, N.R. [Los Alamos National Lab., NM (United States). Safeguards Systems Group

1993-12-31T23:59:59.000Z

84

Determining information management needs for enhanced international safeguards  

SciTech Connect (OSTI)

The Safeguards Information Management System initiative is a program of the Department of Energy`s (DOE) Office of Arms Control and Nonproliferation aimed at supporting the International Atomic Energy Agency`s (IAEA) efforts to strengthen safeguards through the enhancement of information management capabilities. The DOE hopes to provide the IAEA with the ability to correlate and analyze data from existing and new sources of information, including publicly available information, information on imports and exports, design information, environmental monitoring data, and non-safeguards information. The first step in this effort is to identify and define IAEA requirements. In support of this, we have created a users` requirements document based on interviews with IAEA staff that describes the information management needs of the end user projected by the IAEA, including needs for storage, retrieval, analysis, communication, and visualization of data. Also included are characteristics of the end user and attributes of the current environment. This paper describes our efforts to obtain the required information. We discuss how to accurately represent user needs and involve users for an international organization with a multi-cultural user population. We describe our approach, our experience in setting up and conducting the interviews and brainstorming sessions, and a brief discussion of what we learned.

Badalamente, R.V. [Pacific Northwest Lab., Richland, WA (United States); DeLand, S.M. [Sandia National Labs., Albuquerque, NM (United States); Whiteson, R. [Los Alamos National Lab., NM (United States); Anzelon, G. [Lawrence Livermore National Lab., CA (United States)

1994-08-01T23:59:59.000Z

85

Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.  

SciTech Connect (OSTI)

The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS requirements can be incorporated into the pre-conceptual through early facility design stages, seeking a cost-effective design that meets both operational efficiencies and the regulatory environment. The larger scope of the project, i.e., in future stages, includes the identification of potentially conflicting requirements identified by the ISOSS framework, including an analysis of how regulatory requirements may be changed to account for the intrinsic features of SMRs.

Middleton, Bobby D.; Mendez, Carmen Margarita [Sociotecnia Solutions] [Sociotecnia Solutions

2013-10-01T23:59:59.000Z

86

safeguards  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF8/%2A ennike |1/%2A en9/%2Arussia |/%2A

87

Overview of the Facility Safeguardability Analysis (FSA) Process  

SciTech Connect (OSTI)

Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

2012-08-01T23:59:59.000Z

88

IAEA Safeguards: Past, Present, and Future  

SciTech Connect (OSTI)

This talk will present an overview of the International Atomic Energy Agency with a specific focus on its international safeguards mission and activities. The talk will first present a brief history of the IAEA and discuss its current governing structure. It will then focus on the Safeguards Department and its role in providing assurance that nuclear materials are being used for peaceful purposes. It will then look at how the IAEA is currently evolving the way in which it executes its safeguards mission with a focus on the idea of a state-level approach.

Santi, Peter A. [Los Alamos National Laboratory; Hypes, Philip A. [Los Alamos National Laboratory

2012-06-14T23:59:59.000Z

89

Generation of Initial Kinetic Distributions for Simulation of Long-Pulse Charged Particle Beams with High Space-Charge intensity  

SciTech Connect (OSTI)

Self-consistent Vlasov-Poisson simulations of beams with high space-charge intensity often require specification of initial phase-space distributions that reflect properties of a beam that is well adapted to the transport channel--both in terms of low-order rms (envelope) properties as well as the higher-order phase-space structure. Here, we first review broad classes of kinetic distributions commonly in use as initial Vlasov distributions in simulations of unbunched or weakly bunched beams with intense space-charge fields including: the Kapchinskij-Vladimirskij (KV) equilibrium, continuous-focusing equilibria with specific detailed examples, and various non-equilibrium distributions, such as the semi-Gaussian distribution and distributions formed from specified functions of linear-field Courant-Snyder invariants. Important practical details necessary to specify these distributions in terms of usual accelerator inputs are presented in a unified format. Building on this presentation, a new class of approximate initial kinetic distributions are constructed using transformations that preserve linear-focusing single-particle Courant-Snyder invariants to map initial continuous-focusing equilibrium distributions to a form more appropriate for non-continuous focusing channels. Self-consistent particle-in-cell simulations are employed to show that the approximate initial distributions generated in this manner are better adapted to the focusing channels for beams with high space-charge intensity. This improved capability enables simulation applications that more precisely probe intrinsic stability properties and machine performance.

Lund, Steven M.; Kikuchi, Takashi; Davidson, Ronald C.

2007-04-03T23:59:59.000Z

90

Generation of initial Vlasov distributions for simulation of charged particle beams with high space-charge intensity  

SciTech Connect (OSTI)

Self-consistent Vlasov simulations of beams with high space-charge intensity often require specification of initial phase-space distributions that reflect properties of a beam that is well adapted to the transport channel, both in terms of low-order rms (envelope) properties as well as the higher-order phase-space structure. Here, we first review broad classes of distributions commonly in use as initial Vlasov distributions in simulations of beams with intense space-charge fields including: the Kapchinskij-Vladimirskij (KV) equilibrium, continuous-focusing equilibria with specific detailed examples, and various non-equilibrium distributions, such as the semi-Gaussian distribution and distributions formed from specified functions of linear-field Courant-Snyder invariants. Important practical details necessary to specify these distributions in terms of usual accelerator inputs are presented in a unified format. Building on this presentation, a new class of approximate initial distributions are constructed using transformations that preserve linear-focusing single-particle Courant-Snyder invariants to map initial continuous-focusing equilibrium distributions to a form more appropriate for non-continuous focusing channels. Self-consistent particle-in-cell simulations are employed to show that the approximate initial distributions generated in this manner are better adapted to the focusing channels for beams with high space-charge intensity. This improved capability enables simulation applications that more precisely probe intrinsic stability properties and machine performance.

Lund, S M; Kikuchi, T; Davidson, R C

2007-04-12T23:59:59.000Z

91

International Nuclear Safeguards Inspection Support Tool  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is committed to developing technologies to meet escalating requirements for the International Atomic Energy Agency (IAEA) Non-Proliferation Treaty (NPT) monitoring and associated inspections. This commitment involves the customization and transfer of existing remote monitoring/information management technologies for use by the IAEA. This paper describes an information management system called INSIST International Nuclear Safeguards Inspection Support Tool, which was developed by the Pacific Northwest Laboratory (PNL) to support the IAEA Action Team in its role of monitoring and verifying compliance under United Nations Special Commission (UNSC) Resolutions 687, 707, and 715. Initial emphasis was placed on developing and deploying functionality and databases customized to support the Action Team. Throughout the design and customization of INSIST, emphasis was placed on information storage and retrieval capabilities for data gathered by the Action Team. In addition, PNL provided the Action Team with maps and satellite images and other relevant Iraqi databases to further facilitate the following activities: monitoring nuclear activities, facility operations, and nuclear material inventories assisting in inspection planning and training providing post inspection analysis providing onsite inspection support reporting on inspection findings.

Steinmaus, K.L.; Wukelic, G.E.; Beal, O.M.

1994-03-01T23:59:59.000Z

92

The Concept of Goals-Driven Safeguards  

SciTech Connect (OSTI)

The IAEA, NRC, and DOE regulations and requirements for safeguarding nuclear material and facilities have been reviewed and each organization’s purpose, objectives, and scope are discussed in this report. Current safeguards approaches are re-examined considering technological advancements and how these developments are changing safeguards approaches used by these organizations. Additionally, the physical protection approaches required by the IAEA, NRC, and DOE were reviewed and the respective goals, objectives, and requirements are identified and summarized in this report. From these, a brief comparison is presented showing the high-level similarities among these regulatory organizations’ approaches to physical protection. The regulatory documents used in this paper have been assembled into a convenient reference library called the Nuclear Safeguards and Security Reference Library. The index of that library is included in this report, and DVDs containing the full library are available.

R. Wigeland; T Bjornard; B. Castle

2009-02-01T23:59:59.000Z

93

Safeguards and Security Program Planning and Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes program planning and management requirements for the Departments Safeguards and Security (S&S) Program. Cancels: DOE N 473.9 and DOE M 470.1-1

2005-08-26T23:59:59.000Z

94

Safeguards and Security Program Planning and Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual establishes program planning and management requirements for the Departments Safeguards and Security. Chg 1, dated 3-7-06 Cancels DOE N 473.9, DOE M 470.1-1 Chg 2.

2005-08-26T23:59:59.000Z

95

Safeguards and Security Program and Project Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The proposed revision to this Department of Energy Guide focuses on alignment of guidance for implementing key safeguard and security components to the DOE capital asset acquisition process with the revised DOE O 413.3B, Program and Project Management for Acquisition of Capital Assets, the revised DOE O 470.4B, Safeguard and Security Program, and the new series of DOE Orders replacing the DOE M 470.4 series of manuals.

2013-04-18T23:59:59.000Z

96

Integrated Safeguards and Security Management (ISSM) Policy  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The purpose of this Policy is to formalize an Integrated Safeguards and Security Management (ISSM) framework. Safeguards and security management systems provide a formal, organized process for planning, performing, assessing, and improving the secure conduct of work in accordance with risk-based protection strategies. These systems are institutionalized through Department of Energy (DOE) directives and contracts. Does not cancel other directives. Canceled by DOE P 470.1A.

2001-05-08T23:59:59.000Z

97

Advanced Safeguards Approaches for New Reprocessing Facilities  

SciTech Connect (OSTI)

U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-06-24T23:59:59.000Z

98

Coupling a transient solvent extraction module with the separations and safeguards performance model.  

SciTech Connect (OSTI)

A number of codes have been developed in the past for safeguards analysis, but many are dated, and no single code is able to cover all aspects of materials accountancy, process monitoring, and diversion scenario analysis. The purpose of this work was to integrate a transient solvent extraction simulation module developed at Oak Ridge National Laboratory, with the Separations and Safeguards Performance Model (SSPM), developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The SSPM was designed for materials accountancy and process monitoring analyses, but previous versions of the code have included limited detail on the chemical processes, including chemical separations. The transient solvent extraction model is based on the ORNL SEPHIS code approach to consider solute build up in a bank of contactors in the PUREX process. Combined, these capabilities yield a more robust transient separations and safeguards model for evaluating safeguards system design. This coupling and initial results are presented. In addition, some observations toward further enhancement of separations and safeguards modeling based on this effort are provided, including: items to be addressed in integrating legacy codes, additional improvements needed for a fully functional solvent extraction module, and recommendations for future integration of other chemical process modules.

DePaoli, David W. (Oak Ridge National Laboratory, Oak Ridge, TN); Birdwell, Joseph F. (Oak Ridge National Laboratory, Oak Ridge, TN); Gauld, Ian C. (Oak Ridge National Laboratory, Oak Ridge, TN); Cipiti, Benjamin B.; de Almeida, Valmor F. (Oak Ridge National Laboratory, Oak Ridge, TN)

2009-10-01T23:59:59.000Z

99

Safeguards by design - industry engagement for new uranium enrichment facilities in the United States  

SciTech Connect (OSTI)

The United States Department of Energy's (DOE's) Office of Nonproliferation and International Security (NA-24) has initiated a Safeguards by Design (SBD) effort to encourage the incorporation of international (IAEA) safeguards features early in the design phase of a new nuclear facility in order to avoid the need to redesign or retrofit the facility at a later date. The main goals of Safeguards by Design are to (1) make the implementation of international safeguards at new civil nuclear facilities more effective and efficient, (2) avoid costly and time-consuming re-design work or retrofits at such facilities and (3) design such facilities in a way that makes proliferation as technically difficult, as time-consuming, and as detectable as possible. The U.S. Nuclear Regulatory Commission (NRC) has recently hosted efforts to facilitate the use of Safeguards by Design for new uranium enrichment facilities currently being planned for construction in the U.S. While SBD is not a NRC requirement, the NRC is aiding the implementation of SBD by coordinating discussions between DOE's NA-24 and industry's facility design teams. More specifically, during their normal course of licensing discussions the NRC has offered industry the opportunity to engage with NA-24 regarding SBD.

Demuth, Scott F [Los Alamos National Laboratory; Grice, Thomas [NRC; Lockwood, Dunbar [DOE/NA-243

2010-01-01T23:59:59.000Z

100

The state-level approach: moving beyond integrated safeguards  

SciTech Connect (OSTI)

The concept of a State-Level Approach (SLA) for international safeguards planning, implementation, and evaluation was contained in the Conceptual Framework for Integrated Safeguards (IS) agreed in 2002. This paper describes briefly the key elements of the SLA, including State-level factors and high-level safeguards objectives, and considers different cases in which application of the SLA methodology could address safeguards for 'suspect' States, 'good' States, and Nuclear Weapons States hosting fuel cycle centers. The continued use and further development of the SLA to customize safeguards for each State, including for States already under IS, is seen as central to effective and efficient safeguards for an expanding nuclear world.

Tape, James W [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

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101

IMPACT OF THE U.S. SUPPORT PROGRAM SAFEGUARDS INTERNSHIP PROGRAM.  

SciTech Connect (OSTI)

The U.S. Support Program began funding an internship program in the IAEA Department of Safeguards in 2002. Since that time, 39 U.S. citizens and permanent residents have been placed in one-year, paid internships with the IAEA. The management of the internship program was originally the responsibility of the International Safeguards Project Office but was transferred to the Office of Educational Programs at Brookhaven National Laboratory in 2004. Feedback on the internship program from the U.S. government and the IAEA has been positive. The interns have completed basic yet essential work for the Department of Safeguards and freed IAEA staff members to perform more complex tasks. The cost of an intern is low relative to other forms of human resources support. After the conclusion of their assignments, many of the interns go on to work for the U.S. government, the national laboratories, or companies in international safeguards and nonproliferation. This paper will discuss the work done by the interns for the IAEA, factors influencing the success of the internship program, and the effects the program has had on the careers of interns, in preparing the next generation to work in the nuclear industry, participation in INMM activities, and recruitment for U.S. citizens for safeguards positions.

PEPPER, S.; OSIECKI, C.

2006-07-16T23:59:59.000Z

102

Fundamentals of materials accounting for nuclear safeguards  

SciTech Connect (OSTI)

Materials accounting is essential to providing the necessary assurance for verifying the effectiveness of a safeguards system. The use of measurements, analyses, records, and reports to maintain knowledge of the quantities of nuclear material present in a defined area of a facility and the use of physical inventories and materials balances to verify the presence of special nuclear materials are collectively known as materials accounting for nuclear safeguards. This manual, prepared as part of the resource materials for the Safeguards Technology Training Program of the US Department of Energy, addresses fundamental aspects of materials accounting, enriching and complementing them with the first-hand experiences of authors from varied disciplines. The topics range from highly technical subjects to site-specific system designs and policy discussions. This collection of papers is prepared by more than 25 professionals from the nuclear safeguards field. Representing research institutions, industries, and regulatory agencies, the authors create a unique resource for the annual course titled ''Materials Accounting for Nuclear Safeguards,'' which is offered at the Los Alamos National Laboratory.

Pillay, K.K.S. (comp.)

1989-04-01T23:59:59.000Z

103

Antineutrino reactor safeguards - a case study  

E-Print Network [OSTI]

Antineutrinos have been proposed as a means of reactor safeguards for more than 30 years and there has been impressive experimental progress in neutrino detection. In this paper we conduct, for the first time, a case study of the application of antineutrino safeguards to a real-world scenario - the North Korean nuclear crisis in 1994. We derive detection limits to a partial or full core discharge in 1989 based on actual IAEA safeguards access and find that two independent methods would have yielded positive evidence for a second core with very high confidence. To generalize our results, we provide detailed estimates for the sensitivity to the plutonium content of various types of reactors, including most types of plutonium production reactors, based on detailed reactor simulations. A key finding of this study is that a wide class of reactors with a thermal power of less than 0.1-1 GWth can be safeguarded achieving IAEA goals for quantitative sensitivity and timeliness with detectors right outside the reactor building. This type of safeguards does not rely on the continuity of knowledge and provides information about core inventory and power status in real-time.

Eric Christensen; Patrick Huber; Patrick Jaffke

2014-02-13T23:59:59.000Z

104

Integrated international safeguards concepts for fuel reprocessing  

SciTech Connect (OSTI)

This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility.

Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

1981-12-01T23:59:59.000Z

105

Allocation of inspection resources for international safeguards  

SciTech Connect (OSTI)

Increasing numbers and complexity of facilities inspected by the International Atomic Energy Agency will require difficult decisions about the levels of safeguards to be assigned to materials and facilities should limitations on inspection resources continue. This paper examines some alternative strategies for assigning inspection effort that could improve effectiveness and efficiency of safeguards compared with current inspection practice. These allocation concepts are: (1) extension of inspection planning to include material strata and accounting areas that encompass multiple facilities and (2) the use of randomization of the quality and frequency of inspections and inspection activities.

Markin, J.T.

1987-01-01T23:59:59.000Z

106

Safeguards and Security Program Planning and Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual establishes program planning and management requirements for the Department’s Safeguards and Security (S&S) Program. Change 2 is a revision to Section M of both the Manual and the CRD to realign the process for establishing deviations from DOE directives containing safeguards and security requirements to reflect established Departmental policy as set forth in DOE O 251.1C. Original publication, 8-26-05; Chg 1, 3-7-06. Canceled by DOE O 470.4B

2005-08-26T23:59:59.000Z

107

Safeguards and Security Systems | ornl.gov  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwardsSafeguards and Security Systems SHARE Safeguards

108

Evaluating safeguard effectiveness against violent insiders  

SciTech Connect (OSTI)

The threat posed by a violent insiders presents a major challenge to safeguards managers. These insiders, in addition to their ability to exploit their special authorities, access, and knowledge of facility operations and safeguards, could use violence to defeat safeguards components and personnel. In protecting against theft of special nuclear material, facilities have emphasized the use of perimeter protection and physical barriers to protect against attacks by an outsider adversary group. Recently emphasis has begun to shift toward the implementation of hardware and procedural measures to protect against nonviolent insiders. Approaches are also needed to help assess the effectiveness of protection against those insiders who are willing to use violence. In this paper we describe an approach we're developing for dealing with violent insiders. We begin by categorizing insiders according to whether they are active or passive, rational or irrational, and whether they are willing to use force against safeguards components or coworkers. We define characteristics of each category, and describe the extent to which each category is adequately modelled by existing evaluation tools. We also discuss several modelling issues posed by active insiders, including: entry of contraband; reluctance to use violence; neutralization of insiders; and the ability to switch modes of attack between force, stealth, and deceit. 5 refs., 2 figs.

Al-Ayat, R.A.; Fortney, D.S.

1990-07-16T23:59:59.000Z

109

Advanced Safeguards Approaches for New Fast Reactors  

SciTech Connect (OSTI)

This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-12-15T23:59:59.000Z

110

IBM Software Solution Brief Safeguarding the cloud  

E-Print Network [OSTI]

IBM Software Solution Brief Safeguarding the cloud with IBM Security solutions Maintain visibility and control with proven security solutions for public, private and hybrid clouds Highlights Address cloud internal and external users, data, applications and workloads as they move to and from the cloud Regain

111

Overview of the Facility Safeguardability Analysis (FSA) Process  

SciTech Connect (OSTI)

The safeguards system of the International Atomic Energy Agency (IAEA) provides the international community with credible assurance that a State is fulfilling its nonproliferation obligations. The IAEA draws such conclusions from the evaluation of all available information. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of this “State-level” approach. Efficiently used, the Safeguards by Design (SBD) methodologies , , , now being developed can contribute to effective and cost-efficient facility-level safeguards. The Facility Safeguardability Assessment (FSA) introduced here supports SBD in three areas. 1. It describes necessary interactions between the IAEA, the State regulator, and the owner / designer of a new or modified facility to determine where SBD efforts can be productively applied, 2. It presents a screening approach intended to identify potential safeguard issues for; a) design changes to existing facilities; b) new facilities similar to existing facilities with approved safeguards approaches, and c) new designs, 3. It identifies resources (the FSA toolkit), such as good practice guides, design guidance, and safeguardability evaluation methods that can be used by the owner/designer to develop solutions for potential safeguards issues during the interactions with the State regulator and IAEA. FSA presents a structured framework for the application of the SBD tools developed in other efforts. The more a design evolves, the greater the probability that new safeguards issues could be introduced. Likewise, for first-of-a-kind facilities or research facilities that involve previously unused processes or technologies, it is reasonable to expect that a number of possible safeguards issues might exist. Accordingly, FSA is intended to help the designer and its safeguards experts identify early in the design process: • Areas where elements of previous accepted safeguards approach(es) may be applied to facility modifications or new designs • Modifications of the design that could mitigate a potential safeguards issue or facilitate a more efficient application of the safeguards approach • Possible innovative ideas for more efficient application of safeguards • The potential for changes in elements of the safeguard approach that may be required by IAEA as a result of facility design features and characteristics • Other potential concerns These issues will then be presented to the IAEA and the state regulator to be resolved in a timely manner, ensuring that the planned safeguards approach is acceptable and compatible with the facility design. The proposed approach should be validated by application to suitable facilities to assess its utility, comprehensiveness, and cost-effectiveness. The approach and example application should also be reviewed by industry to confirm the conclusions reached in the DOE review.

Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Shirley J.; Wigeland, Roald; Zentner, Michael D.

2011-10-10T23:59:59.000Z

112

Safeguards and Security progress report, January--December 1989  

SciTech Connect (OSTI)

From January to December 1989, the Los Alamos Safeguards and Security Research and Development (R D) program carried out the activities described in the first four parts of this report: Science and Technology Base Development, Basic Systems Design, Onsite Test and Evaluation and Facility Support, and International Safeguards. For the most part, these activities were sponsored by the Department of Energy's Office of Safeguards and Security. Part 1 covers development of the basic technology essential to continuing improvements in the practice of safeguards and security. It includes our computer security R D and the activities of the DOE Center for Computer Security, which provides the basis for encouraging and disseminating this important technology. Part 2 treats activities aimed at developing methods for designing and evaluating safeguards systems, with special emphasis on the integration of the several subsystems into a real safeguards system. Part 3 describes efforts of direct assistance to the DOE and its contractors and includes consultation on materials control and accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and demonstration of advanced safeguards systems. Part 3 also reports a series of training courses in various aspects of safeguards that makes the technology more accessible to those who must apply it. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Part 5 reports several safeguards-related activities that have sponsors other than the DOE/OSS. 87 refs., 52 figs.

Smith, D.B.; Jaramillo, G.R. (comps.)

1990-11-01T23:59:59.000Z

113

Education in Safeguards and Security Technology Meeting Challenges with Technology and Experience  

SciTech Connect (OSTI)

Education and hands-on experience are crucial to ensuring a workforce of safeguards and security professionals who can meet the challenges currently faced in global nuclear safeguards and security. Global demand for nuclear energy and technology, the new Strategic Arms Reduction Treaty (START), and the cleanup of Cold War facilities have resulted in an increased need for trained safeguards and security personnel. At the same time, the global community is facing a growing shortage of experienced workers with hands-on knowledge of nuclear material processing. Limited access to operating facilities has dramatically reduced the opportunities for next-generation practitioners to obtain hands-on training experience. To address these needs, the Safeguards Technology Integration Center (STIC) at Oak Ridge National Laboratory was created as a Department of Energy User Facility to provide access both to the latest technology and to field-experienced professionals. The STIC provides real-world conditions, process equipment mock-ups, and controlled access to encapsulated radioactive materials (including highly enriched uranium and plutonium) for training and technology evaluation encompassing various techniques and skills, such as Radiation Inspection Systems, Containment and Surveillance Systems, Nondestructive Assay, Security System Performance Testing, and System Design and Analysis. The STIC facilities, laboratories, test beds, and training facilities are described along with the more notable aspects of the training program, which has included more than 1000 participants in the last four years.

Paschal, Linda J [ORNL; Chapman, Jeffrey Allen [ORNL; Rowe, Nathan C [ORNL; Stinson, Brad J [ORNL

2011-01-01T23:59:59.000Z

114

A Monte Carlo based spent fuel analysis safeguards strategy assessment  

SciTech Connect (OSTI)

Safeguarding nuclear material involves the detection of diversions of significant quantities of nuclear materials, and the deterrence of such diversions by the risk of early detection. There are a variety of motivations for quantifying plutonium in spent fuel assemblies by means of nondestructive assay (NDA) including the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguards nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from spent fuel; however, no single NDA technique can, in isolation, quantify elemental plutonium and other actinides of interest in spent fuel. A study has been undertaken to determine the best integrated combination of cost effective techniques for quantifying plutonium mass in spent fuel for nuclear safeguards. A standardized assessment process was developed to compare the effective merits and faults of 12 different detection techniques in order to integrate a few techniques and to down-select among the techniques in preparation for experiments. The process involves generating a basis burnup/enrichment/cooling time dependent spent fuel assembly library, creating diversion scenarios, developing detector models and quantifying the capability of each NDA technique. Because hundreds of input and output files must be managed in the couplings of data transitions for the different facets of the assessment process, a graphical user interface (GUI) was development that automates the process. This GUI allows users to visually create diversion scenarios with varied replacement materials, and generate a MCNPX fixed source detector assessment input file. The end result of the assembly library assessment is to select a set of common source terms and diversion scenarios for quantifying the capability of each of the 12 NDA techniques. We present here the generalized assessment process, the techniques employed to automate the coupled facets of the assessment process, and the standard burnup/enrichment/cooling time dependent spent fuel assembly library. We also clearly define the diversion scenarios that will be analyzed during the standardized assessments. Though this study is currently limited to generic PWR assemblies, it is expected that the results of the assessment will yield an adequate spent fuel analysis strategy knowledge that will help the down-select process for other reactor types.

Fensin, Michael L [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Sandoval, Nathan P [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

115

SRS delayed neutron instruments for safeguards measurements  

SciTech Connect (OSTI)

Six analytical systems measuring delayed neutrons have been used for safeguards measurements at the Savannah River Site (SRS). A predecessor, the 252Cf Activation Analysis Facility installed at the Savannah River Technology Center (formally SR Laboratory) has been used since 1974 to analyze small samples, measuring both delayed neutrons and gammas. The six shufflers, plus one currently being fabricated, were developed, designed and fabricated by the LANL N-1 group. These shufflers have provided safeguards measurements of product (2 each), in-process scrap (2 each plus a conceptual replacement) and process waste (2 each plus one being fabricated). One shuffler for scrap assay was the first shuffler to be installed (1978) in a process. Another (waste) was the first installed in a process capable of assaying barrels. A third (waste) is the first pass-through model and a fourth (product) is the most precise ({+-}.12%) and accurate NDA instrument yet produced.

Studley, R.V. [Westinghouse SRC, Aiken, SC (United States)

1993-12-31T23:59:59.000Z

116

Safeguard Requirements for Fusion Power Plants  

SciTech Connect (OSTI)

Nuclear proliferation risks from magnetic fusion energy associated with access to fissile materials can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production and diversion of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state openly produces fissile material in violation of international agreements. The degree of risk in each of these categories is assessed, taking into account both state and non-state actors, and it is found that safeguards are required for fusion energy to be highly attractive from a non-proliferation standpoint. Specific safeguard requirements and R&D needs are outlined for each category of risk, and the technical capability of the ITER experiment, under construction, to contribute to this R&D is noted. A preliminary analysis indicates a potential legal pathway for fusion power systems to be brought under the Treaty for the Non-Proliferation of Nuclear Weapons. "Vertical" proliferation risks associated with tritium and with the knowledge that can be gained from inertial fusion energy R&D are outlined.

Robert J. Goldston and Alexander Glaser

2012-08-10T23:59:59.000Z

117

Safeguards and Security for Program and Project Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Guide provides a methodology for implementing the safeguards and security requirements of DOE O 413.3B. Cancels DOE G 413.3-3.

2013-08-15T23:59:59.000Z

118

FAQS Reference Guide – Safeguards and Security General Technical Base  

Broader source: Energy.gov [DOE]

This reference guide addresses the competency statements in the July 2009 edition of DOE-STD-1123-2009, Safeguards and Security General Technical Base Qualification Standard.

119

Safeguards and Security Oversight and Assessments Implementation Guide  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Guide identifies acceptable methods for implementing the safeguards and security provisions of DOE O 226.1A. Canceled by DOE N 251.80.

2007-12-21T23:59:59.000Z

120

FAQS Job Task Analyses - Safeguards and Security General Technical...  

Broader source: Energy.gov (indexed) [DOE]

Security General Technical Base FAQS Job Task Analyses - Safeguards and Security General Technical Base FAQS Job Task Analyses are performed on the Function Area Qualification...

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Advances toward a transportable antineutrino detector system for reactor monitoring and safeguards  

SciTech Connect (OSTI)

Nuclear reactors have served as the neutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Our SNL/LLNL collaboration has demonstrated that such antineutrino based monitoring is feasible using a relatively small cubic meter scale liquid scintillator detector at tens of meters standoff from a commercial Pressurized Water Reactor (PWR). With little or no burden on the plant operator we have been able to remotely and automatically monitor the reactor operational status (on/off), power level, and fuel burnup. The initial detector was deployed in an underground gallery that lies directly under the containment dome of an operating PWR. The gallery is 25 meters from the reactor core center, is rarely accessed by plant personnel, and provides a muon-screening effect of some 20-30 meters of water equivalent earth and concrete overburden. Unfortunately, many reactor facilities do not contain an equivalent underground location. We have therefore attempted to construct a complete detector system which would be capable of operating in an aboveground location and could be transported to a reactor facility with relative ease. A standard 6-meter shipping container was used as our transportable laboratory - containing active and passive shielding components, the antineutrino detector and all electronics, as well as climate control systems. This aboveground system was deployed and tested at the San Onofre Nuclear Generating Station (SONGS) in southern California in 2010 and early 2011. We will first present an overview of the initial demonstrations of our below ground detector. Then we will describe the aboveground system and the technological developments of the two antineutrino detectors that were deployed. Finally, some preliminary results of our aboveground test will be shown. (authors)

Reyna, D. [Sandia National Laboratories, Livermore, CA 94550 (United States); Bernstein, A. [Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States); Lund, J.; Kiff, S.; Cabrera-Palmer, B. [Sandia National Laboratories, Livermore, CA 94550 (United States); Bowden, N. S.; Dazeley, S.; Keefer, G. [Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States)

2011-07-01T23:59:59.000Z

122

E-Print Network 3.0 - activities safeguards training Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

safeguards training Search Powered by Explorit Topic List Advanced Search Sample search results for: activities safeguards training Page: << < 1 2 3 4 5 > >> 1 Title:...

123

Safeguard By Design Lessons Learned from DOE Experience Integrating Safety into Design  

SciTech Connect (OSTI)

This paper identifies the lessons to be learned for the institutionalization of Safeguards by Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189-2008, Integration of Safety into the Design Process. The experience is valuable because of the similarity of the challenges of integrating safety and safeguards into the design process. The paper reviews the content and development of DOE-STD-1189-2008 from its initial concept in January 2006 to its issuance in March 2008. Lessons learned are identified in the areas of the development and structure of requirements for the SBD process; the target audience for SBD requirements and guidance, the need for a graded approach to SBD, and a possible strategy for development and implementation of SBD within DOE.

Hockert, John; Burbank, Roberta L.

2010-04-13T23:59:59.000Z

124

Safeguards and security modeling for electrochemical plants  

SciTech Connect (OSTI)

Safeguards and security design for reprocessing plants can lead to excessive costs if not incorporated early in the design process. The design for electrochemical plants is somewhat uncertain since these plants have not been built at a commercial scale in the past. The Separation and Safeguards Performance Model (SSPM), developed at Sandia National Laboratories, has been used for safeguards design and evaluation for multiple reprocessing plant types. The SSPM includes the following capabilities: -) spent fuel source term library, -) mass tracking of elements 1-99 and bulk solid/liquids, -) tracking of heat load and activity, -) customisable measurement points, -) automated calculation of ID and error propagation, -) alarm conditions and statistical tests, and -) user-defined diversion scenarios. Materials accountancy and process monitoring data can provide more timely detection of material loss specifically to protect against the insider threat. While the SSPM is capable of determining detection probabilities and examining detection times for material loss scenarios, it does not model the operations or spatial effects for a plant design. The STAGE software was chosen to model the physical protection system. STAGE provides a framework to create end-to-end scalable force-on-force combat simulations. It allows for a complete 3D model of a facility to be designed along with the design of physical protection elements. This software, then, can be used to model operations and response for various material loss scenarios. The future integration of the SSPM model data with the STAGE software will provide a more complete analysis of diversion scenarios to assist plant designers.

Cipiti, B.B.; Duran, F.A.; Mendoza, L.A.; Parks, M.J.; Dominguez, D.; Le, T.D. [Sandia National Laboratories, PO Box 5800 MS 0747, Albuquerque, NM 87185 (United States)

2013-07-01T23:59:59.000Z

125

Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants  

SciTech Connect (OSTI)

This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a legal document. As such, it is written in a legalese that is understood by specialists in international law and treaties, but not by most outside of this field, including designers of nuclear facilities. For this reason, many of the requirements have been simplified and restated. However, in all cases, the relevant source document and passage is noted so that readers may trace the requirement to the source. This is a helpful living guide, since some of these requirements are subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and nuclear facility operators to improve not only the effectiveness of international nuclear safeguards, but also the efficiency. As these improvements are made, the following guidelines should be updated and revised accordingly.

Robert Bean; Casey Durst

2009-10-01T23:59:59.000Z

126

Safeguarding Truck-Shipped Wholesale and Retail Fuels (STSWRF)  

E-Print Network [OSTI]

Safeguarding Truck-Shipped Wholesale and Retail Fuels (STSWRF) Oak Ridge National Laboratory at the wholesaler/distributor level or below. This presents additional challenges in tracking untaxed fuel after approved ORNL's plan to conduct a Phase II Pilot Test titled Safeguarding Truck-Shipped Wholesale

127

NIH POLICY MANUAL 1345 -HANDLING AND SAFEGUARDING OF CONTROLLED SUBSTANCES  

E-Print Network [OSTI]

NIH POLICY MANUAL 1345 - HANDLING AND SAFEGUARDING OF CONTROLLED SUBSTANCES FOR NONHUMAN USE: This Chapter describes NIH policies and procedures for handling and safeguarding controlled substances the chapter in compliance with the NIH Office of Management Assessment standardized format. The revised

Bandettini, Peter A.

128

Safeguards & Security | Department of Energy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGEComplainant,.VisitorSafeguards & Security

129

Fuzzy risk analysis for nuclear safeguards  

SciTech Connect (OSTI)

Analysis of a safeguards system, based on the notion of fuzzy sets and linguistic variables, concerns such as complexity and inherent imprecision in estimating the possibility of loss or compromise. The automated risk analysis allows the risk to be determined for an entire system based on estimates for lowest level components and the component proportion. In addition, for each component (asset) the most effective combination of protection mechanisms against a given set of threats is determined. A distinction between bar and featured risk is made.

Zardecki, A.

1993-01-01T23:59:59.000Z

130

Fuzzy risk analysis for nuclear safeguards  

SciTech Connect (OSTI)

Analysis of a safeguards system, based on the notion of fuzzy sets and linguistic variables, concerns such as complexity and inherent imprecision in estimating the possibility of loss or compromise. The automated risk analysis allows the risk to be determined for an entire system based on estimates for lowest level components and the component proportion. In addition, for each component (asset) the most effective combination of protection mechanisms against a given set of threats is determined. A distinction between bar and featured risk is made.

Zardecki, A.

1993-05-01T23:59:59.000Z

131

Safeguards & Security | National Nuclear Security Administration  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromisingStoriesSANDIA1 0-SA-02 September 2013Safeguards &

132

Safeguards and security progress report, January-December 1985  

SciTech Connect (OSTI)

From January to December 1985, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Safeguards Operations, Security Development and Support, Safeguards Technology Development, and International Support. Part 1 covers efforts of direct assistance to the Department of Energy and Nuclear Regulatory Commission licensee facilities. This assistance includes consultation on materials accounting problems, development and demonstration of specialized techniques and instruments, and comprehensive participation in the design and evaluation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this period was on continuing the activities of the Center for Computer Security, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards and international safeguards for reprocessing plants required a significant portion of our resources. All of these efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

Not Available

1987-03-01T23:59:59.000Z

133

A colalborative environment for information driven safeguards  

SciTech Connect (OSTI)

For two decades, the IAEA has recognized the need for a comprehensive and strongly integrated Knowledge Management system to support its Information Driven Safeguards activities. In the past, plans for the development of such a system have progressed slowly due to concerns over costs and feasibility. In recent years, Los Alamos National Laboratory has developed a knowledge management system that could serve as the basis for an IAEA Collaborative Environment (ICE). The ICE derivative knowledge management system described in this paper addresses the challenge of living in an era of information overload coupled with certain knowledge shortfalls. The paper describes and defines a system that is flexible, yet ensures coordinated and focused collaboration, broad data evaluation capabilities, architected and organized work flows, and improved communications. The paper and demonstration of ICE will utilize a hypothetical scenario to highlight the functional features that facilitate collaboration amongst and between information analysts and inspectors. The scenario will place these two groups into a simulated planning exercise for a safeguards inspection drawing upon past data acquisitions, inspection reports, analyst conclusions, and a coordinated walk-through of a 3-D model of the facility. Subsequent to the conduct of the simulated facility inspection, the detection of an anomaly and pursuit of follow up activities will illustrate the event notification, information sharing, and collaborative capabilities of the system. The use of a collaborative environment such as ICE to fulfill the complicated knowledge management demands of the Agency and facilitate the completion of annual State Evaluation Reports will also be addressed.

Scott, Mark R [Los Alamos National Laboratory; Michel, Kelly D [Los Alamos National Laboratory

2010-09-15T23:59:59.000Z

134

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01T23:59:59.000Z

135

Safeguards Evaluation Method for evaluating vulnerability to insider threats  

SciTech Connect (OSTI)

As protection of DOE facilities against outsiders increases to acceptable levels, attention is shifting toward achieving comparable protection against insiders. Since threats and protection measures for insiders are substantially different from those for outsiders, new perspectives and approaches are needed. One such approach is the Safeguards Evaluation Method. This method helps in assessing safeguards vulnerabilities to theft or diversion of special nuclear meterial (SNM) by insiders. The Safeguards Evaluation Method-Insider Threat is a simple model that can be used by safeguards and security planners to evaluate safeguards and proposed upgrades at their own facilities. The method is used to evaluate the effectiveness of safeguards in both timely detection (in time to prevent theft) and late detection (after-the-fact). The method considers the various types of potential insider adversaries working alone or in collusion with other insiders. The approach can be used for a wide variety of facilities with various quantities and forms of SNM. An Evaluation Workbook provides documentation of the baseline assessment; this simplifies subsequent on-site appraisals. Quantitative evaluation is facilitated by an accompanying computer program. The method significantly increases an evaluation team's on-site analytical capabilities, thereby producing a more thorough and accurate safeguards evaluation.

Al-Ayat, R.A.; Judd, B.R.; Renis, T.A.

1986-01-01T23:59:59.000Z

136

Safeguards and security progress report, January-December 1984  

SciTech Connect (OSTI)

From January to December 1984, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. Part 2 treats activities aimed at the security of information and computer systems. was Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in benefiting from field experiences in operating environments.

Smith, D.B. (comp.)

1986-01-01T23:59:59.000Z

137

The European Safeguards Research and Development Association Addresses Safeguards and Nonproliferation  

SciTech Connect (OSTI)

The renaissance of efforts to expand the use of nuclear energy requires the parallel development of a renewed and more sophisticated work force. Growth in the nuclear sector with high standard of safety, safeguards and security requires skilled staff for design, operations, inspections etc. High-quality nuclear technology educational programs are diminished from past years, and the ability of universities to attract students and to meet future staffing requirements of the nuclear industry is becoming seriously compromised. Thus, education and training in nuclear engineering and sciences is one of the cornerstones for the nuclear sector. Teaching in the nuclear field still seems strongly influenced by national history but it is time to strengthen resources and collaborate. Moreover with the current nuclear security threats it becomes critical that nuclear technology experts master the basic principles not only of safety, but also of nuclear safeguards, nonproliferation and nuclear security. In Europe the European Nuclear Education Network (ENEN) Association has established the certificate 'European Master of Science in Nuclear Engineering (EMSNE)' as the classic nuclear engineering program covering reactor operation and nuclear safety. However, it does not include courses on nonproliferation, safeguards, or dual-use technologies. The lack of education in nuclear safeguards was tackled by the European Safeguards Research and Development Association (ESARDA), through development and implementation of safeguards course modules. Since 2005 the ESARDA Working Group, called the Training and Knowledge Management Working Group, (TKMWG) has worked with the Joint Research Centre (JRC) in Ispra, Italy to organize a Nuclear Safeguards and Nonproliferation course. This five-day course is held each spring at the JRC, and continues to show increasing interest as evidenced by the positive responses of international lecturers and students. The standard set of lectures covers a broad range of subjects, including nuclear material accountancy principles, legal definitions and the regulatory base and inspection tools and techniques. This 60% core part is given by representatives from regulatory bodies (The International Atomic Energy Agency (IAEA), Institute for Radiological Protection and Nuclear Safety, Directorate General for Nuclear Energy and Transport), industry (AREVA, British Nuclear Group), and research (Stockholm University, Hamburg University, Joint Research Centre-Institute of Transuranic Elements, and Joint Research Centre-Institute for the Protection of the Citizen). The remaining part is completed with topical lectures addressed by invited lecturers, such as from Pacific Northwest National Laboratory and the IAEA addressing topics of physical protection, illicit trafficking, the Iraq case study, exercises, including satellite imagery interpretation etc. With this structure of a stable core plus a variable set of invited lectures, the course will remain sustainable and up-to-date. A syllabus provides the students a homogeneous set of information material in nuclear safeguards and nonproliferation matters at the European and international level. In this way, the ESARDA TKMWG aims to contribute to a two-fold scientific-technical and political-juridical education and training.

Janssens-Maenhout, Greet; Kusumi, R.; Daures, Pascal A.; Janssens, Willem; Dickman, Deborah A.

2010-06-16T23:59:59.000Z

138

Safeguards and security progress report, January-December 1983  

SciTech Connect (OSTI)

From January to December 1983, the Los Alamos Safeguards and Security Program was involved in the activities described in the first four parts of this report: Nuclear Facility Support, Security Development and Support, Safeguards Technology Development, and International Safeguards. Part 1 covers efforts of direct assistance to the Department of Energy (DOE) and Nuclear Regulatory Commission (NRC) licensee facilities. This assistance includes consultation on materials accounting problems, development of specialized techniques and instruments, and comprehensive participation in the design and implementation of advanced safeguards systems. In addition, a series of training courses in various aspects of safeguards makes the technology more accessible to those who must apply it. Part 2 treats activities aimed at the security of information and computer systems. Our focus this peiod was on continuing the activities of the Computer Security Center, which provides the basis for encouraging and disseminating this emerging technology, and on the development and demonstration of secure computer systems. Part 3 describes the broad development efforts essential to continuing improvements in the practice of safeguards. Although these projects are properly classified as developmental, they address recognized problems that commonly occur in operating facilities. Finally, Part 4 covers international safeguards activities, including both support to the International Atomic Energy Agency and bilateral exchanges. Enrichment plant safeguards, especially those concerning the Gas Centrifuge Enrichment Plant, required a significant portion of our resources. These efforts are beginning to provide substantial returns on our investment in technology transfer, not only in raising the level of safeguards effectiveness but also in our benefiting from field experiences in operating environments.

Smith, D.B. (comp.)

1984-09-01T23:59:59.000Z

139

Safeguards Approaches for Black Box Processes or Facilities  

SciTech Connect (OSTI)

The objective of this study is to determine whether a safeguards approach can be developed for “black box” processes or facilities. These are facilities where a State or operator may limit IAEA access to specific processes or portions of a facility; in other cases, the IAEA may be prohibited access to the entire facility. The determination of whether a black box process or facility is safeguardable is dependent upon the details of the process type, design, and layout; the specific limitations on inspector access; and the restrictions placed upon the design information that can be provided to the IAEA. This analysis identified the necessary conditions for safeguardability of black box processes and facilities.

Diaz-Marcano, Helly; Gitau, Ernest TN; Hockert, John; Miller, Erin; Wylie, Joann

2013-09-25T23:59:59.000Z

140

Panel on protection and management of plutonium: Subpanel on safeguards and security  

SciTech Connect (OSTI)

Nuclear materials safeguards and security systems are described in the context of the nuclear nonproliferation regime. Materials of interest to safeguards, threats, proposals to strengthen International Atomic Energy Agency safeguards, evolving safeguards issues and requirements, system effectiveness, and elements of a global nuclear materials management regime are discussed. Safeguards are seen as an essential element of nuclear materials management, but not a driver for decisions regarding nuclear power or the disposal of excess weapon nuclear materials.

Tape, J.W.

1995-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Apparatus for safeguarding a radiological source  

DOE Patents [OSTI]

A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

Bzorgi, Fariborz M

2014-10-07T23:59:59.000Z

142

Advanced integrated safeguards using front-end-triggering devices  

SciTech Connect (OSTI)

This report addresses potential uses of front-end-triggering devices for enhanced safeguards. Such systems incorporate video surveillance as well as radiation and other sensors. Also covered in the report are integration issues and analysis techniques.

Howell, J.A.; Whitty, W.J.

1995-12-01T23:59:59.000Z

143

Safeguards for Uranium Extraction (UREX) +1a Process  

E-Print Network [OSTI]

of nuclear material accountancy (MA), containment and surveillance (C/S) and solution monitoring (SM). Facility information was developed for a hypothesized UREX+1a plant with a throughput of 1000 Metric Tons Heavy Metal (MTHM) per year. Safeguard goals...

Feener, Jessica S.

2011-08-08T23:59:59.000Z

144

Development of Pattern Recognition Options for Combining Safeguards Subsystems  

SciTech Connect (OSTI)

This talk reviews project progress in combining process monitoring data and nuclear material accounting data to improve the over nuclear safeguards system. Focus on 2 subsystems: (1) nuclear materials accounting (NMA); and (2) process monitoring (PM).

Burr, Thomas L. [Los Alamos National Laboratory; Hamada, Michael S. [Los Alamos National Laboratory

2012-08-24T23:59:59.000Z

145

FY09 Advanced Instrumentation and Active Interrogation Research for Safeguards  

SciTech Connect (OSTI)

Multiple small-scale projects have been undertaken to investigate advanced instrumentation solutions for safeguard measurement challenges associated with advanced fuel cycle facilities and next-generation fuel reprocessing installations. These activities are in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and its Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. 1) Work was performed in a collaboration with the University of Michigan (Prof. Sara Pozzi, co-PI) to investigate the use of liquid-scintillator radiation detectors for assaying mixed-oxide (MOX) fuel, to characterize its composition and to develop advanced digital pulse-shape discrimination algorithms for performing time-correlation measurements in the MOX fuel environment. This work included both simulations and experiments and has shown that these techniques may provide a valuable approach for use within advanced safeguard measurement scenarios. 2) Work was conducted in a collaboration with Oak Ridge National Laboratory (Dr. Paul Hausladen, co-PI) to evaluate the strengths and weaknesses of the fast-neutron coded-aperture imaging technique for locating and characterizing fissile material, and as a tool for performing hold-up measurements in fissile material handling facilities. This work involved experiments at Idaho National Laboratory, using MOX fuel and uranium metal, in both passive and active interrogation configurations. A complete analysis has not yet been completed but preliminary results suggest several potential uses for the fast neutron imaging technique. 3) Work was carried out to identify measurement approaches for determining nitric acid concentration in the range of 1 – 4 M and beyond. This work included laboratory measurements to investigate the suitability of prompt-gamma neutron activation analysis for this measurement and product reviews of other commercial solutions. Ultrasonic density analysis appears to be the best candidate technology for determining nitric acid concentrations but the PGNAA approach may also be applicable. 4) Work was also carried out to begin investigating the use of remote UV imaging to detect air-ionization induced by alpha particle emission from plutonium. This approach has been shown elsewhere as a useful tool for detecting and quantifying plutonium contamination and has the potential of providing a unique and powerful approach for quantifying hold-up in reprocessing facilities. Based on these simple scoping experiments the potential far-reaching capabilities of the measurement are clear.

D. L. Chichester; S. A. Pozzi; E. H. Seabury; J. L. Dolan; M. Flaska; J. T. Johnson; S. M. Watson; J. Wharton

2009-08-01T23:59:59.000Z

146

Enhanced AFCI Sampling, Analysis, and Safeguards Technology Review  

SciTech Connect (OSTI)

The focus of this study includes the investigation of sampling technologies used in industry and their potential application to nuclear fuel processing. The goal is to identify innovative sampling methods using state of the art techniques that could evolve into the next generation sampling and analysis system for metallic elements. Sampling and analysis of nuclear fuel recycling plant processes is required both to monitor the operations and ensure Safeguards and Security goals are met. In addition, environmental regulations lead to additional samples and analysis to meet licensing requirements. The volume of samples taken by conventional means, can restrain productivity while results samples are analyzed, require process holding tanks that are sized to meet analytical issues rather than process issues (and that create a larger facility footprint), or, in some cases, simply overwhelm analytical laboratory capabilities. These issues only grow when process flowsheets propose new separations systems and new byproduct material for transmutation purposes. Novel means of streamlining both sampling and analysis are being evaluated to increase the efficiency while meeting all requirements for information. This report addresses just a part of the effort to develop and study novel methods by focusing on the sampling and analysis of aqueous samples for metallic elements. It presents an overview of the sampling requirements, including frequency, sensitivity, accuracy, and programmatic drivers, to demonstrate the magnitude of the task. The sampling and analysis system needed for metallic element measurements is then discussed, and novel options being applied to other industrial analytical needs are presented. Inductively coupled mass spectrometry instruments are the most versatile for metallic element analyses and are thus chosen as the focus for the study. Candidate novel means of process sampling, as well as modifications that are necessary to couple such instruments to introduce these samples, are discussed. A suggested path forward based on an automated microchip capillary based sampling system interfaced to the analysis spectrometer is presented. The ability to obtain micro liter volume samples coupled with remote automated means of sample tracking and transport to the instrument would greatly improve analytical efficiency while reducing both personnel exposure and radioactive waste. Application of this sampling technique to new types of mass spectrometers for selective elemental isotopic analysis could also provide significant improvements in safeguards and security analyses.

John Svoboda

2009-09-01T23:59:59.000Z

147

A Hubble Astrometry Initiative: Laying the Foundation for the Next-Generation Proper-Motion Survey of the Local Group  

E-Print Network [OSTI]

High-precision astrometry throughout the Local Group is a unique capability of the Hubble Space Telescope (HST), with potential for transformative science, including constraining the nature of dark matter, probing the epoch of reionization, and understanding key physics of galaxy evolution. While Gaia will provide unparalleled astrometric precision for bright stars in the inner halo of the Milky Way, HST is the only current mission capable of measuring accurate proper motions for systems at greater distances (> 80 kpc), which represents the vast majority of galaxies in the Local Group. The next generation of proper-motion measurements will require long time baselines, spanning many years to decades and possibly multiple telescopes, combining HST with the James Webb Space Telescope (JWST) or the Wide-Field Infrared Survey Telescope (WFIRST). However, the current HST allocation process is not conducive to such multi-cycle/multi-mission science, which will bear fruit primarily over many years. We propose an HST ...

Kallivayalil, Nitya; Simon, Joshua D; Boylan-Kolchin, Michael; Deason, Alis J; Fritz, Tobias K; Geha, Marla; Sohn, Sangmo Tony; Weisz, Daniel R

2015-01-01T23:59:59.000Z

148

Influence of safeguards and fire protection on criticality safety  

SciTech Connect (OSTI)

There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described.

Six, D E

1980-01-01T23:59:59.000Z

149

Termination of Safeguards on ULWBR Material  

SciTech Connect (OSTI)

The Department of Energy (DOE), Office of Environmental Management, has approved the disposition of 31 metric tons of Unirradiated Light Water Breeder Reactor (ULWBR) material in canisters stored within dry wells of the Underground Fuel Storage Facility at the Idaho Nuclear Technology and Engineering Center (INTEC). This unirradiated material consists primarily of ceramic pellets of thorium oxide in stainless steel cladding, but it also contains 300 kilograms of uranium that is 98 wt% U-233. The ULWBR material was not processed at the INTEC because it was incompatible with prior chemical separation schemes. Other economical recovery options have not been identified, and expressions of interest for consolidating the material with existing projects at other DOE sites have not been received. The U-233 could be used for producing the medical isotope Actinium-225, but the proof-of-principle demonstration and follow-on pilot program have not been developed to the point of requiring production quantities of U-233. Consequently, the selected disposition of the ULWBR material was burial as Low Level Waste at the Nevada Test Site (NTS), which required terminating safeguards controls for the contained Category II quantity of Attractiveness Level D special nuclear material (SNM). The requested termination followed the twelve point evaluation criteria of the Historical Defense Program Discard Guidance and included a security analysis for evaluating the risks of theft, diversion, and radiological sabotage associated with the material. Continuity of knowledge in the book inventory was assured by documenting that the original shipper’s measurements accurately reflected the quantities of materials received and that the ULWBR materials had remained under adequate physical protection and had been subject to periodic physical inventories. The method selected for substantiating the book values as the basis for terminating safeguards was the nondestructive assay used during physical inventories. Shipping arrangements included refurbishing a licensed cask to be reused over the duration of the termination process. An accompanying batching plan and shipping schedule were developed to accommodate multiple commercial shipments of Category III quantities of SNM in the selected cask, such that all canisters would be received at NTS prior to the expiration of the nonrenewable cask license.

Ivan R. Thomas; Ernest L. Laible

2008-07-01T23:59:59.000Z

150

NDA safeguards techniques for LMFBR assemblies  

SciTech Connect (OSTI)

The significant safeguards concerns for liquid-metal fast breeder reactors (LMFBRs), and for the LMFBR fuel handling systems are the accountability, surveillance, and identification of fuel and blanket assemblies. The introduction of fuel assemblies with a high content of Pu into the receiving and shipping areas of the LMFBR fuel cycle does allow a more direct near-real-time assay profile of the disposition of Pu. Isotope correlations and neutron assay methods have been investigated and implemented for determining plutonium and burnup in fresh and spent LMFBR fuel assemblies. The methods are based on active and passive neutron coincidence counting (NCC) techniques. Preliminary studies on neutron yield rates from the spontaneous fission of plutonium and curium isotopes have indicated that the NCC system is a most effective measure in the verification of nuclear material flow in assembly form for the entire reactor fuel handling cycle, i.e., from the fresh- to the spent-fuel stage. A consequence of the high plutonium concentration level throughout the fuel irradiation period in an LMFBR, is that the spontaneous fission neutron yield from the 242-curium and 244-curium does not dominate the spontaneous fission neutron yield from the plutonium isotopes in the spent fuel stage.

Persiani, P.J.; Gundy, M.L.

1982-08-01T23:59:59.000Z

151

SAFEGUARDS AND SECURITY INTEGRATION WITH SAFETY ANALYSIS  

SciTech Connect (OSTI)

The objective of this paper is to share the Savannah River Site lessons learned on Safeguards and Security (S&S) program integration with K-Area Complex (KAC) safety basis. The KAC Documented Safety Analysis (DSA), is managed by the Washington Savannah River Company (WSRC), and the S&S program, managed by Wackenhut Services, Incorporated--Savannah River Site (WSI-SRS). WSRC and WSI-SRS developed a contractual arrangement to recognize WSI-SRS requirements in the KAC safety analysis. Design Basis Threat 2003 (DBT03) security upgrades required physical modifications and operational changes which included the availability of weapons which could potentially impact the facility safety analysis. The KAC DSA did not previously require explicit linkage to the S&S program to satisfy the safety analysis. WSI-SRS have contractual requirements with the Department of Energy (DOE) which are separate from WSRC contract requirements. The lessons learned will include a discussion on planning, analysis, approval of the controls and implementation issues.

Hearn, J; James Lightner, J

2007-04-13T23:59:59.000Z

152

Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant  

SciTech Connect (OSTI)

The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

Ehinger, Michael H [ORNL; Johnson, Shirley [Tucker Creek Consulting

2010-02-01T23:59:59.000Z

153

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect (OSTI)

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF – specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as “MOX”. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these “minor actinides” can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

2007-12-15T23:59:59.000Z

154

Task team approach to safeguards and security designs  

SciTech Connect (OSTI)

In 1987, a US Department of Energy (DOE) supported task team was organized at the request of the DOE Idaho Field Office (DOE-ID) to provide support for safeguards and security (S S) designs of the Special Isotope Separation (SIS) facility. Prior to deferral of the project, the SIS facility was to be constructed at the Idaho National Engineering Laboratory (INEL) to produce weapons grade plutonium from DOE owned fuel grade plutonium. The task team was assembled to provide the resources necessary to assure that safeguards and security considerations were included as an integral part of the design of the facility, and that SIS designs would take advantage of available technology in the areas of physical security, measurements, accountability, and material and personnel tracking. The task team included personnel from DOE/Office of Safeguards and Security (DOE-OSS), DOE-ID, DOE contractors, and the national laboratories providing a wide range of expertise and experience. The team reviewed proposed designs and provided recommendations for safeguards and security features in each stage of the design process. The value of this approach to safeguards and security designs will be discussed with respect to benefits, lessons learned, and recommendations for future applications. 5 refs.

Zack, N.R. (Los Alamos National Lab., NM (United States)); Wilkey, D.D. (USDOE Idaho Operations Office, Idaho Falls, ID (United States))

1991-01-01T23:59:59.000Z

155

Safeguards and security research and development progress report, October 1993--September 1994  

SciTech Connect (OSTI)

This report describes the activities carried out by the Los Alamos Safeguards and Security Research and Development (R&D) program from October 1993 through September 1994. The activities presented in the first part of the report were directed primarily to domestic US safeguards applications and were, for the most part, sponsored by the Department of Energy`s Office of Safeguards and Security (DOE/OSS, NN-50). The activities described in Part 2, International Safeguards, were supported by the International Safeguards Division of the Office of Arms Control and Nonproliferation (DOE/OACN, NN-40). Part 3 describes several safeguards or safeguards-related activities that have other sponsors. The final part of the report lists titles and abstracts of Los Alamos safeguards R&D reports, technical journal articles, and conference papers that were published or presented in 1994.

Smith, D.B.; Jaramillo, G.R. [comp.

1995-08-01T23:59:59.000Z

156

Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)  

SciTech Connect (OSTI)

This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of ‘safeguards by design’. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how ‘safeguardability’ was introduced into RRP.

Johnson, Shirley J.; Ehinger, Michael

2010-08-07T23:59:59.000Z

157

Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop  

Broader source: Energy.gov [DOE]

NUREG/CP-0183, Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop, June 12, 2003 U.S. Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards Washington, DC 20555-0001.

158

High-resolution microcalorimeter detectors as a tool in the future of nuclear safeguards  

SciTech Connect (OSTI)

New measurements are presented from the LANL-NIST microcalorimeter array for two standard plutonium sources. The results demonstrate substantially smaller error bars obtained from the spectral analysis program FRAM. Some areas of improvement to the analysis technique have been identified, indicating that the micro calorimeter results can be improved upon. These results support the viability of a device for performing real nuclear safeguards measurements in the near future. The challenge of providing reliably accurate and precise data is a critical component of any safeguards initiative. In the realm of nuclear safeguards, this is an especially daunting task since inaccurate and/or imprecise data could have very serious international consequences. As such, there is a constant drive within the community to establish better measurement and analysis techniques in order to further reduce the associated errors and uncertainties. Even with todays state of the art equipment, measurement uncertainties can extend to several significant quantities worth of material over a relatively modest period of time. Furthermore, there is a strong desire for improved nondestructive analysis techniques in order to reduce both the cost, turnover rate, and inconvenience of destructive analyses. One promising new technology that may help to realize these goals is that of gamma-ray microcalorimeter detectors. The hallmark quality of this new technique is the ability to achieve energy resolution nearly an order of magnitude better than typical planar high-purity germanium (HPGe) detectors. Such an improvement may help reduce uncertainties associated with, for instance, plutonium isotopics or uranium enrichment measurements. This may, in turn, help to reduce uncertainties in total plutonium and/or uranium content in a given sample without the need for destructive analysis. In this paper, we will describe this new detector technology as well as some recent measurements carried out with the LANL-NIST gamma-ray microcalorimeter ({micro}cal) array. Discussion will focus on the capabilities of this technology as well as the progress toward a practical measurement device.

Hoteling, Nathan J [Los Alamos National Laboratory; Hoover, Andrew S [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

159

Integrated safeguards & security for material protection, accounting, and control.  

SciTech Connect (OSTI)

Traditional safeguards and security design for fuel cycle facilities is done separately and after the facility design is near completion. This can result in higher costs due to retrofits and redundant use of data. Future facilities will incorporate safeguards and security early in the design process and integrate the systems to make better use of plant data and strengthen both systems. The purpose of this project was to evaluate the integration of materials control and accounting (MC&A) measurements with physical security design for a nuclear reprocessing plant. Locations throughout the plant where data overlap occurs or where MC&A data could be a benefit were identified. This mapping is presented along with the methodology for including the additional data in existing probabilistic assessments to evaluate safeguards and security systems designs.

Duran, Felicia Angelica; Cipiti, Benjamin B.

2009-10-01T23:59:59.000Z

160

Considerations for Possible Light Impact of Spent Nuclear Fuel for Safeguards Measurements  

SciTech Connect (OSTI)

This effort is designed to be a preliminary study to determine the appropriateness of lightly contacting SNF with zirconium-based cladding, in wet storage, for the purpose of taking safeguards measurements. Contact will likely consist of an initial impact followed by a light tensile load on the exterior surface of the SNF cladding. In the past, concerns have been raised that contacting SNF cladding could result in a loss of long-term mechanical integrity due to crack initiation, uncontrolled crack propagation, and a mechanical exfoliation of the protective oxide layer. The mechanical integrity concerns are addressed with an analytic model that evaluates the threshold impact limits for degraded, but undamaged SNF cladding. Aqueous corrosion concerns, associated with exfoliation of the protective oxide layer, are addressed with a qualitative argument, focusing on the possible corrosion mechanisms of zirconium-based cladding.

Brian K. Castle; Kelly D. Ellis

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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161

Application of the sources code in nuclear safeguards  

SciTech Connect (OSTI)

The Sources Code System provides a greatly expanded calculational capacity in the field of nuclear safeguards. It is becoming more common that we are called upon to perform assays on materials for which no standards exist. These materials tend to be mixtures of nuclear materials and low-Z compounds (spent fuels in a variety of matrices, in-process compounds such as UF6, MOX with varying water content). We will present soma applications of the Sources Code and discuss the application calculated (a,n) source terms in neutron coincidence counting for nuclear safeguards.

Beddingfield, D. H. (David H.)

2002-01-01T23:59:59.000Z

162

AUTHENTICATED SENSOR INTERFACE DEVICE FOR JOINT USE SAFEGUARDS APPLICATIONS - CONCEPTS AND CHALLENGES  

SciTech Connect (OSTI)

This paper will discuss the key features of the Authenticated Sensor Interface Device that collectively provide the ability to share data among a number of parties while ensuring the authentication of data and protecting both the operator’s and the IAEA’s interests. The paper will also discuss the development of the prototype, the initial testing with an accountancy scale, and future plans and challenges to implementation into the joint use and remote monitoring applications. As nuclear fuel cycle technology becomes more prevalent throughout the world and the capacity of plants increases, limited resources of the IAEA are being stretched near a breaking point. A strategy is to increase efficiency in safeguards monitoring using “joint use” equipment that will provide the facility operator process data while also providing the IAEA key safeguards data. The data, however, must be authenticated and validated to ensure the data have not been tampered with. The Authenticated Sensor Interface Device provides the capability to share data and can be a valuable component in the IAEA’s ability to collect accountancy data from scales in Uranium conversion and enrichment plants, as well as nuclear fuel fabrication plants. Likewise, the Authenticated Sensor Interface Device can be configured to accept a diverse array of input signals, ranging from analog voltage, to current, to digital interfaces and more. These modular capabilities provide the ability to collect authenticated, joint-use, data streams from various process monitoring sensors.

Poland, R.; Drayer, R.; Wilson, J.

2013-08-12T23:59:59.000Z

163

Report on the September 2011 Meeting of the Next Generation Safegaurds Professional Network  

SciTech Connect (OSTI)

The Next Generation Safeguards Professional Network (NGSPN) was established in 2009 by Oak Ridge National Laboratory targeted towards the engagement of young professionals employed in safeguards across the many national laboratories. NGSPN focuses on providing a mechanism for young safeguards professionals to connect and foster professional relationships, facilitating knowledge transfer between current safeguards experts and the next generation of experts, and acting as an entity to represent the interests of the international community of young and mid-career safeguards professionals. This is accomplished in part with a yearly meeting held at a national laboratory site. In 2011, this meeting was held at Pacific Northwest National Laboratory. This report documents the events and results of that meeting.

Gitau, Ernest TN; Benz, Jacob M.

2011-12-19T23:59:59.000Z

164

Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina)  

E-Print Network [OSTI]

Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina) Sandia of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being

Gratta, Giorgio

165

Project Report on Development of a Safeguards Approach for Pyroprocessing  

SciTech Connect (OSTI)

The Idaho National Laboratory has undertaken an effort to develop a standard safeguards approach for international commercial pyroprocessing facilities. This report details progress for the fiscal year 2010 effort. A component by component diversion pathway analysis has been performed, and has led to insight on the mitigation needs and equipment development needed for a valid safeguards approach. The effort to develop an in-hot cell detection capability led to the digital cloud chamber, and more importantly, the significant potential scientific breakthrough of the inverse spectroscopy algorithm, including the ability to identify energy and spatial location of gamma ray emitting sources with a single, non-complex, stationary radiation detector system. Curium measurements were performed on historical and current samples at the FCF to attempt to determine the utility of using gross neutron counting for accountancy measurements. A solid cost estimate of equipment installation at FCF has been developed to guide proposals and cost allocations to use FCF as a test bed for safeguards measurement demonstrations. A combined MATLAB and MCNPX model has been developed to perform detector placement calculations around the electrorefiner. Early harvesting has occurred wherein the project team has been requested to provide pyroprocessing technology and safeguards short courses.

Robert Bean

2010-09-01T23:59:59.000Z

166

China in the World Trade Organization: Antidumping and Safeguards  

E-Print Network [OSTI]

China in the World Trade Organization: Antidumping and Safeguards Patrick A. Messerlin China finds of antidumping measures, but (so far) one of the smallest users of such measures. China's World Trade China's recent antidumping enforcement; how China could minimize its exposure to foreign antidumping

Paris-Sud XI, Université de

167

Nuclear Materials Management and Safeguards System Reporting and Data Submission  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual provides clear and detailed instructions and procedures for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE 5633.3B. Canceled by DOE M 474.1-2A.

1998-02-10T23:59:59.000Z

168

Process monitoring in support of International Atomic Energy Agency safeguards  

SciTech Connect (OSTI)

A review of previous efforts in process monitoring for safeguards was conducted. Previous efforts touched on various concepts and a few specific applications, but none was comprehensive in addressing all aspects of a process monitoring application for safeguards. This report develops prototypical process monitoring concepts that can be incorporated into the International Atomic Energy Agency's (IAEA's) general safeguards approach for fuel reprocessing plants. This effort considers existing approaches, recognizing limitations and needed improvements. Prototypical process monitoring applications are developed and proposed for implementation and demonstration in the Integrated Equipment Test facility, which is located at the Oak Ridge National Laboratory. The specific information needed to accomplish the process monitoring objectives are defined, and the mechanics for obtaining that information are described. Effort is given to the identification and assessment of potential impacts and benefits associated with process monitoring concepts, with particular attention to IAEA, state, and plant operator interests. The historical development of process monitoring is described and the implications of using process monitoring in international safeguards are discussed. Specific process process monitoring applications for demonstration in the IET facility are developed in Sects. 6 through 14. 1 fig.

Ehinger, M.H.; Wachter, J.W.; Hebble, T.L.; Kerr, H.T.

1987-08-01T23:59:59.000Z

169

Safeguards Agreement and Protocol with the International Atomic Energy Agency  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To ensure that DOE complies with the Agreement Between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, and the subsidiary arrangements to the Agreement. Canceled by DOE O 142.2A. Cancels DOE 1270.2B.

2004-01-07T23:59:59.000Z

170

The US Support program to IAEA Safeguards - 2008  

SciTech Connect (OSTI)

The U.S. Support Program to IAEA Safeguards (USSP) was established in 1977 to provide technical assistance to the IAEA Department of Safeguards. Since that time the U.S. Department of State has provided funding of over $200 million and over 900 tasks have been completed by USSP contractors on behalf of the KEA. The USSP is directed by a U.S. interagency subcommittee known as the Subgroup on Safeguards Technical Support (SSTS) and is managed by the International Safeguards Project Office (ISPO) at Brookhaven National Laboratory. In recent years, the SSTS and ISPO have identified priorities to guide the process of determining which IAEA requests are aligned with US. policy and will be funded. The USSP priorities are reviewed and updated prior to the USSP Annual Review Meeting which is hosted by the International Atomic Energy Agency (IAEA) each spring in Vienna, Austria. This paper will report on the 2008 USSP priorities and be an introduction for a session which will consist of four papers on USSP priorities and four other papers related to USSP activities.

Pepper,S.

2008-06-09T23:59:59.000Z

171

Safeguards Issues at Nuclear Reactors and Enrichment Plants  

SciTech Connect (OSTI)

The Agency's safeguards technical objective is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection.

Boyer, Brian D [Los Alamos National Laboratory

2012-08-15T23:59:59.000Z

172

Nuclear fission and nuclear safeguards: Common technologies and challenges  

SciTech Connect (OSTI)

Nuclear fission and nuclear safeguards have much in common, including the basic physical phenomena and technologies involved as well as the commitments and challenges posed by expanding nuclear programs in many countries around the world. The unique characteristics of the fission process -- such as prompt and delayed neutron and gamma ray emission -- not only provide the means of sustaining and controlling the fission chain reaction, but also provide unique ''signatures'' that are essential to quantitative measurement and effective safeguarding of key nuclear materials (notably /sup 239/Pu and /sup 235/U) against theft, loss, or diversion. In this paper, we trace briefly the historical emergence of safeguards as an essential component of the expansion of the nuclear enterprise worldwide. We then survey the major categories of passive and active nondestructive assay techniques that are currently in use or under development for rapid, accurate measurement and verification of safe-guarded nuclear materials in the many forms in which they occur throughout the nuclear fuel cycle. 23 refs., 14 figs.

Keepin, G.R.

1989-01-01T23:59:59.000Z

173

Consequence Management, Safeguards & Non-Proliferation Tools...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

field in a mock-up of a UF-6 enrichment facility. The solution was generated on a desktop computer using ORNL's Denovo SN transport code and ADVANTG interface, using geometry and...

174

Integrated Safeguards and Security Management Self-Assessment 2004  

SciTech Connect (OSTI)

In 2002 Ernest Orlando Lawrence Berkeley National Laboratory deployed the first Integrated Safeguards and Security Management (ISSM) Self-Assessment process, designed to measure the effect of the Laboratory's ISSM efforts. This process was recognized by DOE as a best practice and model program for self-assessment and training. In 2004, the second Self-Assessment was launched. The cornerstone of this process was an employee survey that was designed to meet several objectives: (1) Ensure that Laboratory assets are protected. (2) Provide a measurement of the Laboratory's current security status that can be compared against the 2002 Self-Assessment baseline. (3) Educate all Laboratory staff about security responsibilities, tools, and practices. (4) Provide security staff with feedback on the effectiveness of security programs. (5) Provide line management with the information they need to make informed decisions about security. This 2004 Self Assessment process began in July 2004 with every employee receiving an information packet and instructions for completing the ISSM survey. The Laboratory-wide survey contained questions designed to measure awareness and conformance to policy and best practices. The survey response was excellent--90% of Berkeley Lab employees completed the questionnaire. ISSM liaisons from each division followed up on the initial survey results with individual employees to improve awareness and resolve ambiguities uncovered by the questionnaire. As with the 2002 survey, the Self-Assessment produced immediate positive results for the ISSM program and revealed opportunities for longer-term corrective actions. Results of the questionnaire provided information for organizational profiles and an institutional summary. The overall level of security protection and awareness was very high--often above 90%. Post-survey work by the ISSM liaisons and line management consistently led to improved awareness and metrics, as shown by a comparison of profiles at the end of phase one (August 6, 2004) and phase two (November 1, 2004). The Self-Assessment confirmed that classified information is not held or processed at Berkeley Lab. The survey results also identified areas where increased employee knowledge and awareness of Laboratory policy would be beneficial, the two most prominent being password usage and wireless network service. Line management will be able to determine additional corrective actions based on the results of the Self-Assessment. Future assessments will raise the ratings bar for some existing program elements and add new elements to stimulate further improvements in Laboratory security.

Lunford, Dan; Ramsey, Dwayne

2005-04-01T23:59:59.000Z

175

Safeguards instrumentation: a computer-based catalog. Second edition  

SciTech Connect (OSTI)

This catalog contains entries on new developments and on items listed in BNL 51450, which have either been carried over unchanged or been updated. More than 70 entries were deleted because of either obsolescence, insufficient interest in terms of safeguards, or lack of documentable development activities in recent years. Some old listings as well as new material was consolidated into more generic entries. As in the earlier document, the emphasis is on devices and instruments that are either in field use at this time or under active development. A few items such as NDA reference materials, instrument vans and certain shipping containers are included because they are important adjuncts to optimum utilization of safeguards instrumentation. This catalog does not include devices for physical protection. As was the case with its predecessor, most of the material in this catalog originated in the US and Canada; a few contributions came from member states of the European Community.

Auerbach, C.

1985-04-01T23:59:59.000Z

176

Using Highly Interactive Virtual Environments for Safeguards Activities  

SciTech Connect (OSTI)

Highly interactive virtual environment (HIVE) is a term that refers to interactive educational simulations, serious games and virtual worlds. Studies indicate that learning with the aid of interactive environments produces better retention and depth of knowledge by promoting improved trainee engagement and understanding. Virtual reality or three dimensional (3D) visualization is often used to promote the understanding of something when personal observation, photographs, drawings, and/or sketches are not possible or available. Subjects and situations, either real or hypothetical, can be developed using a 3D model. Models can be tailored to the audience allowing safeguards and security features to be demonstrated for educational purposes in addition to engineering evaluation and performance analysis. Oak Ridge National Laboratory (ORNL) has begun evaluating the feasibility of HIVEs for improving safeguards activities such as training, mission planning, and evaluating worker task performance. This paper will discuss the development workflow of HIVEs and present some recent examples.

Weil, Bradley S [ORNL] [ORNL; Alcala, Benjamin S [ORNL] [ORNL; Alcala, Scott [ORNL] [ORNL; Eipeldauer, Mary D [ORNL] [ORNL; Weil, Logan B [ORNL] [ORNL

2010-01-01T23:59:59.000Z

177

Protection and Control of Safeguards and Security Interests  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish policy, responsibilities, and authorities for the protection and control of safeguards and security interests. Cancels DOE O 5632.1B, DOE O 5632.2A, DOE O 5632.5, DOE O 5632.6, DOE O 5632.9A, DOE O 5632.11, DOE O 5635.1A, DOE O 5635.2B, DOE O 5635.3. Canceled by DOE O 473.1

1994-07-15T23:59:59.000Z

178

Safeguards and security research and development: Program status report, February-July 1981  

SciTech Connect (OSTI)

This report, one of a series of biannual progress reports, describes the status of research and development in the Safeguards and Security Program at Los Alamos from February-July 1981. Most work covered here is sponsored by the Office of Safeguards and Security of the Department of Energy; however, project activities that are technically closely related to nuclear safeguards and security also are included where appropriate for conveying information useful to the nuclear community. The report comprises four major subject areas: Security Development and Support; Nuclear Materials Measurement and Engineering; Nuclear Facility Safeguards Support; and International Safeguards, Technology Transfer, and Training. Some technical topics included in the subject areas are computer and informational security, chemical and nondestructive analysis of nuclear materials, process modeling and analysis, nuclear materials accounting systems, evaluation of prototype measurement instrumentation and procedures in nuclear facilities, design and consultation for facilities, technical exchange, training courses, and international safeguards.

Henry, C.N.; Walton, R.B. (comps.)

1982-04-01T23:59:59.000Z

179

The ESA's Climate Change Initiative is reprocessing and reassessing over 40 years of multi-sensor satellite records to generate consistent, traceable, long-term datasets of  

E-Print Network [OSTI]

The ESA's Climate Change Initiative is reprocessing and reassessing over 40 years of multi" for the climate modeling and research communities. THE ESA CLIMATE CHANGE INITIATIVE Satellite Data Records to our understanding of Earth's climate and how it is changing--one of the major challenges of the twenty

Boyer, Edmond

180

E-Print Network 3.0 - automated safeguards system Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

of Contact: Division Director: Alan S. Icenhour, Ph.D. Summary: areas. Leadership Areas: Nuclear Radiation Detection Safeguards Systems Development, Testing... Transportation...

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

E-Print Network 3.0 - advanced safeguards technology Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Measurements with Three-Dimensional Laser Scanning System and Coded-Aperture Gamma-Ray Imaging Systems for International Safeguards Applications Summary: -Ray Imaging...

182

E-Print Network 3.0 - acp safeguards neutron Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Measurements with Three-Dimensional Laser Scanning System and Coded-Aperture Gamma-Ray Imaging Systems for International Safeguards Applications Summary: -Ray Imaging...

183

E-Print Network 3.0 - assembly safeguards summary Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Measurements with Three-Dimensional Laser Scanning System and Coded-Aperture Gamma-Ray Imaging Systems for International Safeguards Applications Summary: -Ray Imaging...

184

Development of Superconducting High-Resolution Gamma-Ray Spectrometers for Nuclear Safeguards  

E-Print Network [OSTI]

of smuggling. Today, nuclear security is significantly morecritical importance of nuclear security, stating that thereJ. Doyle. Nuclear Safeguards, Security and Nonproliferation:

Dreyer, Jonathan

2012-01-01T23:59:59.000Z

185

Advances in nuclear instrumentation for safeguards  

SciTech Connect (OSTI)

This paper describes detectors, instrumentation, and analytical methods under development to address the above issues. The authors will describe work underway on room-temperature semiconductors including attempts to model the response of these detectors to improve spectrum analysis procedures and detector design. Computerized tomography is used in many medical and industrial applications; they are developing both gamma-ray and neutron tomography for improved measurements of waste and direct-use materials. Modern electronics and scintillation detectors should permit the development of fast neutron coincidence detectors with dramatically improved signal-to-noise ratios. For active measurements, they are studying several improved neutron sources, including a high-fluence, plasma-based, d-t generator. New analysis tools from information theory may permit one to better combine data from different measurement systems. This paper attempts to briefly describe a range of new sensors, electronics, and data analysis methods under study at Los Alamos and other laboratories to promote discussion of promising technology that they may bring to bear on these important global issues.

Prettyman, T.H.; Reilly, T.D.; Miller, M.C.; Hollas, C.L.; Pickrell, M.M.; Prommel, J.M.; Dreicer, J.S.

1996-12-31T23:59:59.000Z

186

Defining the needs for gas centrifuge enrichment plants advanced safeguards  

SciTech Connect (OSTI)

Current safeguards approaches used by the International Atomic Energy Agency (IAEA) at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low-enriched (LEU) production, detect undeclared LEU production and detect highly enriched uranium (HEU) production with adequate detection probability using nondestructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of declared UF{sub 6} containers used in the process of enrichment at GCEPs. In verifying declared LEU production, the inspectors also take samples for off-site destructive assay (DA) which provide accurate data, with 0.1% to 0.5% measurement uncertainty, on the enrichment of the UF{sub 6} feed, tails, and product. However, taking samples of UF{sub 6} for off-site analysis is a much more labor and resource intensive exercise for the operator and inspector. Furthermore, the operator must ship the samples off-site to the IAEA laboratory which delays the timeliness of results and interruptions to the continuity of knowledge (CofK) of the samples during their storage and transit. This paper contains an analysis of possible improvements in unattended and attended NDA systems such as process monitoring and possible on-site analysis of DA samples that could reduce the uncertainty of the inspector's measurements and provide more effective and efficient IAEA GCEPs safeguards. We also introduce examples advanced safeguards systems that could be assembled for unattended operation.

Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Ianakiev, Kiril [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory

2010-04-05T23:59:59.000Z

187

Safeguards and security research and development: Progress report, October 1994--September 1995  

SciTech Connect (OSTI)

The primary goal of the Los Alamos Safeguards and Security Technology Development Program, International Safeguards, and other Safeguards and Security Programs is to continue to be the center of excellence in the field of Safeguards and Security. This annual report for 1995 describes those scientific and engineering projects that contribute to all of the aforementioned programs. The authors have presented the information in a different format from previous annual reports. Part I is devoted to Nuclear Material Measurement Systems. Part II contains projects that are specific to Integrated Safeguards Systems. Part III highlights Safeguards Systems Effectiveness Evaluations and Part IV is a compilation of highlights from Information Assurance projects. Finally Part V highlights work on the projects at Los Alamos for International Safeguards. The final part of this annual report lists titles and abstracts of Los Alamos Safeguards and Security Technology Development reports, technical journal articles, and conference papers that were presented and published in 1995. This is the last annual report in this format. The authors wish to thank all of the individuals who have contributed to this annual report and made it so successful over the years.

Rutherford, D.R.; Henriksen, P.W. [comp.

1997-03-01T23:59:59.000Z

188

Extended Evaluations of the Commercial Spectrometer Systems for Safeguards Applications  

SciTech Connect (OSTI)

Safeguards applications require the best of the spectrometer system with excellent resolution, stability, and throughput. Instruments must perform well in all situations and environments. Data communication to the computer should be convenient, fast, and reliable. The software should have all the necessary tools and be easy to use. Portable systems should be small in size, lightweight, and have a long battery life. Nine commercially available spectrometer systems are tested with five different germanium detectors. Considering the performance of the Digital Signal Processors (DSP), digital-based spectroscope y may become the way of future gamma-ray spectroscopy.

Duc T. Vo

1999-08-01T23:59:59.000Z

189

Materials management in an internationally safeguarded fuels reprocessing plant  

SciTech Connect (OSTI)

The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

1980-04-01T23:59:59.000Z

190

Safeguards and Security Program - DOE Directives, Delegations, and  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGEComplainant,.VisitorSafeguards

191

Safeguards and Security Program - DOE Directives, Delegations, and  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGEComplainant,.VisitorSafeguardsRequirements

192

Safeguards and Security for Program and Project Management - DOE  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwardsSafeguards and Security Systems SHARE

193

Safeguards and Security Program - DOE Directives, Delegations, and  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromisingStoriesSANDIA1 0-SA-02 September 2013Safeguards

194

Transportation Safeguards & Security Test Bed (TSSTB) | ORNL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layered NbS2Topo II:LIGHT-DUTYTransportation Safeguards and

195

Next Generation Reactors  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear Advances We are coordinating the Generation IV Nuclear Systems Initiative - an international effort to develop the next generation of nuclear power reactors. Skip...

196

Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor  

E-Print Network [OSTI]

............................................................................................... 24 8 Flow diagram for an Advanced CANDU reactor ..................................... 27 9 Implementation of safeguards measures at a CANDU facility using video surveillance and radiation monitors... ................................................ 28 10 Implementation of safeguards measures at a CANDU facility using core discharge monitor.............................................................................. 28 11 Primary safeguards measures at MONJU Fast Reactor in Japan...

Gitau, Ernest Travis Ngure

2012-10-19T23:59:59.000Z

197

Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget  

SciTech Connect (OSTI)

This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states’ (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In order to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.

Kollar, Lenka; Mathews, Caroline E.

2009-07-01T23:59:59.000Z

198

Clean Coal Power Initiative | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Clean Coal Power Initiative Clean Coal Power Initiative "Clean coal technology" describes a new generation of energy processes that sharply reduce air emissions and other...

199

Implementation of remove monitoring in facilities under safeguards with unattended systems  

SciTech Connect (OSTI)

Remote monitoring is being applied by the International Atomic Energy Agency (IAEA) at nuclear facilities around the world. At the Monju Reactor in Japan we have designed, developed and implemented a remote monitoring approach that can serve as a model for applying remote monitoring to facilities that are already under full-scope safeguards using unattended instrumentation. Remote monitoring implementations have historically relied upon the use of specialized data collection hardware and system design features that integrate remote monitoring into the safeguards data collection system. The integration of remote monitoring and unattended data collection increases the complexity of safeguards data collection systems. This increase in complexity necessarily produces a corresponding reduction of system reliability compared to less-complex unattended monitoring systems. At the Monju facility we have implemented a remote monitoring system that is decoupled from the activity of safeguards data collection. In the completed system the function of remote data transfer is separated from the function of safeguards data collection. As such, a failure of the remote monitoring function cannot produce an associated loss of safeguards data, as is possible with integrated remote-monitoring implementations. Currently, all safeguards data from this facility is available to the IAEA on a 24/7 basis. This facility employs five radiation-based unattended systems, video surveillance and numerous optical seal systems. The implementation of remote monitoring at this facility, while increasing the complexity of the safeguards system, is designed to avoid any corresponding reduction in reliability of the safeguards data collection systems by having decoupled these functions. This design and implementation can serve as a model for implementation of remote monitoring at nuclear facilities that currently employ unattended safeguards systems.

Beddingfield, David H [Los Alamos National Laboratory; Nordquist, Heather A [Los Alamos National Laboratory; Umebayaashi, Eiji [JAEA

2009-01-01T23:59:59.000Z

200

Fully integrated safeguards and security for reprocessing plant monitoring.  

SciTech Connect (OSTI)

Nuclear fuel reprocessing plants contain a wealth of plant monitoring data including material measurements, process monitoring, administrative procedures, and physical protection elements. Future facilities are moving in the direction of highly-integrated plant monitoring systems that make efficient use of the plant data to improve monitoring and reduce costs. The Separations and Safeguards Performance Model (SSPM) is an analysis tool that is used for modeling advanced monitoring systems and to determine system response under diversion scenarios. This report both describes the architecture for such a future monitoring system and present results under various diversion scenarios. Improvements made in the past year include the development of statistical tests for detecting material loss, the integration of material balance alarms to improve physical protection, and the integration of administrative procedures. The SSPM has been used to demonstrate how advanced instrumentation (as developed in the Material Protection, Accounting, and Control Technologies campaign) can benefit the overall safeguards system as well as how all instrumentation is tied into the physical protection system. This concept has the potential to greatly improve the probability of detection for both abrupt and protracted diversion of nuclear material.

Duran, Felicia Angelica; Ward, Rebecca; Cipiti, Benjamin B.; Middleton, Bobby D.

2011-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Application of safeguards technology in DOE's environmental restoration program  

SciTech Connect (OSTI)

During the last two decades, the Department of Energy's Office of Safeguards and Security (DOE/OSS) has supported the research and development of safeguards systems analysis methodologies and nondestructive assay (NDS) technology for characterizing, monitoring, and accounting nuclear materials. This paper discusses methodologies and NDA instrumentation developed by the DOE/OSS program that could be applied in the Environmental Restoration Program. NDA instrumentation could be used for field measurements during site characterization and to monitor nuclear materials, heavy metals, and other hazardous materials during site remediation. Systems methodologies can minimize the expenditure of resources and help specify appropriate combinations of NDA instrumentation and chemical analyses to characterize a variety of materials quickly and reduce personnel exposure in hazardous environments. A training program is available to teach fundamental and advanced principles and approaches to characterize and quantify nuclear materials properly and to organize and analyze measurement information for decision making. The ability to characterize the overall volume and distribution of materials at a waste site is difficult because of the inhomogeneous distribution of materials, the requirement for extreme sensitivity, and the lack of resources to collect and chemically analyze a sufficient number of samples. Using a systems study approach based on statistical sampling, the resources necessary to characterize a site can be enhanced by appropriately combining in situ and field NDA measurements with laboratory analyses. 35 refs., 1 figs., 2 tabs.

Eccleston, G.W.; Baker, M.P.; Hansen, W.R.; Lucas, M.C.; Markin, J.T.; Phillips, J.R.

1990-01-01T23:59:59.000Z

202

Safeguards and Security Technology Development Directory. FY 1993  

SciTech Connect (OSTI)

The Safeguards and Security Technology Development Directory is published annually by the Office of Safeguards and Security (OSS) of the US Department of Energy (DOE), and is Intended to inform recipients of the full scope of the OSS R&D program. It is distributed for use by DOE headquarters personnel, DOE program offices, DOE field offices, DOE operating contractors, national laboratories, other federal agencies, and foreign governments. Chapters 1 through 7 of the Directory provide general information regarding the Technology Development Program, including the mission, program description, organizational roles and responsibilities, technology development lifecycle, requirements analysis, program formulation, the task selection process, technology development infrastructure, technology transfer activities, and current research and development tasks. These chapters are followed by a series of appendices which contain more specific information on aspects of the Program. Appendix A is a summary of major technology development accomplishments made during FY 1992. Appendix B lists S&S technology development reports issued during FY 1992 which reflect work accomplished through the OSS Technology Development Program and other relevant activities outside the Program. Finally, Appendix C summarizes the individual task statements which comprise the FY 1993 Technology Development Program.

Not Available

1993-06-01T23:59:59.000Z

203

DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY  

SciTech Connect (OSTI)

Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

204

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report  

SciTech Connect (OSTI)

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

2000-09-01T23:59:59.000Z

205

Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory  

SciTech Connect (OSTI)

Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC&A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material has been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S&S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.

Michael Holzemer; Alan Carvo

2012-04-01T23:59:59.000Z

206

Nuclear Reactor Safeguards and Monitoring with Antineutrino Detectors  

E-Print Network [OSTI]

Cubic-meter-sized antineutrino detectors can be used to non-intrusively, robustly and automatically monitor and safeguard a wide variety of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors. Since the antineutrino spectra and relative yields of fissioning isotopes depend on the isotopic composition of the core, changes in composition can be observed without ever directly accessing the core itself. Information from a modest-sized antineutrino detector, coupled with the well-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being operated in an illegitimate way. A group at Sandia is currently constructing a one cubic meter antineutrino detector at the San Onofre reactor site in California to demonstrate these principles.

Adam Bernstein; Yifang Wang; Giorgio Gratta; Todd West

2001-08-01T23:59:59.000Z

207

The uranium cylinder assay system for enrichment plant safeguards  

SciTech Connect (OSTI)

Safeguarding sensitive fuel cycle technology such as uranium enrichment is a critical component in preventing the spread of nuclear weapons. A useful tool for the nuclear materials accountancy of such a plant would be an instrument that measured the uranium content of UF{sub 6} cylinders. The Uranium Cylinder Assay System (UCAS) was designed for Japan Nuclear Fuel Limited (JNFL) for use in the Rokkasho Enrichment Plant in Japan for this purpose. It uses total neutron counting to determine uranium mass in UF{sub 6} cylinders given a known enrichment. This paper describes the design of UCAS, which includes features to allow for unattended operation. It can be used on 30B and 48Y cylinders to measure depleted, natural, and enriched uranium. It can also be used to assess the amount of uranium in decommissioned equipment and waste containers. Experimental measurements have been carried out in the laboratory and these are in good agreement with the Monte Carlo modeling results.

Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Rael, Carlos D [Los Alamos National Laboratory; Iwamoto, Tomonori [JNFL; Tamura, Takayuki [JNFL; Aiuchi, Syun [JNFL

2010-01-01T23:59:59.000Z

208

The new geospatial tools: global transparency enhancing safeguards verification  

SciTech Connect (OSTI)

This paper focuses on the importance and potential role of the new, freely available, geospatial tools for enhancing IAEA safeguards and how, together with commercial satellite imagery, they can be used to promote 'all-source synergy'. As additional 'open sources', these new geospatial tools have heralded a new era of 'global transparency' and they can be used to substantially augment existing information-driven safeguards gathering techniques, procedures, and analyses in the remote detection of undeclared facilities, as well as support ongoing monitoring and verification of various treaty (e.g., NPT, FMCT) relevant activities and programs. As an illustration of how these new geospatial tools may be applied, an original exemplar case study provides how it is possible to derive value-added follow-up information on some recent public media reporting of a former clandestine underground plutonium production complex (now being converted to a 'Tourist Attraction' given the site's abandonment by China in the early 1980s). That open source media reporting, when combined with subsequent commentary found in various Internet-based Blogs and Wikis, led to independent verification of the reporting with additional ground truth via 'crowdsourcing' (tourist photos as found on 'social networking' venues like Google Earth's Panoramio layer and Twitter). Confirmation of the precise geospatial location of the site (along with a more complete facility characterization incorporating 3-D Modeling and visualization) was only made possible following the acquisition of higher resolution commercial satellite imagery that could be correlated with the reporting, ground photos, and an interior diagram, through original imagery analysis of the overhead imagery.

Pabian, Frank Vincent [Los Alamos National Laboratory

2010-09-16T23:59:59.000Z

209

Feasibility Study of Implementing a Mobile Collaborative Information Platform for International Safeguards Inspections  

SciTech Connect (OSTI)

In response to the growing pervasiveness of mobile technologies such as tablets and smartphones, the International Atomic Energy Agency and the U.S. Department of Energy National Laboratories have been exploring the potential use of these platforms for international safeguards activities. Specifically of interest are information systems (software, and accompanying servers and architecture) deployed on mobile devices to increase the situational awareness and productivity of an IAEA safeguards inspector in the field, while simultaneously reducing paperwork and pack weight of safeguards equipment. Exploratory development in this area has been met with skepticism regarding the ability to overcome technology deployment challenges for IAEA safeguards equipment. This report documents research conducted to identify potential challenges for the deployment of a mobile collaborative information system to the IAEA, and proposes strategies to mitigate those challenges.

Gastelum, Zoe N.; Gitau, Ernest TN; Doehle, Joel R.; Toomey, Christopher M.

2014-09-30T23:59:59.000Z

210

Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System  

E-Print Network [OSTI]

There has been a strong international interest in using pyroprocessing to close the fast nuclear reactor fuel cycle and reprocess spent fuel efficiently. To commercialize pyroprocessing, safeguards technologies are required to be developed...

Le Coq, Annabelle G

2013-06-25T23:59:59.000Z

211

US statutes of general interest to safeguards and security officers. Revision 12/95  

SciTech Connect (OSTI)

This document is one of a three volume set. This document, BNL 52202, it titled, ``US Statutes of General Interest to Safeguards and Security Officers``, and is intended for use by officers.

Cadwell, J.J.; Ruger, C.J.

1995-12-01T23:59:59.000Z

212

REVIEW OF THE NEGOTIATION OF THE MODEL PROTOCOL ADDITIONAL TO THE AGREEMENT(S) BETWEEN STATE(S) AND THE INTERNATIONAL ATOMIC ENERGY AGENCY FOR THE APPLICATION OF SAFEGUARDS,INFCIRC/540 (Corrected) VOLUME I/III SETTING THE STAGE: 1991-1996.  

SciTech Connect (OSTI)

Events in Iraq at the beginning of the 1990s demonstrated that the safeguards system of the International Atomic Energy Agency (IAEA) needed to be improved. It had failed, after all, to detect Iraq's clandestine nuclear weapon program even though some of Iraq's's activities had been pursued at inspected facilities in buildings adjacent to ones being inspected by the IAEA. Although there were aspects of the implementation of safeguards where the IAEA needed to improve, the primary limitations were considered to be part of the safeguards system itself. That system was based on the Nuclear Nonproliferation Treaty of 1970, to which Iraq was a party, and implemented on the basis of a model NPT safeguards agreement, published by the IAEA 1972 as INFCIRC/153 (corrected). The agreement calls for states to accept and for the IAEA to apply safeguards to all nuclear material in the state. Iraq was a party to such an agreement, but it violated the agreement by concealing nuclear material and other nuclear activities from the IAEA. Although the IAEA was inspecting in Iraq, it was hindered by aspects of the agreement that essentially limited its access to points in declared facilities and provided the IAEA with little information about nuclear activities anywhere else in Iraq. As a result, a major review of the NPT safeguards system was initiated by its Director General and Member States with the objective of finding the best means to enable the IAEA to detect both diversions from declared stocks and any undeclared nuclear material or activities in the state. Significant improvements that could be made within existing legal authority were taken quickly, most importantly a change in 1992 in how and when and what design information would be reported to the IAEA. During 1991-1996, the IAEA pursued intensive study, legal and technical analysis, and field trials and held numerous consultations with Member States. The Board of Governors discussed the issue of strengthening safeguards at almost all of its meeting.

Rosenthal, M.D.; Saum-Manning, L.; Houck, F.; Anzelon, G.

2010-01-01T23:59:59.000Z

213

Nuclear Energy Research Initiative (NERI): Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems - Technical Progress Report August 2000 - October 2000  

SciTech Connect (OSTI)

OAK-B135 This ID belongs to an IWO and is being released out of the system. The Program manager Rebecca Richardson has confirmed that all reports have been received. The objective of the proposed research is to develop the scientific basis for a new class of radiation-resistant materials. Two approaches will be evaluated to develop damage resistant materials far superior to current stainless steels: (1) lattice perturbation to catalyze defect recombination within the early stages of cascade formation and defect migration and (2) controlled manipulation of the aggregate defect ensemble through the deliberate introduction of dynamic metastable microstructures. The intrinsic ability of the host matrix to resist displacement damage survival will be optimized in first concept. This approach (Task 1) explores baseline atomic displacement and recovery processes as affected by major and minor alloy constituents selected for the dual purpose of environmental cracking resistance as well as interactions with point defects. Inert oversized solutes known to improve corrosion behavior will be used to create vacancy/interstitial traps and promote defect recombination. Dynamic metastable microstructures tailored to resist damage accumulation will be investigated and optimized in the second concept (Task 2). Unique intermetallic second phases with inherent instabilities under irradiation will be used to create a dynamic microstructure resistant to radiation hardening, swelling and embrittlement. A key aspect of designing this dynamic microstructure will be to ensure the complex, radiation-induced changes do not promote environmental cracking. The underlying radiation materials science for these two approaches is being explored using charged particle irradiations. Radiation damage resistance will be established by isolating the effect of each approach on defect microstructure, grain boundary microchemistries and matrix hardening. The dose dependence of these radiation-induced material changes will be used to identify promising alloys and initial microstructure that effectively delay or eliminate detrimental microstructural and microchemical evolution. Environmental cracking response is being established on non-irradiated alloys with thermomechanical treatments to simulate radiation microstructures and by tests on proton-irradiated specimens. The ultimate goal for these alloys will be resistance to environmental cracking, swelling and embrittlement during the high radiation exposures (>150 dpa) planned for advanced reactors.

None

2000-09-01T23:59:59.000Z

214

Safeguards and security requirements for weapons plutonium disposition in light water reactors  

SciTech Connect (OSTI)

This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

1994-10-01T23:59:59.000Z

215

RADIO FREQUENCY IDENTIFICATION DEVICES: EFFECTIVENESS IN IMPROVING SAFEGUARDS AT GAS-CENTRIFUGE URANIUM-ENRICHMENT PLANTS.  

SciTech Connect (OSTI)

Recent advances in radio frequency identification devices (RFIDs) have engendered a growing interest among international safeguards experts. Potentially, RFIDs could reduce inspection work, viz. the number of inspections, number of samples, and duration of the visits, and thus improve the efficiency and effectiveness of international safeguards. This study systematically examined the applications of RFIDs for IAEA safeguards at large gas-centrifuge enrichment plants (GCEPs). These analyses are expected to help identify the requirements and desirable properties for RFIDs, to provide insights into which vulnerabilities matter most, and help formulate the required assurance tests. This work, specifically assesses the application of RFIDs for the ''Option 4'' safeguards approach, proposed by Bruce Moran, U. S. Nuclear Regulatory Commission (NRC), for large gas-centrifuge uranium-enrichment plants. The features of ''Option 4'' safeguards include placing RFIDs on all feed, product and tails (F/P/T) cylinders, along with WID readers in all FP/T stations and accountability scales. Other features of Moran's ''Option 4'' are Mailbox declarations, monitoring of load-cell-based weighing systems at the F/P/T stations and accountability scales, and continuous enrichment monitors. Relevant diversion paths were explored to evaluate how RFIDs improve the efficiency and effectiveness of safeguards. Additionally, the analysis addresses the use of RFIDs in conjunction with video monitoring and neutron detectors in a perimeter-monitoring approach to show that RFIDs can help to detect unidentified cylinders.

JOE,J.

2007-07-08T23:59:59.000Z

216

Gas centrifuge enrichment plants inspection frequency and remote monitoring issues for advanced safeguards implementation  

SciTech Connect (OSTI)

Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low enriched uranium (LEU) production, detect undeclared LEU production and detect high enriched uranium (BEU) production with adequate probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of declared cylinders of uranium hexafluoride that are used in the process of enrichment at GCEPs. This paper contains an analysis of how possible improvements in unattended and attended NDA systems including process monitoring and possible on-site destructive analysis (DA) of samples could reduce the uncertainty of the inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We have also studied a few advanced safeguards systems that could be assembled for unattended operation and the level of performance needed from these systems to provide more effective safeguards. The analysis also considers how short notice random inspections, unannounced inspections (UIs), and the concept of information-driven inspections can affect probability of detection of the diversion of nuclear material when coupled to new GCEPs safeguards regimes augmented with unattended systems. We also explore the effects of system failures and operator tampering on meeting safeguards goals for quantity and timeliness and the measures needed to recover from such failures and anomalies.

Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Ianakiev, Kiril D [Los Alamos National Laboratory; Reimold, Benjamin A [Los Alamos National Laboratory; Ward, Steven L [Los Alamos National Laboratory; Howell, John [GLASGOW UNIV.

2010-09-13T23:59:59.000Z

217

DEVELOPMENT OF A CANDLE FILTER FAILURE SAFEGUARD DEVICE  

SciTech Connect (OSTI)

The full-flow mechanical safeguard device (FFMSGD) has been developed under contract to the National Energy Technology Laboratory (NETL) to address problems with the reliability of ceramic candle filter elements installed on high-temperature, high-pressure (HTHP) Hot Gas Cleanup (HGCU) filters. Although systems candle filters are expected to perform satisfactorily when in good operating condition, the failure of even a single filter element can increase the filter system outlet dust loading enough to potentially damage gas turbine blades, contaminate other downstream processes, and limit the availability of the power system. Filter failure safeguard devices that are installed on each individual candle filter element are envisioned as a guarantee of a candle filter system's ability to withstand some number of element failures and continue operation without these negative consequences. The intention of the FFMSGD is to provide this guarantee without incurring any significant pressure drop penalty or constraining the filter system's reverse-pulse cleaning procedures. The FFMSGD provides a clear flow path for filtered and reverse-flow cleaning gases when its filter element is intact, and activates to provide a positive mechanical seal against gas flow in either direction when its filter element breaks or fails. This activation is induced by the increase in the flow rate of gas through the device in event of filter failure. The FFMSGD is designed to be easily removed and reconditioned when the filter system is taken off line for routine maintenance. This report is intended to be issued with a companion appendix. As instructed in Section J.12 of Contract No. DE-AC26-99FT40678, all the restricted, proprietary, and patentable information (not yet disclosed through the patent application process) related to the FFMSGD and its evaluation under this contract has been included only in the appendix. This Final Report, which is available to the public, contains background information and general descriptions of the operating principles of the FFMSGD. This report also describes the results of various evaluations of the device at room temperature and in HTHP environments. This Final Report also includes discussions of commercialization issues. For clarity and completeness, all of the information contained in this Final Report has also been included in the appendix.

Todd R. Snyder

2002-03-29T23:59:59.000Z

218

Enabling International Safeguards Research and Development in the United States  

SciTech Connect (OSTI)

Idaho National Laboratory (INL) is the lead laboratory in nuclear energy research and development within the U.S. Department of Energy national laboratory complex. INL is tasked with the advancement of nuclear energy research and development, and leadership in the renaissance of nuclear power globally. INL scientists have been central to the assessment of needs and the integration of technical programs aimed at the world-wide growth of nuclear power. One of the grand challenges of the nuclear energy resurgence is nuclear nonproliferation. Nonproliferation technology development is key to meeting this challenge. The needed advances in nonproliferation technologies are being made more difficult by the growing gap between increasing demands for nuclear materials to support technology development, and reduced availability of these materials. The gap is caused by the reduction, consolidation and more stringent lockdown of nuclear materials, made necessary by heightened and evolving security concerns, in the face of increased demand for materials to support technology development. Ironically, the increased demand for materials for technology development is made necessary by these same security concerns. The situation will continue to worsen if safeguards and security budgets remain limited for the International Atomic Energy Agency (IAEA) and many member states, while growth in global nuclear energy becomes a reality. Effective U.S. leadership in the closing of this gap is vital to homeland security and global stability. INL has taken positive steps, described in this paper, to close this gap by reestablishing a viable base for the development, testing and demonstration of safeguards and security technologies. Key attributes of this technology development base are (1) the availability of a wide variety of special nuclear materials in forms that allow for enhanced accessibility; (2) ease of access by U.S. government, national laboratory, industry and academic institution researchers; (3) openness to and ease of access by international users working through U.S. government sponsoring agencies; and (4) the availability of requisite infrastructure to support research, testing and demonstration. While there is still work to do in closing the gap between material accessibility and demand, the steps taken by INL to date begin to address this important challenge.

John E. Dwight; Mark J. Schanfein; Trond A. Bjornard

2009-07-01T23:59:59.000Z

219

EMCAS, an evaluation methodology for safeguards and security systems  

SciTech Connect (OSTI)

EMCAS is an evaluation methodology for safeguards and security systems. It provides a score card of projected or actual system performance for several areas of system operation. In one area, the performance of material control and accounting and security systems, which jointly defend against the insider threat to divert or steal special nuclear material (SNM) using stealth and deceit, is evaluated. Time-dependent and time-independent risk equations are used for both diversion and theft risk calculations. In the case of loss detection by material accounting, a detailed timeliness model is provided to determine the combined effects of loss detection sensitivity and timeliness on the overall effectiveness of the material accounting detection procedure. Calculated risks take into account the capabilities of process area containment/surveillance, material accounting mass balance tests, and physical protection barriers and procedures. In addition, EMCAS evaluates the Material Control and Accounting (MCandA) System in the following areas: (1) system capability to detect errors in the official book inventory of SNM, using mass balance accounting methods, (2) system capability to prevent errors from entering the nuclear material data base during periods of operation between mass balance tests, (3) time to conduct inventories and resolve alarms, and (4) time lost from production to carry out material control and accounting loss detection activities.

Eggers, R.F.; Giese, E.W.; Bichl, F.J.

1987-07-01T23:59:59.000Z

220

EMCAS: An evaluation methodology for safeguards and security systems  

SciTech Connect (OSTI)

EMCAS is an evaluation methodology for safeguards and security systems. It provides a score card of projected or actual system performance for several areas of system operation. In one area, the performance of material control and accounting and security systems, which jointly defend against the insider threat to divert or steal special nuclear material (SNM) using stealth and deceit, is evaluated. Time-dependent and time-independent risk equations are used for both diversion and theft risk calculations. In the case of loss detection by material accounting, a detailed timeliness model is provided to determine the combined effects of loss detection sensitivity and timeliness on the overall effectiveness of the material accounting detection procedure. Calculated risks take into account the capabilities of process area containment/surveillance, material accounting mass balance tests, and physical protection barriers and procedures. In addition, EMCAS evaluates the Material Control and Accounting (MC and A) System in the following areas: (1) system capability to detect errors in the official book inventory of SNM, using mass balance accounting methods, (2) system capability to prevent errors from entering the nuclear material data base during periods of operation between mass balance tests, (3) time to conduct inventories and resolve alarms, and (4) time lost from production to carry out material control and accounting loss detection activities. 3 figs., 5 tabs.

Eggers, R.F.; Giese, E.W.; Bichl, F.J.

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Applications of a portable MCA in nuclear safeguards  

SciTech Connect (OSTI)

In 1981 a small, battery-operated multichannel analyzer (MCA) prototype developed at Los Alamos National Laboratory was delivered to the International Atomic Energy Agency (IAEA). The intent was to produce an instrument for inspector (nonscientist) use. Automated measurement programs were built into the MCA. An enhanced, commercially produced MCA is now available, which was patterned after and is software compatible with the prototype. After an extensive review of the hardware and software of the available portable MCAs, the IAEA has chosen this MCA to be used by IAEA inspectors throughout the world. Inspectors from the EURATOM Directorate of Safeguards are also using these MCAs in inspections throughout Europe. While this MCA's portability and programmability make it ideally suited for infield applications, its powerful built-in intelligence and communications protocol make it a strong candidate for distributed data acquisition and control systems. The user-instrument interface philosophy is so easy to use that in domestic and international training schools, the operators manual is not used.

Halbig, J.K.; Klosterbuer, F.; Cameron, R.A.

1986-02-01T23:59:59.000Z

222

Authentication of reprocessing plant safeguards data through correlation analysis  

SciTech Connect (OSTI)

This report investigates the feasibility and benefits of two new approaches to the analysis of safeguards data from reprocessing plants. Both approaches involve some level of plant modeling. All models involve some form of mass balance, either applied in the usual way that leads to material balances for individual process vessels at discrete times or applied by accounting for pipe flow rates that leads to material balances for individual process vessels at continuous times. In the first case, material balances are computed after each tank-to-tank transfer. In the second case, material balances can be computed at any desired time. The two approaches can be described as follows. The first approach considers the application of a new multivariate sequential test. The test statistic is a scalar, but the monitored residual is a vector. The second approach considers the application of recent nonlinear time series methods for the purpose of empirically building a model for the expected magnitude of a material balance or other scalar variable. Although the report restricts attention to monitoring scalar time series, the methodology can be extended to vector time series.

Burr, T.L.; Wangen, L.E.; Mullen, M.F.

1995-04-01T23:59:59.000Z

223

SCB initiator  

DOE Patents [OSTI]

A detonator for high explosives initiated by mechanical impact includes a cylindrical barrel, a layer of flyer material mechanically covering the barrel at one end, and a semiconductor bridge ignitor including a pair of electrically conductive pads connected by a semiconductor bridge. The bridge is in operational contact with the layer, whereby ignition of said bridge forces a portion of the layer through the barrel to detonate the explosive. Input means are provided for igniting the semiconductor bridge ignitor.

Bickes Jr., Robert W.; Renlund, Anita M.; Stanton, Philip L.

1994-11-01T23:59:59.000Z

224

SCB initiator  

DOE Patents [OSTI]

A detonator for high explosives initiated by mechanical impact includes a cylindrical barrel, a layer of flyer material mechanically covering the barrel at one end, and a semiconductor bridge ignitor including a pair of electrically conductive pads connected by a semiconductor bridge. The bridge is in operational contact with the layer, whereby ignition of said bridge forces a portion of the layer through the barrel to detonate the explosive. Input means are provided for igniting the semiconductor bridge ignitor.

Bickes, Jr., Robert W. (Albuquerque, NM); Renlund, Anita M. (Albuquerque, NM); Stanton, Philip L. (Albuquerque, NM)

1994-01-01T23:59:59.000Z

225

Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control  

SciTech Connect (OSTI)

The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns.

Forsberg, C.W.; Storch, S.N. [Oak Ridge National Lab., TN (United States); Lewis, L.C. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-07-07T23:59:59.000Z

226

Behavior of 241Am in fast reactor systems - a safeguards perspective  

SciTech Connect (OSTI)

Advanced fuel-cycle developments around the world currently under development are exploring the possibility of disposing of {sup 241}Am from spent fuel recycle processes by burning this material in fast reactors. For safeguards practitioners, this approach could potentially complicate both fresh- and spent-fuel safeguards measurements. The increased ({alpha},n) production in oxide fuels from the {sup 241}Am increases the uncertainty in coincidence assay of Pu in MOX assemblies and will require additional information to make use of totals-based neutron assay of these assemblies. We have studied the behavior of {sup 241}Am-bearing MOX fuel in the fast reactor system and the effect on neutron and gamma-ray source-terms for safeguards measurements. In this paper, we will present the results of simulations of the behavior of {sup 241}Am in a fast breeder reactor system. Because of the increased use of MOX fuel in thermal reactors and advances in fuel-cycle designs aimed at americium disposal in fast reactors, we have undertaken a brief study of the behavior of americium in these systems to better understand the safeguards impacts of these new approaches. In this paper we will examine the behavior of {sup 241}Am in a variety of nuclear systems to provide insight into the safeguards implications of proposed Am disposition schemes.

Beddingfield, David H [Los Alamos National Laboratory; Lafleur, Adrienne M [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

227

Alternative materials to cadmium for neutron absorbers in safeguards applications  

SciTech Connect (OSTI)

Cadmium is increasingly difficult to use in safeguards applications because of rising cost and increased safety regulations. This work examines the properties of two materials produced by Ceradyne, inc. that present alternatives to cadmium for neutron shielding. The first is an aluminum metal doped with boron and the second is a boron carbide powder, compressed into a ceramic. Both are enriched in the {sup 10}B isotope. Two sheets of boron doped aluminum (1.1 mm and 5.2mm thick) and one sheet of boron carbide (8.5mm thick) were provided by Ceradyne for testing. An experiment was designed to test the neutron absorption capabilities of these three sheets against two different thicknesses of cadmium (0.6mm and 1.6mm thick). The thinner piece of aluminum boron alloy (1.1mm) performed as well as the cadmium pieces at absorbing neutrons. The thicker aluminum-boron plate provided more shielding than the cadmium sheets and the boron carbide performed best by a relatively large margin. Monte Carlo N-Particle eXtended (MCNPX) transport code modeling of the experiment was performed to provide validaLed computational tools for predicting the behavior of systems in which these materials may be incorporated as alternatives to cadmium. MCNPX calculations predict that approximately 0.17mm of the boron carbide is equivalent to 0.6mm of cadmium. There are drawbacks to these materials that need to be noted when considering using them as replacements for cadmium. Notably, they may need to be thicker than cadmium, and are not malleable, requiring machining to fit any curved forms.

Freeman, Corey R [Los Alamos National Laboratory; Geist, William H [Los Alamos National Laboratory; West, James D [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

228

Safeguards Summary Event List (SSEL), January 1, 1990--December 31, 1996, Vol. 2, Rev. 5  

SciTech Connect (OSTI)

The Safeguards Summary Event List (SSEL), Vol. 2, Rev. 5, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC) which occurred and were reported from January 1, 1990, through December 31, 1996. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of Bomb-related, Intrusion, Missing and/or Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms, Radiological Sabotage, Nonradiological Sabotage, and Miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels.

NONE

1997-07-01T23:59:59.000Z

229

Safeguards on uranium ore concentrate? the impact of modern mining and milling process  

SciTech Connect (OSTI)

Increased purity in uranium ore concentrate not only raises the question as to whether Safeguards should be applied to the entirety of uranium conversion facilities, but also as to whether some degree of coverage should be moved back to uranium ore concentrate production at uranium mining and milling facilities. This paper looks at uranium ore concentrate production across the globe and explores the extent to which increased purity is evident and the underlying reasons. Potential issues this increase in purity raises for IAEA's strategy on the Starting Point of Safeguards are also discussed.

Francis, Stephen [National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington WA3 6AE (United Kingdom)

2013-07-01T23:59:59.000Z

230

DEVELOPMENT OF AN ADHESIVE CANDLE FILTER SAFEGUARD DEVICE  

SciTech Connect (OSTI)

In order to reach the highest possible efficiencies in a coal-fired turbine-based power system, the turbine should be directly fired with the products of coal conversion. Two main types of systems employ these turbines: those based on pressurized fluidized-bed combustors and those based on integrated gasification combined cycles. In both systems, suspended particulates must be cleaned from the gas stream before it enters the turbine so as to prevent fouling and erosion of the turbine blades. To produce the cleanest gas, barrier filters are being developed and are in use in several facilities. Barrier filters are composed of porous, high-temperature materials that allow the hot gas to pass but collect the particulates on the surface. The three main configurations of the barrier filters are candle, cross-flow, and tube filters. Both candle and tube filters have been tested extensively. They are composed of coarsely porous ceramic that serves as a structural support, overlain with a thin, microporous ceramic layer on the dirty gas side that serves as the primary filter surface. They are highly efficient at removing particulate matter from the gas stream and, because of their ceramic construction, are resistant to gas and ash corrosion. However, ceramics are brittle and individual elements can fail, allowing particulates to pass through the hole left by the filter element and erode the turbine. Preventing all failure of individual ceramic filter elements is not possible at the present state of development of the technology. Therefore, safeguard devices (SGDs) must be employed to prevent the particulates streaming through occasional broken filters from reaching the turbine. However, the SGD must allow for the free passage of gas when it is not activated. Upon breaking of a filter, the SGD must either mechanically close or quickly plug with filter dust to prevent additional dust from reaching the turbine. Production of a dependable rapidly closing autonomous mechanical device at high temperatures in a dusty gas stream is difficult because of problems with materials corrosion, dust leakage, and detection of filter failure. Therefore, the Energy & Environmental Research Center is using its knowledge of the factors that make filter dust sticky at gas filtration temperatures to make a simple and inexpensive SGD that employs an adhesive yet thermodynamically stable coating on a highly porous ceramic substrate. The SGDs are placed on top of individual candle filters at the filtered gas exit. Upon failure of the filter, the dirty gas flows through the SGD where the adhesive surface rapidly and permanently traps dust particles, causing the device to plug and prevent the dust from reaching the turbine.

John P. Hurley; Ann K. Henderson; Jan W. Nowok; Michael L. Swanson

2002-01-01T23:59:59.000Z

231

NNSA Signs Memorandum with Kuwait to Increase Cooperation on Nuclear Safeguards and Nonproliferation  

ScienceCinema (OSTI)

On June 23, 2010, the National Nuclear Security Administration (NNSA) signed a Memorandum of Cooperation on nuclear safeguards and other nonproliferation topics with the Kuwait National Nuclear Energy Committee (KNNEC). NNSA Administrator Thomas D'Agostino and KNNEC's Secretary General, Dr. Ahmad Bishara, signed the memorandum at a ceremony at U.S. Department of Energy headquarters in Washington.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

232

Applications of virtual reality to nuclear safeguards and non-proliferation  

SciTech Connect (OSTI)

This paper presents several applications of virtual reality relevant to the areas of nuclear safeguards and non-proliferation. Each of these applications was developed to the prototype stage at Sandia National Laboratories` Virtual Reality and Intelligent Simulation laboratory. These applications include the use of virtual reality for facility visualization, training of inspection personnel, and security and monitoring of nuclear facilities.

Stansfield, S.

1996-12-31T23:59:59.000Z

233

Safety First Safety Last Safety Always Here is a partial list of safeguards for explosive actuated  

E-Print Network [OSTI]

Safety First Safety Last Safety Always Here is a partial list of safeguards for explosive actuated the design requirements in "American National Standards Institute Safety Requirements for Explosive Actuated on the other side. Portable Power Tools Safety Tip #14 Don't be a fool. Inspect your tools. Operators

Minnesota, University of

234

Analysis of the effectiveness of gas centrifuge enrichment plants advanced safeguards  

SciTech Connect (OSTI)

Current safeguards approaches used by the International Atomic Energy Agency (IAEA) at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low-enriched uranium (LEU) production, detect undeclared LEU production and detect highly enriched uranium (HEU) production with adequate detection probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and 235U enrichment of declared UF6 containers used in the process of enrichment at GCEPs. This paper contains an analysis of possible improvements in unattended and attended NDA systems including process monitoring and possible on-site destructive assay (DA) of samples that could reduce the uncertainty of the inspector's measurements. These improvements could reduce the difference between the operator's and inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We also explore how a few advanced safeguards systems could be assembled for unattended operation. The analysis will focus on how unannounced inspections (UIs), and the concept of information-driven inspections (IDS) can affect probability of detection of the diversion of nuclear materials when coupled to new GCEPs safeguards regimes augmented with unattended systems.

Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Swinjoe, Martyn T [Los Alamos National Laboratory; Ianakiev, Kiril D [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

235

Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method  

E-Print Network [OSTI]

We developed a segmented reactor-antineutrino detector made of plastic scintillators for application as a tool in nuclear safeguards inspection and performed mostly unmanned field operations at a commercial power plant reactor. At a position outside the reactor building, we measured the difference in reactor antineutrino flux above the ground when the reactor was active and inactive.

S. Oguri; Y. Kuroda; Y. Kato; R. Nakata; Y. Inoue; C. Ito; M. Minowa

2014-05-23T23:59:59.000Z

236

56647Federal Register / Vol. 70, No. 187 / Wednesday, September 28, 2005 / Notices SAFEGUARDS  

E-Print Network [OSTI]

(PEIS) entitled, ``Designation of Energy Corridors on Federal Land in the 11 Western States'' (DOE56647Federal Register / Vol. 70, No. 187 / Wednesday, September 28, 2005 / Notices SAFEGUARDS FOR THE SYSTEM: None. [FR Doc. 05­19326 Filed 9­27­05; 8:45 am] BILLING CODE 5001­06­M DEPARTMENT OF ENERGY

237

Role of IAEA (International Atomic Energy Agency) safeguards in confidence building  

SciTech Connect (OSTI)

In this paper, I will examine some attributes of confidence building and connect them with how the International Atomic Energy Agency (IAEA) interacts with its member states in carrying out its safeguards function. These interactions and the structure set up to define them help maintain and strengthen confidence between the IAEA and the member states and among these states. 3 refs.

Augustson, R.H.

1989-01-01T23:59:59.000Z

238

Plutonium assay for safeguards purposes: material heterogeneity and the application of calorimetry  

SciTech Connect (OSTI)

A variety of nuclear materials measurement techniques have been employed by the facility operator (WHC) and the IAEA during the two physical inventory verifications (PIVs) and at other items to determine and verify the quantities of plutonium present in the safeguarded inventory. Results of these analyses were statistically evaluated and are presented in this report.

Welsh, T.I., Westinghouse Hanford

1996-07-01T23:59:59.000Z

239

Manual for Nuclear Materials Management and Safeguards System Reporting and Data Submission  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The manual provides detailed instructions for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE M 474.1-2. Canceled by DOE M 470.4-6.

2003-08-19T23:59:59.000Z

240

Abstract: The challenges in nuclear safeguards and in nuclear security have significantly changed over the last decades. On the one side nuclear safeguards evolved from the simple verifica9on of declared amounts of material to a more informa9on driven app  

E-Print Network [OSTI]

Abstract: The challenges in nuclear safeguards and in nuclear security have significantly changed over the last decades. On the one side nuclear safeguards evolvedon driven approach based on the verifica9on of absence of undeclared nuclear

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Development of a Safeguards Verification Method and Instrument to Detect Pin Diversion from Pressurized Water Reactor (PWR) Spent Fuel Assemblies  

SciTech Connect (OSTI)

A technical safeguards challenge has remained for decades for the IAEA to identify possible diversion of nuclear fuel pins from Light Water Reactor (LWR) spent fuel assemblies. In fact, as modern nuclear power plants are pushed to higher power levels and longer fuel cycles, fuel failures (i.e., ''leakers'') as well as the corresponding fuel assembly repairs (i.e., ''reconstitutions'') are commonplace occurrences within the industry. Fuel vendors have performed hundreds of reconstitutions in the past two decades, thus, an evolved know-how and sophisticated tools exist to disassemble irradiated fuel assemblies and replace damaged pins with dummy stainless steel or other type rods. Various attempts have been made in the past two decades to develop a technology to identify a possible diversion of pin(s) and to determine whether some pins are missing or replaced with dummy or fresh fuel pins. However, to date, there are no safeguards instruments that can detect a possible pin diversion scenario to the requirements of the IAEA. The FORK detector system [1-2] can characterize spent fuel assemblies using operator declared data, but it is not sensitive enough to detect missing pins from spent fuel assemblies. Likewise, an emission computed tomography system [3] has been used to try to detect missing pins from a spent fuel assembly, which has shown some potential for identifying possible missing pins but this capability has not yet been fully demonstrated. The use of such a device in the future would not be envisaged, especially in an inexpensive, easy to handle setting for field applications. In this article, we describe a concept and ongoing research to help develop a new safeguards instrument for the detection of pin diversions in a PWR spent fuel assembly. The proposed instrument is based on one or more very thin radiation detectors that could be inserted within the guide tubes of a Pressurized Water Reactor (PWR) assembly. Ultimately, this work could lead to the development of a detector cluster and corresponding high-precision driving system to collect radiation signatures inside PWR spent fuel assemblies. The data obtained would provide the spatial distribution of the neutron and gamma flux fields within the spent fuel assembly, while the data analysis would be used to help identify missing or replaced pins. Monte Carlo simulations have been performed to help validate this concept using a realistic 17 x 17 PWR spent fuel assembly [4-5]. The initial results of this study show that neutron profile in the guide tubes, when obtained in the presence of missing pins, can be identifiably different from the profiles obtained without missing pins, Our latest simulations have focused upon a specific type of fission chamber that could be tested for this application.

Ham, Y S; Maldonado, G I; Burdo, J; He, T

2006-10-10T23:59:59.000Z

242

Explosive laser light initiation of propellants  

DOE Patents [OSTI]

A improved initiator for artillery shell using an explosively generated laser light to uniformly initiate the propellent. A small quantity of a high explosive, when detonated, creates a high pressure and temperature, causing the surrounding noble gas to fluoresce. This fluorescence is directed into a lasing material, which lases, and directs laser light into a cavity in the propellant, uniformly initiating the propellant.

Piltch, M.S.

1993-05-18T23:59:59.000Z

243

Annual Report FY2013-- A Kinematically Complete, Interdisciplinary, and Co-Institutional Measurement of the 19F(?,n) Cross-section for Nuclear Safeguards Science  

SciTech Connect (OSTI)

The goal of this proposal is to enable neutron detection for precision Non-Destructive Assays (NDAs) of actinide-fluoride samples. Neutrons are continuously generated from a UFx matrix in a container or sample as a result of the interaction of alpha particles from uranium-decay ? particles with fluorine nuclei in the matrix. Neutrons from 19F(?,n)22Na were once considered a poorly characterized background for assays of UFx samples via 238U spontaneous fission neutron detection [SMI2010B]. However, the yield of decay-?-driven neutrons is critical for 234,235U LEU and HEU assays, as it can used to determine both the total amount of uranium and the enrichment [BER2010]. This approach can be extremely valuable in a variety of safeguard applications, such as cylinder monitoring in underground uranium storage facilities, nuclear criticality safety studies, nuclear materials accounting, and other nonproliferation applications. The success of neutron-based assays critically depends on an accurate knowledge of the cross section of the (?,n) reaction that generates the neutrons. The 40% uncertainty in the 19F(?,n)22Na cross section currently limits the precision of such assays, and has been identified as a key factor in preventing accurate enrichment determinations [CRO2003]. The need for higher quality cross section data for (?,n) reactions has been a recurring conclusion in reviews of the nuclear data needs to support safeguards. The overarching goal of this project is to enable neutron detection to be used for precision Non- Destructive Assays (NDAs) of actinide-fluoride samples. This will significantly advance safeguards verification at existing declared facilities, nuclear materials accounting, process control, nuclear criticality safety monitoring, and a variety of other nonproliferation applications. To reach this goal, Idaho National Laboratory (INL), in partnership with Oak Ridge National Laboratory (ORNL), Rutgers University (RU), and the University of Notre Dame (UND), will focus on three specific items: (1) making a precision (better than 10 %) determination of the absolute cross section of the 19F(?,n)22Na reaction as a function of energy; (2) determining the spectrum of neutrons and ?-rays emitted from 19F(?,n)22Na over an energy range pertinent to NDA; and (3) performing simulations with this new cross section to extract the neutron yield (neutrons/gram/second) and resulting neutron- and gamma ray-spectra when ? particles interact with fluorine nuclei in actinide samples, to aid in the design and reduce uncertainty of future NDA measurements and simulations.

Peters, William A [ORNL; Smith, Michael Scott [ORNL; Clement, Ryan [INL; Tan, Wanpeng [University of Notre Dame; Stech, Ed [University of Notre Dame; Cizewski, J A [Rutgers University; Febbraro, Michael [University of Michigan; Madurga Flores, Miguel [ORNL

2013-10-01T23:59:59.000Z

244

The US Support Program Assistance to the IAEA Safeguards Information Technology, Collection, and Analysis 2008  

SciTech Connect (OSTI)

One of the United States Support Program's (USSP) priorities for 2008 is to support the International Atomic Energy Agency's (IAEA) development of an integrated and efficient safeguards information infrastructure, including reliable and maintainable information systems, and effective tools and resources to collect and analyze safeguards-relevant information. The USSP has provided funding in support of this priority for the ISIS Re-engineering Project (IRP), and for human resources support to the design and definition of the enhanced information analysis architecture project (nVision). Assistance for several other information technology efforts is provided. This paper will report on the various ongoing support measures undertaken by the USSP to support the IAEA's information technology enhancements and will provide some insights into activities that the USSP may support in the future.

Tackentien,J.

2008-06-12T23:59:59.000Z

245

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design  

SciTech Connect (OSTI)

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

2012-11-09T23:59:59.000Z

246

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design  

SciTech Connect (OSTI)

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

Coles, Garill A.; Hockert, John; Gitau, Ernest TN; Zentner, Michael D.

2013-01-26T23:59:59.000Z

247

New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities  

SciTech Connect (OSTI)

An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

Brim, Cornelia P.

2013-04-01T23:59:59.000Z

248

New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities  

SciTech Connect (OSTI)

An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

Brim, Cornelia P.

2013-03-04T23:59:59.000Z

249

Plutonium Measurements with a Fast-Neutron Multiplicity Counter for Nuclear Safeguards Applications  

SciTech Connect (OSTI)

Measurements were performed at the Joint Research Centre in Ispra, Italy to field test a fast-neutron multiplicity counter developed at the University of Michigan. The measurements allowed the illustration of the system’s photon discrimination abilities, efficiency when measuring neutron multiplicity, ability to characterize 240Pueff mass, and performance relative to a currently deployed neutron coincidence counter. This work is motivated by the need to replace and improve upon 3He neutron detection systems for nuclear safeguards applications.

Jennifer L. Dolan; Marek Flaska; Alexis Poitrasson-Riviere; Andreas Enqvist; Paolo Peerani; David L. Chichester; Sara A. Pozzi

2014-11-01T23:59:59.000Z

250

INDUSTRIAL CONTROL SYSTEM CYBER SECURITY: QUESTIONS AND ANSWERS RELEVANT TO NUCLEAR FACILITIES, SAFEGUARDS AND SECURITY  

SciTech Connect (OSTI)

Typical questions surrounding industrial control system (ICS) cyber security always lead back to: What could a cyber attack do to my system(s) and; how much should I worry about it? These two leading questions represent only a fraction of questions asked when discussing cyber security as it applies to any program, company, business, or organization. The intent of this paper is to open a dialog of important pertinent questions and answers that managers of nuclear facilities engaged in nuclear facility security and safeguards should examine, i.e., what questions should be asked; and how do the answers affect an organization's ability to effectively safeguard and secure nuclear material. When a cyber intrusion is reported, what does that mean? Can an intrusion be detected or go un-noticed? Are nuclear security or safeguards systems potentially vulnerable? What about the digital systems employed in process monitoring, and international safeguards? Organizations expend considerable efforts to ensure that their facilities can maintain continuity of operations against physical threats. However, cyber threats particularly on ICSs may not be well known or understood, and often do not receive adequate attention. With the disclosure of the Stuxnet virus that has recently attacked nuclear infrastructure, many organizations have recognized the need for an urgent interest in cyber attacks and defenses against them. Several questions arise including discussions about the insider threat, adequate cyber protections, program readiness, encryption, and many more. These questions, among others, are discussed so as to raise the awareness and shed light on ways to protect nuclear facilities and materials against such attacks.

Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

2011-07-01T23:59:59.000Z

251

Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order defines requirements for Department of Energy (DOE) compliance with the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, the Additional Protocol to the Agreement, and the Subsidiary Arrangements to the Agreement and Additional Protocol. Cancels DOE O 142.2. Admin Chg 1, 6-27-13.

2006-12-15T23:59:59.000Z

252

Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order defines requirements for Department of Energy (DOE) compliance with the Agreement between the United States of America and the International Atomic Energy Agency for the Application of Safeguards in the United States, the Protocol to the Agreement, the Additional Protocol to the Agreement, and the Subsidiary Arrangements to the Agreement and Additional Protocol. Cancels DOE O 142.2. Admin Chg 1, dated 6-27-13, cancels DOE O 142.1A. Certified 12-3-14.

2006-12-15T23:59:59.000Z

253

Boron-10 ABUNCL Prototype Initial Testing  

SciTech Connect (OSTI)

The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results of initial testing of an Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Several configurations of the ABUNCL models, which use 10B-lined proportional counters in place of 3He proportional counters for the neutron detection elements, were previously reported. The ABUNCL tested is of a different design than previously modeled. Initial experimental testing of the as-delivered passive ABUNCL was performed, and modeling will be conducted. Testing of the system reconfigured for active testing will be performed in the near future, followed by testing with nuclear fuel.

Kouzes, Richard T.; Ely, James H.; Lintereur, Azaree T.; Siciliano, Edward R.

2012-12-01T23:59:59.000Z

254

ASSESS (Analytic System and Software for Evaluating Safeguards and Security) update: Current status and future developments  

SciTech Connect (OSTI)

The Analytic System and Software for Evaluating Safeguards and Security (ASSESS) has been released for use by DOE field offices and their contractors. In October, 1989, we offered a prototype workshop to selected representatives of the DOE community. Based on the prototype results, we held the first training workshop at the Central Training Academy in January, 1990. Four additional workshops are scheduled for FY 1990. ASSESS is a state-of-the-art analytical tool for management to conduct integrated evaluation of safeguards systems at facilities handling facilities. Currently, ASSESS focuses on the threat of theft/diversion of special nuclear material by insiders, outsiders, and a special form of insider/outsider collusion. ASSESS also includes a neutralization module. Development of the tool is continuing. Plans are underway to expand the capabilities of ASSESS to evaluate against violent insiders, to validate the databases, to expand the neutralization module, and to assist in demonstrating compliance with DOE Material Control and Accountability (MC A) Order 5633.3. These new capabilities include the ability to: compute a weighted average for performance capability against a spectrum of insider adversaries; conduct defense-in-depth analyses; and analyze against protracted theft scenarios. As they become available, these capabilities will be incorporated in our training program. ASSESS is being developed jointly by Lawrence Livermore and Sandia National Laboratories under the sponsorship of the Department of Energy (DOE) Office of Safeguards and Security.

Al-Ayat, R.A. (Lawrence Livermore National Lab., CA (USA)); Cousins, T.D. (USDOE, Washington, DC (USA)); Hoover, E.R. (Sandia National Labs., Albuquerque, NM (USA))

1990-07-15T23:59:59.000Z

255

Under-sodium viewing technology for improvement of fast-reactor safeguards  

SciTech Connect (OSTI)

The current safeguards approach for fast reactors relies exclusively on maintenance of continuity of knowledge to track the movement of fuel assemblies through these facilities. The remote handling of fuel assemblies, the visual opacity of the liquid metal coolant. and the chemical reactivity of sodium all combine and result in significant limitations on the available options to verify fuel assembly identification numbers or the integrity of these assemblies. These limitations also serve to frustrate attempts to restore the continuity-of-knowledge in instances where the information is under a variety of scenarios. The technology of ultrasonic under-sodium viewing offers new options to the safeguards community for recovering continuity-of-knowledge and applying more traditional item accountancy to fast reactor facilities. We have performed a literature review to investigate the development of under-sodium viewing technologies. In this paper we will summarize our findings and report the state of development of this technology and we will present possible applications to the fast reactor system to improve the existing safeguards approach at these reactors and in future fast reactors.

Beddingfield, David H [Los Alamos National Laboratory; Gerhart, Jeremy J [Los Alamos National Laboratory; Kawakubo, Yoko [JAEA

2009-01-01T23:59:59.000Z

256

Next Generation Nuclear Plant Licensing Strategy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

reactor that is based on research and development (R&D) activities supported by the Generation IV Nuclear Energy Systems Initiative and shall be used to generate electricity,...

257

Boron-10 ABUNCL Prototype Models And Initial Active Testing  

SciTech Connect (OSTI)

The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results from MCNPX model simulations and initial testing of the active mode variation of the Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Initial experimental testing of the as-delivered passive ABUNCL was previously reported.

Kouzes, Richard T.; Ely, James H.; Lintereur, Azaree T.; Siciliano, Edward R.

2013-04-23T23:59:59.000Z

258

Knowledge Generation  

SciTech Connect (OSTI)

Unattended monitoring systems are being studied as a means of reducing both the cost and intrusiveness of present nuclear safeguards approaches. Such systems present the classic information overload problem to anyone trying to interpret the resulting data not only because of the sheer quantity of data but also because of the problems inherent in trying to correlate information from more than one source. As a consequence, analysis efforts to date have mostly concentrated on checking thresholds or diagnosing failures. Clearly more sophisticated analysis techniques are required to enable automated verification of expected activities level concepts in order to make automated judgments about safety, sensor system integrity, sensor data quality, diversion, and accountancy.

BRABSON,JOHN M.; DELAND,SHARON M.

2000-11-02T23:59:59.000Z

259

Preliminary study: isotopic safeguards techniques (IST) LMFBR fuel cycles  

SciTech Connect (OSTI)

This memorandum presents the preliminary results of the effort to investigate the applicability of isotope correlation techniques (ICT), formulated for the LWR system, to the LMFBR fuel cycle. The detailed isotopic compositional changes with burnup developed for the CRBR was utilized as the reference case. This differs from the usual LMFBR design studies in that the core uranium is natural uranium rather than depleted. Nevertheless, the general isotopic behavior should not differ significantly and does allow an initial insight into the expected behavior of isotopic correlations for the LMFBR power systems such as: the U.K. PFR and reprocessing plant; the French Phenix and Superphenix; and the US reference conceptual design studies (CDS) of homogeneous and heterogeneous LMFBR systems as they are developed.

Persiani, P.J.; Kroc, T.K.

1980-06-01T23:59:59.000Z

260

Safeguards and security concept for the Secure Automated Fabrication (SAF) and Liquid Metal Reactor (LMR) fuel cycle, SAF line technical support  

SciTech Connect (OSTI)

This report is a safeguards and security concept system review for the secure automated fabrication (SAF) and national liquid metal reactor (LMR) fuel programs.

Schaubert, V.J.; Remley, M.E.; Grantham, L.F.

1986-02-21T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Report on the US Program of Technical Assistance to Safeguards of the International Atomic Energy Agency (POTAS)  

SciTech Connect (OSTI)

This document summarizes the work done under the US Program of Technical Assistance to IAEA Safeguards (POTAS), providing the US Government, IAEA, and others with a short review of the progress made in the program since its inception. Becaue of the size and complexity of the program, only major accomplishments are presented. These are grouped under the following categories: (1) equipment and standard which cover assay of irradiated and unirradiated nuclear materials, automatic data processing, and physical standards; (2) experts who are involved in technology transfer, training, system design, and safeguard information processing and analysis; (3) system studies which cover diversion hazard analysis, safeguards approaches and application, and inspection effort planning and forecasting; (4) techniques, procedures, and equipment evaluation; (5) training of IAEA inspectors and safeguards specialists from member states. The major achievement has been the provisions of safeguards equipment designed to be reliable, and tamper resistant, some of which have already been in use in the field by inspector or by IAEA staff members in Vienna. These are listed in a table. (AT)

Not Available

1981-05-01T23:59:59.000Z

262

FUTURE POWER GRID INITIATIVE Future Power Grid  

E-Print Network [OSTI]

FUTURE POWER GRID INITIATIVE Future Power Grid Control Paradigm OBJECTIVE This project integration & exploit the potential of distributed smart grid assets » Significantly reduce the risk of advanced mathematical models, next- generation simulation and analytics capabilities for the power grid

263

Lake Michigan Corridor Alternative Fuel Implementation Initiative  

Broader source: Energy.gov (indexed) [DOE]

Fleet Program (Indiana) 2.4: Document Success and Quantify Impact 2.5: Generation of Smart Green Purchasing Policy Task 3: Barrier Reduction Initiatives 3.1: Weights and...

264

Feasibility Study of Economics and Performance of Biomass Power Generation at the Former Farmland Industries Site in Lawrence, Kansas. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites  

SciTech Connect (OSTI)

Under the RE-Powering America's Land initiative, the U.S. Environmental Protection Agency (EPA) provided funding to the National Renewable Energy Laboratory (NREL) to support a feasibility study of biomass renewable energy generation at the former Farmland Industries site in Lawrence, Kansas. Feasibility assessment team members conducted a site assessment to gather information integral to this feasibility study. Information such as biomass resources, transmission availability, on-site uses for heat and power, community acceptance, and ground conditions were considered.

Tomberlin, G.; Mosey, G.

2013-03-01T23:59:59.000Z

265

Development of a Safeguards Verification Method and Instrument to Detect Pin Diversion from Pressurized Water Reactor (PWR) Spent Fuel Assemblies Phase I Study  

SciTech Connect (OSTI)

A novel methodology to detect diversion of spent fuel from Pressurized Water Reactors (PWR) has been developed in order to address a long unsolved safeguards verification problem for international safeguards community such as International Atomic Energy Agency (IAEA) or European Atomic Energy Community (EURATOM). The concept involves inserting tiny neutron and gamma detectors into the guide tubes of a spent fuel assembly and measuring the signals. The guide tubes form a quadrant symmetric pattern in the various PWR fuel product lines and the neutron and gamma signals from these various locations are processed to obtain a unique signature for an undisturbed fuel assembly. Signatures based on the neutron and gamma signals individually or in a combination can be developed. Removal of fuel pins from the assembly will cause the signatures to be visibly perturbed thus enabling the detection of diversion. All of the required signal processing to obtain signatures can be performed on standard laptop computers. Monte Carlo simulation studies and a set of controlled experiments with actual commercial PWR spent fuel assemblies were performed and validated this novel methodology. Based on the simulation studies and benchmarking measurements, the methodology developed promises to be a powerful and practical way to detect partial defects that constitute 10% or more of the total active fuel pins. This far exceeds the detection threshold of 50% missing pins from a spent fuel assembly, a threshold defined by the IAEA Safeguards Criteria. The methodology does not rely on any operator provided data like burnup or cooling time and does not require movement of the fuel assembly from the storage rack in the spent fuel pool. A concept was developed to build a practical field device, Partial Defect Detector (PDET), which will be completely portable and will use standard radiation measuring devices already in use at the IAEA. The use of the device will not require any information provided by the operator or any prior knowledge of the spent fuel assembly. The device can also be operated without any movement of the spent fuel from its storage position. Based on parametric studies conducted via computer simulation, the device should be able to detect diversion of as low as ten percent of the missing or replaced fuel from an assembly regardless of the location of the missing fuel within the assembly, of the cooling time, initial fuel enrichment or burnup levels. Conditions in the spent fuel pool such as clarity of the water or boron content are also not issues for this device. The shape of the base signature is principally dependent on the layout of the guide tubes in the various types of PWR fuel assemblies and perturbations in the form of replaced fuel pins will distort this signature. These features of PDET are all unique and overcome limitation and disadvantages presented by currently used devices such as the Fork detector or the Cerenkov Viewing Device. Thus, this device when developed and tested could fill an important need in the safeguards area for partial defect detection, a technology that the IAEA has been seeking for the past few decades.

Ham, Y S; Sitaraman, S

2008-12-24T23:59:59.000Z

266

Evaluating Safeguards Benefits of Process Monitoring as compared with Nuclear Material Accountancy  

SciTech Connect (OSTI)

This paper illustrates potential safeguards benefits that process monitoring (PM) may have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). This benefit is illustrated by quantifying the standard deviation associated with detecting a considered material diversion scenario using either an NMA-based method or a PM-based approach. To illustrate the benefits of PM for effective safeguards, we consider a reprocessing facility. We assume that the diversion of interest for detection manifests itself as a loss of Pu caused by abnormally operating a dissolver for an extended period to accomplish protracted diversion (or misdirection) of Pu to a retained (unconditioned) waste stream. For detecting the occurrence of this diversion (which involves anomalous operation of the dissolver), we consider two different data evaluation and integration (DEI) approaches, one based on NMA and the other based on PM. The approach based on PM does not directly do mass balance calculations, but rather monitors for the possible occurrence of anomaly patterns related to potential loss of nuclear material. It is thus assumed that the loss of a given mass amount of nuclear material can be directly associated with the execution of proliferation-driven activities that trigger the occurrence of an anomaly pattern consisting of series of events or signatures occurring at different unit operations and time instances. By effectively assessing these events over time and space, the PM-based DEI approach tries to infer whether this specific pattern of events has occurred and how many times within a given time period. To evaluate the goodness of PM, the 3 Sigma of the estimated mass loss is computed under both DEI approaches as function of the number of input batches processed. Simulation results are discussed.

Humberto Garcia; Wen-Chiao Lin; Reed Carlson

2014-07-01T23:59:59.000Z

267

Safeguards & Security (S&S) Program | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticlesHuman Resources HumanOfficeOrganizationProjectsofSafeguards

268

Safeguards & Security | U.S. DOE Office of Science (SC)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGEComplainant,.VisitorSafeguards &

269

Manual for Implementation of the Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual provides detailed information for implementing the requirements of DOE O 142.2A, dated 12-15-06; the Agreement Between the United States of America and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in the United States; the Original Protocol to the Agreement; the Additional Protocol to the Agreement signed by the United States and the IAEA on June 12, 1998; and the Interagency Procedures for the Implementation of the U.S.-IAEA Safeguards Agreement. No cancellation. Admin Chg 1, dated 6-27-13, cancels DOE M 142.2-1. Certified 12-3-14.

1998-06-12T23:59:59.000Z

270

Manual for Implementation of the Voluntary Offer Safeguards Agreement and Additional Protocol with the International Atomic Energy Agency  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual provides detailed information for implementing the requirements of DOE O 142.2A, dated 12-15-06; the Agreement Between the United States of America and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in the United States; the Original Protocol to the Agreement; the Additional Protocol to the Agreement signed by the United States and the IAEA on June 12, 1998; and the Interagency Procedures for the Implementation of the U.S.-IAEA Safeguards Agreement. No cancellation. Admin Chg 1, 6-27-13

1998-06-12T23:59:59.000Z

271

Implementation of safeguards and security for fissile materials disposition reactor alternative facilities  

SciTech Connect (OSTI)

A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular attention will be given to the reactor alternatives which include existing, partially completed, advanced or evolutionary LWRs and CANDU reactors. The various reactor alternatives are all very similar and include processing which converts Pu to a usable form for fuel fabrication, a MOX fuel fab facility located in either the US or in Europe, US LWRs or the CANDU reactors and ultimate disposal of spent fuel in a geologic repository. This paper focuses on how the objectives of reducing security risks and strengthening arms reduction and nonproliferation will be accomplished and the possible impacts of meeting these objectives on facility operations and design. Some of the areas in this paper include: (1) domestic and international safeguards requirements, (2) non-proliferation criteria and measures, (3) the threat, and (4) potential proliferation risks, the impacts on the facilities, and safeguards and security issues unique to the presence of Category 1 or strategic special nuclear material.

Jaeger, C.D.; Duggan, R.A.; Tolk, K.M.

1995-10-01T23:59:59.000Z

272

Diophantine Generation,  

E-Print Network [OSTI]

Diophantine Generation, Horizontal and Vertical Problems, and the Weak Vertical Method Alexandra Shlapentokh Diophantine Sets, Definitions and Generation Diophantine Sets Diophantine Generation Properties of Diophantine Generation Diophantine Family of Z Diophantine Family of a Polynomial Ring Going Down Horizontal

Shlapentokh, Alexandra

273

APEC Smart Grid Initiative  

SciTech Connect (OSTI)

This brief paper describes the activities of the Asia Pacific Economic Cooperation (APEC) Smart Grid Initiative (ASGI) which is being led by the U.S. and developed by the APEC Energy Working Group. In the paper, I describe the origin of the initiative and briefly mention the four major elements of the initiative along with existing APEC projects which support it.

Bloyd, Cary N.

2012-03-01T23:59:59.000Z

274

Integrated Process Monitoring based on Systems of Sensors for Enhanced Nuclear Safeguards Sensitivity and Robustness  

SciTech Connect (OSTI)

This paper illustrates safeguards benefits that process monitoring (PM) can have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). In order to infer the possible existence of proliferation-driven activities, the objective of NMA-based methods is often to statistically evaluate materials unaccounted for (MUF) computed by solving a given mass balance equation related to a material balance area (MBA) at every material balance period (MBP), a particular objective for a PM-based approach may be to statistically infer and evaluate anomalies unaccounted for (AUF) that may have occurred within a MBP. Although possibly being indicative of proliferation-driven activities, the detection and tracking of anomaly patterns is not trivial because some executed events may be unobservable or unreliably observed as others. The proposed similarity between NMA- and PM-based approaches is important as performance metrics utilized for evaluating NMA-based methods, such as detection probability (DP) and false alarm probability (FAP), can also be applied for assessing PM-based safeguards solutions. To this end, AUF count estimates can be translated into significant quantity (SQ) equivalents that may have been diverted within a given MBP. A diversion alarm is reported if this mass estimate is greater than or equal to the selected value for alarm level (AL), appropriately chosen to optimize DP and FAP based on the particular characteristics of the monitored MBA, the sensors utilized, and the data processing method employed for integrating and analyzing collected measurements. To illustrate the application of the proposed PM approach, a protracted diversion of Pu in a waste stream was selected based on incomplete fuel dissolution in a dissolver unit operation, as this diversion scenario is considered to be problematic for detection using NMA-based methods alone. Results demonstrate benefits of conducting PM under a system-centric strategy that utilizes data collected from a system of sensors and that effectively exploits known characterizations of sensors and facility operations in order to significantly improve anomaly detection, reduce false alarm, and enhance assessment robustness under unreliable partial sensor information.

Humberto E. Garcia

2014-07-01T23:59:59.000Z

275

Feasibility Study of Economics and Performance of Geothermal Power Generation at the Lakeview Uranium Mill Site in Lakeview, Oregon. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites  

SciTech Connect (OSTI)

The U.S. Environmental Protection Agency (EPA), in accordance with the RE-Powering America's Land initiative, selected the Lakeview Uranium Mill site in Lakeview, Oregon, for a feasibility study of renewable energy production. The EPA contracted with the National Renewable Energy Laboratory (NREL) to provide technical assistance for the project. The purpose of this report is to describe an assessment of the site for possible development of a geothermal power generation facility and to estimate the cost, performance, and site impacts for the facility. In addition, the report recommends development pathways that could assist in the implementation of a geothermal power system at the site.

Hillesheim, M.; Mosey, G.

2013-11-01T23:59:59.000Z

276

Initial Radionuclide Inventories  

SciTech Connect (OSTI)

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as 2030 and 2033, depending on the type of waste. TSPA-LA uses the results of this analysis to decay the inventory to the year of repository closure projected for the year of 2060.

H. Miller

2004-09-19T23:59:59.000Z

277

The ASSESS (Analytic System and Software for Evaluating Safeguards and Security) Outsider module with multiple analyses  

SciTech Connect (OSTI)

The Analytic System and Software for Evaluating Safeguards and Security (ASSESS) includes modules for analyzing vulnerabilities against outsider and insider adversaries. The ASSESS Outsider Analysis Module has been upgraded to allow for defining, analyzing, and displaying the results of multiple analyses. Once a set of threat definitions have been defined in one Outsider file, they can be readily copied to other Outsider files. This multiple analysis, or batch, mode of operation provides an efficient way of covering the standard DOE outsider threat spectrum. A new approach for coupling the probability of interruption, P(I), values and values calculated by the ASSESS Neutralization module has been implemented in Outsider and is described. An enhanced capability for printing results of these multiple analyses is also included in the upgraded Outside module. 7 refs., 7 figs., 1 tab.

Snell, M.K.; Winblad, A.E. (Sandia National Labs., Albuquerque, NM (USA)); Bingham, B.; Key, B.; Walker, S. (Science and Engineering Associates, Inc., Albuquerque, NM (USA))

1990-01-01T23:59:59.000Z

278

Strategic analysis for safeguards systems: a feasibility study. Volume 2. Appendix  

SciTech Connect (OSTI)

This appendix provides detailed information regarding game theory (strategic analysis) and its potential role in safeguards to supplement the main body of this report. In particualr, it includes an extensive, though not comprehensive review of literature on game theory and on other topics that relate to the formulation of a game-theoretic model (e.g. the payoff functions). The appendix describes the basic form and components of game theory models, and the solvability of various models. It then discusses three basic issues related to the use of strategic analysis in material accounting: (1) its understandability; (2) its viability in regulatory settings; and (3) difficulties in the use of mixed strategies. Each of the components of a game theoretic model are then discussed and related to the present context.

Goldman, A J

1984-12-01T23:59:59.000Z

279

Safeguards and Security FY 1996 Program Plan: WBS 6.6  

SciTech Connect (OSTI)

The Safeguards and Security (SAS) Program is based upon integrity, competence and innovation in the protection of the public and Hanford resources through: (1) outstanding assistance, oversight, education, and counsel to their customers to ensure the protection of the public, site personnel, assets, and information; (2) value-added and cost-effective solutions to Hanford issues; and (3) risk management techniques to ensure effective asset protection, site accessibility, and the flexibility to adapt to changing customer needs. This plan is divided into two parts: overview and SAS WBS (work breakdown structure) dictionary sheets. The overview is divided into vision and mission, goals and objectives, assumptions and priorities, milestones, and a summary. The SAS WBS dictionary sheets are divided into department overhead, general and administrative, sitewide support, Hanford patrol, traffic safety, and locksmith services.

Lee, F.D.

1995-08-01T23:59:59.000Z

280

Ultra-high-resolution alpha spectrometry for nuclear forensics and safeguards applications  

SciTech Connect (OSTI)

We will present our work on the development of ultra-high-resolution detectors for alpha particle spectrometry. These detectors, based on superconducting transition-edge sensors, offer energy resolution that is five to ten times better than conventional silicon detectors. Using these microcalorimeter detectors, the isotopic composition of mixed-actinide samples can be determined rapidly without the need for actinide separation chemistry to isolate each element, or mass spectrometry to separate isotopic signatures that can not be resolved using traditional alpha spectrometry (e.g. Pu-239/Pu-240, or Pu-238/Am-241). This paper will cover the detector and measurement system, actinide source preparation, and the quantitative isotopic analysis of a number of forensics- and safeguards-relevant radioactive sources.

Bacrania, Minesh K [Los Alamos National Laboratory; Croce, Mark [Los Alamos National Laboratory; Bond, Evelyn [Los Alamos National Laboratory; Dry, Donald [Los Alamos National Laboratory; Moody, W. Allen [Los Alamos National Laboratory; Lamont, Stephen [Los Alamos National Laboratory; Rabin, Michael [Los Alamos National Laboratory; Rim, Jung [Los Alamos National Laboratory; Smith, Audrey [Los Alamos National Laboratory; Beall, James [NIST-BOULDER; Bennett, Douglas [NIST-BOULDER; Kotsubo, Vincent [NIST-BOULDER; Horansky, Robert [NIST-BOULDER; Hilton, Gene [NIST-BOULDER; Schmidt, Daniel [NIST-BOULDER; Ullom, Joel [NIST-BOULDER; Cantor, Robin [STAR CRYOELECTRONICS

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Precision Information Environment (PIE) for International Safeguards: Pre-Demonstration Development Use Cases  

SciTech Connect (OSTI)

In FY2013, the PIE International Safeguards team demonstrated our development progress to U.S. Department of Energy (DOE) staff from the Office of Nonproliferation and International Security (NA-24, our client) and the Office of Defense Nuclear Nonproliferation Research and Development (NA-22). Following the demonstration, the team was asked by our client to complete additional development prior to a planned demonstration at the International Atomic Energy Agency (IAEA), scheduled tentatively for January or spring of 2014. The team discussed four potential areas for development (in priority order), and will develop them as time and funding permit prior to an IAEA demonstration. The four capability areas are: 1. Addition of equipment manuals to PIE-accessible files 2. Optical character recognition (OCR) of photographed text 3. Barcode reader with information look-up from a database 4. Add Facilities to Data Model 5. Geospatial capabilities with information integration Each area will be described below in a use case.

Gastelum, Zoe N.; Henry, Michael J.

2013-11-13T23:59:59.000Z

282

International and national security applications of cryogenic detectors - mostly nuclear safeguards  

SciTech Connect (OSTI)

As with science, so with security - in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma ray, neutron, and alpha particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invi sible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

Rabin, Michael W [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

283

Safeguards design strategies: designing and constructing new uranium and plutonium processing facilities in the United States  

SciTech Connect (OSTI)

In the United States, the Department of Energy (DOE) is transforming its outdated and oversized complex of aging nuclear material facilities into a smaller, safer, and more secure National Security Enterprise (NSE). Environmental concerns, worker health and safety risks, material security, reducing the role of nuclear weapons in our national security strategy while maintaining the capability for an effective nuclear deterrence by the United States, are influencing this transformation. As part of the nation's Uranium Center of Excellence (UCE), the Uranium Processing Facility (UPF) at the Y-12 National Security Complex in Oak Ridge, Tennessee, will advance the U.S.'s capability to meet all concerns when processing uranium and is located adjacent to the Highly Enriched Uranium Materials Facility (HEUMF), designed for consolidated storage of enriched uranium. The HEUMF became operational in March 2010, and the UPF is currently entering its final design phase. The designs of both facilities are for meeting anticipated security challenges for the 21st century. For plutonium research, development, and manufacturing, the Chemistry and Metallurgy Research Replacement (CMRR) building at the Los Alamos National Laboratory (LANL) in Los Alamos, New Mexico is now under construction. The first phase of the CMRR Project is the design and construction of a Radiological Laboratory/Utility/Office Building. The second phase consists of the design and construction of the Nuclear Facility (NF). The National Nuclear Security Administration (NNSA) selected these two sites as part of the national plan to consolidate nuclear materials, provide for nuclear deterrence, and nonproliferation mission requirements. This work examines these two projects independent approaches to design requirements, and objectives for safeguards, security, and safety (3S) systems as well as the subsequent construction of these modern processing facilities. Emphasis is on the use of Safeguards-by-Design (SBD), incorporating Systems Engineering (SE) principles for these two projects.

Scherer, Carolynn P [Los Alamos National Laboratory; Long, Jon D [Los Alamos National Laboratory

2010-09-28T23:59:59.000Z

284

National Laboratory Impact Initiative  

Broader source: Energy.gov [DOE]

The National Laboratory Impact Initiative supports the relationship between the Office of Energy Efficiency & Renewable Energy and the national laboratory enterprise.  The national laboratories...

285

Energy Security Initiatives Update  

Broader source: Energy.gov (indexed) [DOE]

-- Aurora Electrical System Vulnerability Assessment and Mitigation Actions FUPWG-EEI CA Net Zero Energy Initiative (Vandenberg AFB, CA) Energy Security Tiger Team Visit (Ft...

286

Energy Security Initiatives Update  

Broader source: Energy.gov [DOE]

Presentation—given at the Spring 2009 Federal Utility Partnership Working Group (FUPWG) meeting—lists Federal government energy security initiatives.

287

Salt Waste Processing Initiatives  

Office of Environmental Management (EM)

1 Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives...

288

Initiating Business with INL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Initiating Business with INL The INL Small Business Program Office (SBPO) serves as the advocate and point of contact for businesses seeking contracting opportunities. We ask you...

289

Strategic Growth Initiative (Michigan)  

Broader source: Energy.gov [DOE]

A joint venture between Michigan Department of Agriculture and Rural Development (MDARD) and the Michigan Economic Development Corporation (MEDC), the Strategic Growth Initiative Grant Program was...

290

1. Generation 1 1. Generation  

E-Print Network [OSTI]

1. Generation 1 _________________________________________________________________________ 1. Generation Sound and vibrations or, in more general terms, oscillations of matter (solids or fluids) are generated in many different dynamic processes. The basic mechanisms which underlie these oscillations

Berlin,Technische Universität

291

Network support for system initiated checkpoints  

DOE Patents [OSTI]

A system, method and computer program product for supporting system initiated checkpoints in parallel computing systems. The system and method generates selective control signals to perform checkpointing of system related data in presence of messaging activity associated with a user application running at the node. The checkpointing is initiated by the system such that checkpoint data of a plurality of network nodes may be obtained even in the presence of user applications running on highly parallel computers that include ongoing user messaging activity.

Chen, Dong; Heidelberger, Philip

2013-01-29T23:59:59.000Z

292

LOCKOUT/TAGOUT PROGRAM The purpose of the Lockout/Tagout program is to safeguard employees from unexpected start-up of  

E-Print Network [OSTI]

LOCKOUT/TAGOUT PROGRAM The purpose of the Lockout/Tagout program is to safeguard employees from the Lockout/Tagout Program, please contact the EH&S Occupational Health and Safety Program at 725-3209. #12;

293

A Materials Facilities Initiative -  

E-Print Network [OSTI]

A Materials Facilities Initiative - FMITS & MPEX D.L. Hillis and ORNL Team Fusion & Materials for Nuclear Systems Division July 10, 2014 #12;2 Materials Facilities Initiative JET ITER FNSF Fusion Reactor Challenges for materials: fluxes and fluence, temperatures 50 x divertor ion fluxes up to 100 x neutron

294

Self-Generation Incentive Program  

Broader source: Energy.gov [DOE]

Initiated in 2001, the Self-Generation Incentive Program (SGIP) offers incentives to customers who produce electricity with wind turbines, fuel cells, various forms of combined heat and power (CHP)...

295

A study of a zone approach to IAEA (International Atomic Energy Agency) safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle  

SciTech Connect (OSTI)

At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches.

Fishbone, L.G.; Higinbotham, W.A.

1986-06-01T23:59:59.000Z

296

Breckinridge Project, initial effort  

SciTech Connect (OSTI)

The project cogeneration plant supplies electric power, process steam and treated boiler feedwater for use by the project plants. The plant consists of multiple turbine generators and steam generators connected to a common main steam header. The major plant systems which are required to produce steam, electrical power and treated feedwater are discussed individually. The systems are: steam, steam generator, steam generator fuel, condensate and feedwater deaeration, condensate and blowdown collection, cooling water, boiler feedwater treatment, coal handling, ash handling (fly ash and bottom ash), electrical, and control system. The plant description is based on the Phase Zero design basis established for Plant 31 in July of 1980 and the steam/condensate balance as presented on Drawing 31-E-B-1. Updating of steam requirements as more refined process information becomes available has generated some changes in the steam balance. Boiler operation with these updated requirements is reflected on Drawing 31-D-B-1A. The major impact of updating has been that less 600 psig steam generated within the process units requires more extraction steam from the turbine generators to close the 600 psig steam balance. Since the 900 psig steam generation from the boilers was fixed at 1,200,000 lb/hr, the additional extraction steam required to close the 600 psig steam balance decreased the quantity of electrical power available from the turbine generators. In the next phase of engineering work, the production of 600 psig steam will be augmented by increasing convection bank steam generation in the Plant 3 fired heaters by 140,000 to 150,000 lb/hr. This modification will allow full rated power generation from the turbine generators.

none,

1982-01-01T23:59:59.000Z

297

Initial data engineering  

E-Print Network [OSTI]

We present a local gluing construction for general relativistic initial data sets. The method applies to generic initial data, in a sense which is made precise. In particular the trace of the extrinsic curvature is not assumed to be constant near the gluing points, which was the case for previous such constructions. No global conditions on the initial data sets such as compactness, completeness, or asymptotic conditions are imposed. As an application, we prove existence of spatially compact, maximal globally hyperbolic, vacuum space-times without any closed constant mean curvature spacelike hypersurface.

Piotr T. Chrusciel; James Isenberg; Daniel Pollack

2005-06-16T23:59:59.000Z

298

Design and development of a 3He replacement safeguards neutron counter based on 10B-lined proportional detector technology  

SciTech Connect (OSTI)

This presentation represents an overview of the experimental evaluation of a boron-lined proportional technology performed within an NA-241 sponsored project on testing of boron-lined proportional counters for the purpose of replacement of {sup 3}He technologies. The presented boron-lined technology will be utilized in a design of a full scale safeguards neutron coincidence counter. The design considerations and the Monte Carlo performance predictions for the counter are also presented.

Henzlova, Daniela [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Menlove, Howard O. [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory; Rael, Carlos D. [Los Alamos National Laboratory; Martinez, Isaac P. [Los Alamos National Laboratory; Marlow, Johnna B. [Los Alamos National Laboratory

2012-07-16T23:59:59.000Z

299

FEMO, A FLOW AND ENRICHMENT MONITOR FOR VERIFYING COMPLIANCE WITH INTERNATIONAL SAFEGUARDS REQUIREMENTS AT A GAS CENTRIFUGE ENRICHMENT FACILITY  

SciTech Connect (OSTI)

A number of countries have received construction licenses or are contemplating the construction of large-capacity gas centrifuge enrichment plants (GCEPs). The capability to independently verify nuclear material flows is a key component of international safeguards approaches, and the IAEA does not currently have an approved method to continuously monitor the mass flow of 235U in uranium hexafluoride (UF6) gas streams. Oak Ridge National Laboratory is investigating the development of a flow and enrichment monitor, or FEMO, based on an existing blend-down monitoring system (BDMS). The BDMS was designed to continuously monitor both 235U mass flow and enrichment of UF6 streams at the low pressures similar to those which exists at GCEPs. BDMSs have been installed at three sites-the first unit has operated successfully in an unattended environment for approximately 10 years. To be acceptable to GCEP operators, it is essential that the instrument be installed and maintained without interrupting operations. A means to continuously verify flow as is proposed by FEMO will likely be needed to monitor safeguards at large-capacity plants. This will enable the safeguards effectiveness that currently exists at smaller plants to be maintained at the larger facilities and also has the potential to reduce labor costs associated with inspections at current and future plants. This paper describes the FEMO design requirements, operating capabilities, and development work required before field demonstration.

Gunning, John E [ORNL; Laughter, Mark D [ORNL; March-Leuba, Jose A [ORNL

2008-01-01T23:59:59.000Z

300

The President's Biofuels Initiative  

Broader source: Energy.gov (indexed) [DOE]

Biofuels Initiative Neil Rossmeissl Office of the Biomass Program Energy Efficiency and Renewable Energy Why Can't We Regulate Our Way There? 25 20 15 10 5 0 1970 1980 1990 2000...

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Application of EMCAS timeliness model to the safeguards/facility interface  

SciTech Connect (OSTI)

The Hanford operating contractor has developed a timeliness model for periodic mass balance tests (MBTs) for loss of special nuclear material (SNM). The purpose of the model is to compute the probability that an adversary will be detected by a periodic MBT before he could escape from a facility with stolen SNM using stealth and deceit to avoid detection. The model considers (a) the loss detection sensitivity of the MBT, (b) the time between MBTs, and (c) the statistical distribution of the total time required to complete stealth and deceit strategies. The model shows whether or not it is cost-effective to conduct frequent MBTs for loss and where improvements should be made. The Evaluation Methods for Material Control and Accountability Safeguards Systems (EMCAS) timeliness model computes the loss detection capability of periodic materials control and accounting (MC A) tests in terms of (a) the ability of the test to detect the specified target quantity and (b) the probability that the MC A test will occur before the adversary can complete the sequence of stealth and deceit strategies required to avoid detection.

Eggers, R.F.; Giese, E.W.

1987-01-01T23:59:59.000Z

302

Savannah River Site delayed neutron instruments for safeguards measurements. Revision 1  

SciTech Connect (OSTI)

The Savannah River Site (SRS) includes a variety of nuclear production facilities that, since 1953, have processed special nuclear materials (SNM) including highly-enriched uranium (>90% {sup 235}U), recycled enriched uranium ({approximately}50% {sup 235}U + 40% {sup 236}U), low burnup plutonium (> 90% {sup 239}Pu + < 6% {sup 240}Pu ) and several other nuclear materials such as heat source plutonium ({sup 238}Pu). DOE Orders, primarily 5633.3, require all nuclear materials to be safeguarded through accountability and material control. Accountability measurements determine the total amount of material in a facility, balancing inventory changes against receipts and shipments, to provide assurance (delayed) that all material was present. Material control immediately detects or deters theft or diversion by assuring materials remain in assigned locations or by impeding unplanned movement of materials within or from a material access area. Goals for accountability or material control, and, therefore, the design of measurement systems, are distinctly different. Accountability measurements are optimized for maximum precision and accuracy, usually for large amounts of special nuclear material. Material control measurements are oriented more toward security features and often must be optimized for sensitivity, to detect small amounts of materials where none should be.

Studley, R.V.

1992-12-31T23:59:59.000Z

303

AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS  

SciTech Connect (OSTI)

Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion / analyte redox adjustment, chemical separations, radiochemical detection and data analysis / reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs.

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

2008-07-13T23:59:59.000Z

304

Safeguards Verification Measurements using Laser Ablation, Absorbance Ratio Spectrometry in Gaseous Centrifuge Enrichment Plants  

SciTech Connect (OSTI)

Laser Ablation Absorbance Ratio Spectrometry (LAARS) is a new verification measurement technology under development at the US Department of Energy (DOE) Pacific Northwest National Laboratory (PNNL). LAARS uses three lasers to ablate and then measure the relative isotopic abundance of uranium compounds. An ablation laser is tightly focused on uranium-bearing solids, producing a small atomic uranium vapor plume. Two collinear wavelength-tuned spectrometry lasers transit through the plume and the absorbance of U-235 and U-238 isotopes are measured to determine U-235 enrichment. The measurement is independent of chemical form and degree of dilution with nuisance dust and other materials. LAARS has high relative precision and detection limits approaching the femtogram range for U-235. The sample is scanned and assayed point-by-point at rates reaching 1 million measurements/hour, enabling LAARS to detect and analyze uranium in trace samples. The spectrometer is assembled using primarily commercially available components and features a compact design and automated analysis.Two specific gaseous centrifuge enrichment plant (GCEP) applications of the spectrometer are currently under development: 1) LAARS-Environmental Sampling (ES), which collects and analyzes aerosol particles for GCEP misuse detection and 2) LAARS-Destructive Assay (DA), which enables onsite enrichment DA sample collection and analysis for protracted diversion detection. The two applications propose game-changing technological advances in GCEP safeguards verification.

Anheier, Norman C.; Cannon, Bret D.; Kulkarni, Gourihar R.; Munley, John T.; Nelson, Danny A.; Qiao, Hong (Amy) [Amy; Phillips, Jon R.

2012-07-17T23:59:59.000Z

305

The Feasibility of Cask "Fingerprinting" as a Spent-Fuel, Dry-Storage Cask Safeguards Technique  

SciTech Connect (OSTI)

This report documents a week-long measurement campaign conducted on six, dry-storage, spent-nuclear-fuel storage casks at the Idaho National Laboratory. A gamma-ray imager, a thermal-neutron imager and a germanium spectrometer were used to collect data on the casks. The campaign was conducted to examine the feasibility of using the cask radiation signatures as unique identifiers for individual casks as part of a safeguards regime. The results clearly show different morphologies for the various cask types although the signatures are deemed insufficient to uniquely identify individual casks of the same type. Based on results with the germanium spectrometer and differences between thermal neutron images and neutron-dose meters, this result is thought to be due to the limitations of the extant imagers used, rather than of the basic concept. Results indicate that measurements with improved imagers could contain significantly more information. Follow-on measurements with new imagers either currently available as laboratory prototypes or under development are recommended.

Ziock, K P; Vanier, P; Forman, L; Caffrey, G; Wharton, J; Lebrun, A

2005-07-27T23:59:59.000Z

306

Long-term need for new generating capacity  

SciTech Connect (OSTI)

Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity by the year 2000. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will not be acceptable to society without solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Technology improvements and waste management practices must be pursued to mitigate environmental and safety impacts from electricity generation. 26 refs., 14 figs., 23 tabs.

Bloomster, C.H.; Merrill, E.T.

1987-03-01T23:59:59.000Z

307

Generating Binary Black Hole Initial Data Gregory B. Cook  

E-Print Network [OSTI]

vector : tµ = nµ + µ ds 2 = - 2 dt 2 + ij(dx i + i dt)(dx j + j dt) µ = gµ + nµn Kµ = -1 2 µ Lng + nµn Kµ = -1 2 µ Lng Constraint equations ¯R + K 2 - KijK ij = 16 ¯j K ij - ij K = 8j i Sµ µ

Cook, Greg

308

Ways & Means PRIME: Probabilistic Initial 3D Model Generation  

E-Print Network [OSTI]

Google Inc., 1600 Amphitheatre Parkway, Mountain View, CA 94043, USA *Correspondence: hael University Medical School, Fairchild Building, 1st Floor, 299 Campus Drive, Stanford, CA 94305-5126, USA 2- dividual biomolecules (single-particle cryo-EM) is a powerful tool for obtaining information about

Tomkins, Andrew

309

RCRA facility stabilization initiative  

SciTech Connect (OSTI)

The RCRA Facility Stabilization Initiative was developed as a means of implementing the Corrective Action Program`s management goals recommended by the RIS for stabilizing actual or imminent releases from solid waste management units that threaten human health and the environment. The overall goal of stabilization is to, as situations warrant, control or abate threats to human health and/or the environment from releases at RCRA facilities, and/or to prevent or minimize the further spread of contamination while long-term remedies are pursued. The Stabilization initiative is a management philosophy and should not be confused with stabilization technologies.

Not Available

1995-02-01T23:59:59.000Z

310

Clean Coal Power Initiative  

SciTech Connect (OSTI)

This report is the fifth quarterly Technical Progress Report submitted by NeuCo, Incorporated, under Award Identification Number, DE-FC26-04NT41768. This award is part of the Clean Coal Power Initiative (''CCPI''), the ten-year, $2B initiative to demonstrate new clean coal technologies in the field. This report is one of the required reports listed in Attachment B Federal Assistance Reporting Checklist, part of the Cooperative Agreement. The report covers the award period January 1, 2006 - March 31, 2006 and NeuCo's efforts within design, development, and deployment of on-line optimization systems during that period.

Doug Bartlett; Rob James; John McDermott; Neel Parikh; Sanjay Patnaik; Camilla Podowski

2006-03-31T23:59:59.000Z

311

Initiatives | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecemberInitiatives Initiatives Through a variety of cross-cutting program

312

Staff Initials ______ Membership Application*  

E-Print Network [OSTI]

NOT include the basketball gym. #12;Staff Initials ______ Furman University Fitness Center Acknowledgement and Release Form I, the undersigned, acknowledge that I am at least 18 years of age and that I am voluntarily here) I acknowledge that I am aware of the possible risks, dangers, and hazards associated with my

313

Global Threat Reduction Initiative  

E-Print Network [OSTI]

Global Threat Reduction Initiative ­ Conversion Program: Reduced Enrichment for Research and Test the dual application of splitting the atom, U.S. policy towards civilian use of highly enriched uranium and test reactors fueled first with low enriched uranium (LEU) and then later with HEU. By the early 1970s

Kemner, Ken

314

Sustainability Initiative Executive Summary  

E-Print Network [OSTI]

UW­Madison Sustainability Initiative Executive Summary October 2010 #12;2 We are pleased to present the final report of the campus Sustainability Task Force. This report fulfills the charge we gave to sustainability for consideration by UW­Madison's leadership and campus community. There are many reasons why

Sheridan, Jennifer

315

INITIATIVES and CAMPAIGN LAUNCH  

E-Print Network [OSTI]

to develop a culture of safety for all our community members · To achieve this, York U has been working1 SAFETY INITIATIVES and CAMPAIGN LAUNCH COMMUNITY SAFETY COUNCIL COMMUNITY UPDATE 30 January 2013 the person per thousand compared to Toronto #12;4 University's Safety Plan · In June 2010, the Metropolitan

316

GLOBAL TAXONOMY INITIATIVE  

E-Print Network [OSTI]

#12;THE GLOBAL TAXONOMY INITIATIVE: Using Systematic Inventories to Meet Country and Regional Needs International #12;Table of Contents Introduction 1 I. Using Inventories to Build Capacity and Advance the GTI 2 for systematic inventories. A major component of the workshop addressed how systematic inventories can serve

Grant, Taran

317

Distributed Generation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

come a long way in addressing interconnection standards for distributed generation, utilities have largely overlooked the untapped potential of these resources. Under certain...

318

Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities  

SciTech Connect (OSTI)

The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF{sub 6} gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman - Olander vertical velocity radial distribution and the solution was obtained using the Matlab software tool. The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the 'on site' inspectors' measurements.

Mercurio, G.; Peerani, P.; Richir, P.; Janssens, W.; Eklund, G. [European Commission, Joint Research Centre, Institute for Transuranium Elements Via Fermi, 2749-TP181,20127 Ispra (Italy)

2012-09-26T23:59:59.000Z

319

Remote-Reading Safety and Safeguards Surveillance System for 3013 Containers  

SciTech Connect (OSTI)

At Hanford's Plutonium Finishing Plant (PFP), plutonium oxide is being loaded into stainless steel containers for long-term storage on the Hanford Site. These containers consist of two weld-sealed stainless steel cylinders nested one within the other. A third container holds the plutonium within the inner cylinder. This design meets the U.S. Department of Energy (DOE) storage standard, DOE-STD- 3013-2000, which anticipates a 50-year storage lifetime. The 3013 standard also requires a container surveillance program to continuously monitor pressure and to assure safeguards are adequate. However, the configuration of the container system makes using conventional measurement and monitoring methods difficult. To better meet the 3013 monitoring requirements, a team from Fluor Hanford (who manages the PFP), Pacific Northwest National Laboratory (PNNL), and Vista Engineering Technologies, LLC, developed a safer, cost-efficient, remote PFP 3013 container surveillance system. This new surveillance system is a combination of two successfully deployed technologies: (1) a magnetically coupled pressure gauge developed by Vista Engineering and (2) a radio frequency (RF) tagging device developed by PNNL. This system provides continuous, 100% monitoring of critical parameters with the containers in place, as well as inventory controls. The 3013 container surveillance system consists of three main elements: (1) an internal magnetic pressure sensor package, (2) an instrument pod (external electronics package), and (3) a data acquisition storage and display computer. The surveillance system described in this paper has many benefits for PFP and DOE in terms of cost savings and reduced personnel exposure. In addition, continuous safety monitoring (i.e., internal container pressure and temperature) of every container is responsible nuclear material stewardship and fully meets and exceeds DOE's Integrated Surveillance Program requirements.

Lechelt, W. M.; Skorpik, J. R.; Silvers, K. L.; Szempruch, R. W.; Douglas, D. G.; Fein, K. O.

2002-02-26T23:59:59.000Z

320

Implications of Export/Import Reporting Requirements in the United States - International Atomic Energy Agency Safeguards Additional Protocol  

SciTech Connect (OSTI)

The United States has signed but not ratified the US/IAEA Safeguards Additional Protocol. If ratified, the Additional Protocol will require the US to report to the IAEA certain nuclear-related exports and imports to the IAEA. This document identifies and assesses the issues associated with the US making those reports. For example, some regulatory changes appear to be necessary. The document also attempts to predict the impact on the DOE Complex by assessing the historical flow of exports and imports that would be reportable if the Additional Protocol were in force.

Killinger, Mark H.; Benjamin, Eugene L.; McNair, Gary W.

2001-02-20T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Thermoelectric Generators 1. Thermoelectric generator  

E-Print Network [OSTI]

. Cold Hot I - -- - - - - -- Figure 1 Electron concentration in a thermoelectric material. #12;2 A large1 Thermoelectric Generators HoSung Lee 1. Thermoelectric generator 1.1 Basic Equations In 1821 on the direction of current and material [3]. This is called the Thomson effect (or Thomson heat). These three

Lee, Ho Sung

322

UNLV Nuclear Hydrogen Initiative  

SciTech Connect (OSTI)

Evaluation of the Crack growth rate (CGR) of Alloy 617 and Alloy 276 under constant K at ambient temperature has been completed. Creep deformation of Alloy 230 at different temperature range and load level has been completed and heat to heat variation has been noticed. Creep deformation study of Alloy 276 has been completed under an applied initial stress level of 10% of yield stress at 950şC. The grain size evaluation of the tested creep specimens of Alloy 276 has been completed.

Hechanova, Anthony E.; Allen Johnson; Brendan O'Toole; Mohamed Trabia; Per Peterson

2012-10-25T23:59:59.000Z

323

DOE Exascale Initiative  

Broader source: Energy.gov (indexed) [DOE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTSof Energy DOE ChallengeThese are the DOE Exascale Initiative

324

2025 Power Marketing Initiative  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert SouthwestTechnologies |November 2011 Mon, Next2025 Power Marketing Initiative The

325

Initiatives | The Ames Laboratory  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFunInfrared Land Surface Emissivity in the VicinitySrTiO3(100).Initiatives GRACE

326

7-GeV Advanced Photon Source Instrumentation Initiative conceptual design report  

SciTech Connect (OSTI)

In this APS Instrumentation Initiative, 2.5-m-long and 5-m-long insertion-device x-ray sources will be built on 9 straight sections of the APS storage ring, and an additional 9 bending-magnet sources will also be put in use. The front ends for these 18 x-ray sources will be built to contain and safeguard access to these bright x-ray beams. In addition, funds will be provided to build state-of-the-art insertion-device beamlines to meet scientific and technological research demands well into the next century. This new initiative will also include four user laboratory modules and a special laboratory designed to meet the x-ray imaging research needs of the users. The Conceptual Design Report (CDR) for the APS Instrumentation Initiative describes the scope of all the above technical and conventional construction and provides a detailed cost and schedule for these activities. According to these plans, this new initiative begins in FY 1994 and ends in FY 1998. The document also describes the preconstruction R D plans for the Instrumentation Initiative activities and provides the cost estimates for the required R D.

Not Available

1992-12-01T23:59:59.000Z

327

7-GeV Advanced Photon Source Instrumentation Initiative conceptual design report  

SciTech Connect (OSTI)

In this APS Instrumentation Initiative, 2.5-m-long and 5-m-long insertion-device x-ray sources will be built on 9 straight sections of the APS storage ring, and an additional 9 bending-magnet sources will also be put in use. The front ends for these 18 x-ray sources will be built to contain and safeguard access to these bright x-ray beams. In addition, funds will be provided to build state-of-the-art insertion-device beamlines to meet scientific and technological research demands well into the next century. This new initiative will also include four user laboratory modules and a special laboratory designed to meet the x-ray imaging research needs of the users. The Conceptual Design Report (CDR) for the APS Instrumentation Initiative describes the scope of all the above technical and conventional construction and provides a detailed cost and schedule for these activities. According to these plans, this new initiative begins in FY 1994 and ends in FY 1998. The document also describes the preconstruction R&D plans for the Instrumentation Initiative activities and provides the cost estimates for the required R&D.

Not Available

1992-12-01T23:59:59.000Z

328

Precision flyer initiator  

DOE Patents [OSTI]

A precision flyer initiator forms a substantially spherical detonation wave in a high explosive (HE) pellet. An explosive driver, such as a detonating cord, a wire bridge circuit or a small explosive, is detonated. A flyer material is sandwiched between the explosive driver and an end of a barrel that contains an inner channel. A projectile or ``flyer`` is sheared from the flyer material by the force of the explosive driver and projected through the inner channel. The flyer than strikes the HE pellet, which is supported above a second end of the barrel by a spacer ring. A gap or shock decoupling material delays the shock wave in the barrel from predetonating the HE pellet before the flyer. A spherical detonation wave is formed in the HE pellet. Thus, a shock wave traveling through the barrel fails to reach the HE pellet before the flyer strikes the HE pellet. The precision flyer initiator can be used in mining devices, well-drilling devices and anti-tank devices. 10 figs.

Frank, A.M.; Lee, R.S.

1998-05-26T23:59:59.000Z

329

Precision flyer initiator  

DOE Patents [OSTI]

A precision flyer initiator forms a substantially spherical detonation wave in a high explosive (HE) pellet. An explosive driver, such as a detonating cord, a wire bridge circuit or a small explosive, is detonated. A flyer material is sandwiched between the explosive driver and an end of a barrel that contains an inner channel. A projectile or "flyer" is sheared from the flyer material by the force of the explosive driver and projected through the inner channel. The flyer than strikes the HE pellet, which is supported above a second end of the barrel by a spacer ring. A gap or shock decoupling material delays the shock wave in the barrel from predetonating the HE pellet before the flyer. A spherical detonation wave is formed in the HE pellet. Thus, a shock wave traveling through the barrel fails to reach the HE pellet before the flyer strikes the HE pellet. The precision flyer initiator can be used in mining devices, well-drilling devices and anti-tank devices.

Frank, Alan M. (Livermore, CA); Lee, Ronald S. (Livermore, CA)

1998-01-01T23:59:59.000Z

330

Safeguards Verification Measurements using Laser Ablation, Absorbance Ratio Spectrometry in Gaseous Centrifuge Enrichment Plants  

SciTech Connect (OSTI)

Laser Ablation Absorbance Ratio Spectrometry (LAARS) is a new verification measurement technology under development at the US Department of Energy’s (DOE) Pacific Northwest National Laboratory (PNNL). LAARS uses three lasers to ablate and then measure the relative isotopic abundance of uranium compounds. An ablation laser is tightly focused on uranium-bearing solids producing a small plume containing uranium atoms. Two collinear wavelength-tuned spectrometry lasers transit through the plume and the absorbance of U-235 and U-238 isotopes are measured to determine U-235 enrichment. The measurement has high relative precision and detection limits approaching the femtogram range for uranium. It is independent of chemical form and degree of dilution with nuisance dust and other materials. High speed sample scanning and pinpoint characterization allow measurements on millions of particles/hour to detect and analyze the enrichment of trace uranium in samples. The spectrometer is assembled using commercially available components at comparatively low cost, and features a compact and low power design. Future designs can be engineered for reliable, autonomous deployment within an industrial plant environment. Two specific applications of the spectrometer are under development: 1) automated unattended aerosol sampling and analysis and 2) on-site small sample destructive assay measurement. The two applications propose game-changing technological advances in gaseous centrifuge enrichment plant (GCEP) safeguards verification. The aerosol measurement instrument, LAARS-environmental sampling (ES), collects aerosol particles from the plant environment in a purpose-built rotating drum impactor and then uses LAARS-ES to quickly scan the surface of the impactor to measure the enrichments of the captured particles. The current approach to plant misuse detection involves swipe sampling and offsite analysis. Though this approach is very robust it generally requires several months to obtain results from a given sample collection. The destructive assay instrument, LAARS-destructive assay (DA), uses a simple purpose-built fixture with a sampling planchet to collect adsorbed UF6 gas from a cylinder valve or from a process line tap or pigtail. A portable LAARS-DA instrument scans the microgram quantity of uranium collected on the planchet and the assay of the uranium is measured to ~0.15% relative precision. Currently, destructive assay samples for bias defect measurements are collected in small sample cylinders for offsite mass spectrometry measurement.

Anheier, Norman C.; Cannon, Bret D.; Qiao, Hong (Amy) [Amy; Phillips, Jon R.

2012-07-01T23:59:59.000Z

331

Waste Generated from LMR-AMTEC Reactor Concept  

SciTech Connect (OSTI)

The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from the packing materials (e.g. activated carbon in cold trap and purification units). The regulations and management of these wastes are summarized in this paper.

Hasan, Ahmed; Mohamed, Yasser, T.; Mohammaden, Tarek, F.

2003-02-25T23:59:59.000Z

332

Microwave generator  

DOE Patents [OSTI]

A microwave generator is provided for generating microwaves substantially from virtual cathode oscillation. Electrons are emitted from a cathode and accelerated to an anode which is spaced apart from the cathode. The anode has an annular slit there through effective to form the virtual cathode. The anode is at least one range thickness relative to electrons reflecting from the virtual cathode. A magnet is provided to produce an optimum magnetic field having the field strength effective to form an annular beam from the emitted electrons in substantial alignment with the annular anode slit. The magnetic field, however, does permit the reflected electrons to axially diverge from the annular beam. The reflected electrons are absorbed by the anode in returning to the real cathode, such that substantially no reflexing electrons occur. The resulting microwaves are produced with a single dominant mode and are substantially monochromatic relative to conventional virtual cathode microwave generators. 6 figs.

Kwan, T.J.T.; Snell, C.M.

1987-03-31T23:59:59.000Z

333

Instrumented Pipeline Initiative  

SciTech Connect (OSTI)

This report summarizes technical progress achieved during the cooperative agreement between Concurrent Technologies Corporation (CTC) and U.S. Department of Energy to address the need for a for low-cost monitoring and inspection sensor system as identified in the Department of Energy (DOE) National Gas Infrastructure Research & Development (R&D) Delivery Reliability Program Roadmap.. The Instrumented Pipeline Initiative (IPI) achieved the objective by researching technologies for the monitoring of pipeline delivery integrity, through a ubiquitous network of sensors and controllers to detect and diagnose incipient defects, leaks, and failures. This report is organized by tasks as detailed in the Statement of Project Objectives (SOPO). The sections all state the objective and approach before detailing results of work.

Thomas Piro; Michael Ream

2010-07-31T23:59:59.000Z

334

Safety and Security Interface Technology Initiative  

SciTech Connect (OSTI)

Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ‘tool box’ of information/successes. Specific Benefits. The expectation or end state resulting from the topical report and associated implementation plan includes: (1) A recommended process for handling the documentation of the security and safety disciplines, including an appropriate change control process and participation by all stakeholders. (2) A means to package security systems with sufficient information to help expedite the flow of that system through the process. In addition, a means to share successes among sites, to include information and safety basis to the extent such information is transportable. (3) Identification of key security systems and associated essential security elements being installed and an arrangement for the sites installing these systems to host an appropriate team to review a specific system and determine what information is exportable. (4) Identification of the security systems’ essential elements and appropriate controls required for testing of these essential elements in the facility. (5) The ability to help refine and improve an agreed to control set at the manufacture stage.

Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

2007-05-01T23:59:59.000Z

335

Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the U.S. Department of Energy. Quarter ending December 31, 1996  

SciTech Connect (OSTI)

The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the First Quarter of Fiscal Year 1997 (October through December, 1996). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in four areas: (1) safeguards technology; (2) safeguards and material accountability; (3) computer security--distributed systems; and (4) physical and personnel security support. The remainder of this report describes the activities in each of these four areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

Davis, G.; Mansur, D.L.; Ruhter, W.D.; Strauch, M.S.

1997-01-01T23:59:59.000Z

336

Lawrence Livermore National Laboratory Safeguards and Security quarterly progress report to the US Department of Energy: Quarter ending December 31, 1993  

SciTech Connect (OSTI)

The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the first quarter of fiscal year 1994 (October through December, 1993). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in five areas: (1) Safeguards Technology, (2) Safeguards and Decision Support, (3) Computer Security, (4) DOE Automated Physical Security, and (5) DOE Automated Visitor Access Control System. This report describes the activities in each of these five areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

Davis, G.; Mansur, D.L.; Ruhter, W.D.; Steele, E.; Strait, R.S.

1994-01-01T23:59:59.000Z

337

Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy: Quarter ending September 30, 1993  

SciTech Connect (OSTI)

The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the fourth quarter of Fiscal Year 1993 (July through September, 1993). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise. These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in five areas: Safeguards Technology, Safeguard System Studies, Computer Security, DOE Automated Physical Security and DOE Automated Visitor Access Control System. The remainder of this report describes the activities in each of these five areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.

Ruhter, W.D.; Strait, R.S.; Mansur, D.L.; Davis, G.

1993-10-01T23:59:59.000Z

338

ORNL Sustainable Campus Initiative  

SciTech Connect (OSTI)

The research conducted at Oak Ridge National Laboratory (ORNL) spans many disciplines and has the potential for far-reaching impact in many areas of everyday life. ORNL researchers and operations staff work on projects in areas as diverse as nuclear power generation, transportation, materials science, computing, and building technologies. As the U.S. Department of Energy s (DOE) largest science and energy research facility, ORNL seeks to establish partnerships with industry in the development of innovative new technologies. The primary focus of this current research deals with developing technologies which improve or maintain the quality of life for humans while reducing the overall impact on the environment. In its interactions with industry, ORNL serves as both a facility for sustainable research, as well as a representative of DOE to the private sector. For these reasons it is important that the everyday operations of the Laboratory reflect a dedication to the concepts of stewardship and sustainability.

Halford, Christopher K [ORNL] [ORNL

2012-01-01T23:59:59.000Z

339

MONTANA PALLADIUM RESEARCH INITIATIVE  

SciTech Connect (OSTI)

Project Objective: The overarching objective of the Montana Palladium Research Initiative is to perform scientific research on the properties and uses of palladium in the context of the U.S. Department of Energy'Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?s Hydrogen, Fuel Cells and Infrastructure Technologies Program. The purpose of the research will be to explore possible palladium as an alternative to platinum in hydrogen-economy applications. To achieve this objective, the Initiatives activities will focus on several cutting-edge research approaches across a range of disciplines, including metallurgy, biomimetics, instrumentation development, and systems analysis. Background: Platinum-group elements (PGEs) play significant roles in processing hydrogen, an element that shows high potential to address this need in the U.S. and the world for inexpensive, reliable, clean energy. Platinum, however, is a very expensive component of current and planned systems, so less-expensive alternatives that have similar physical properties are being sought. To this end, several tasks have been defined under the rubric of the Montana Palladium Research Iniative. This broad swath of activities will allow progress on several fronts. The membrane-related activities of Task 1 employs state-of-the-art and leading-edge technologies to develop new, ceramic-substrate metallic membranes for the production of high-purity hydrogen, and develop techniques for the production of thin, defect-free platinum group element catalytic membranes for energy production and pollution control. The biomimetic work in Task 2 explores the use of substrate-attached hydrogen-producing enzymes and the encapsulation of palladium in virion-based protein coats to determine their utility for distributed hydrogen production. Task 3 work involves developing laser-induced breakdown spectroscopy (LIBS) as a real-time, in situ diagnostic technique to characterize PGEs nanoparticles for process monitoring and control. The systems engineering work in task 4 will determine how fuel cells Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?Ă?Â?taken as systems behave over periods of time that should show how their reformers and other subsystems deteriorate with time.

Peters, John; McCloskey, Jay; Douglas, Trevor; Young, Mark; Snyder, Stuart; Gurney, Brian

2012-05-09T23:59:59.000Z

340

Initial Cladding Condition  

SciTech Connect (OSTI)

The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is received at the Yucca Mountain Project (YMP) site. Most commercial nuclear fuel is encased in Zircaloy cladding. This analysis is developed to describe cladding degradation from the expected failure modes. This includes reactor operation impacts including incipient failures, potential degradation after reactor operation during spent fuel storage in pool and dry storage and impacts due to transportation. Degradation modes include cladding creep, and delayed hydride cracking during dry storage and transportation. Mechanical stresses from fuel handling and transportation vibrations are also included. This Analysis and Model Report (AMR) does not address any potential damage to assemblies that might occur at the YMP surface facilities. Ranges and uncertainties have been defined. This analysis will be the initial boundary condition for the analysis of cladding degradation inside the repository. In accordance with AP-2.13Q, ''Technical Product Development Planning'', a work plan (CRWMS M&O 2000c) was developed, issued, and utilized in the preparation of this document. There are constraints, caveats and limitations to this analysis. This cladding degradation analysis is based on commercial Pressurized Water Reactor (PWR) fuel with Zircaloy cladding but is applicable to Boiling Water Reactor (BWR) fuel. Reactor operating experience for both PWRs and BWRs is used to establish fuel reliability from reactor operation. It is limited to fuel exposed to normal operation and anticipated operational occurrences (i.e. events which are anticipated to occur within a reactor lifetime), and not to fuel that has been exposed to severe accidents. Fuel burnup projections have been limited to the current commercial reactor licensing environment with restrictions on fuel enrichment, oxide coating thickness and rod plenum pressures. The information provided in this analysis will be used in evaluating the post-closure performance of the Monitored Geologic Repository (MGR) in relation to waste form degradation.

E. Siegmann

2000-08-22T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Education and Training in Radiochemistry – The NAMP Initiative  

SciTech Connect (OSTI)

In 2009, the nuclear industry employed approximately 120,000 people. Nearly 38 percent of the nuclear industry force will be eligible to retire within the next five years. To maintain the current work force, the industry will need to hire approximately 25,000 more workers by 2015. Given that the current radiochemistry workforce is approaching the age for retirement and that a limited number of US universities provide experience with radiochemistry, the United States is faced with a growing demand for the education and training of scientists in the radiochemistry arena. Furthermore, it is critical that the US maintains global leadership in the next generation of safe nuclear energy technology from both a national security and environmental perspective. This will require a robust program that focuses entirely on educating and training the next generation of radiochemists in subjects such as 1- radioanalysis of actinides and radioelements not only in the environment but in medium pertinent to the back end of the nuclear fuel cycle, 2- speciation of radionuclides, 3- detection methods, 4- safeguards etc… Therefore, the National Analytical Management Program (NAMP) has organized a subcommittee focusing on training and education in radiochemistry. Through the efforts of this subcommittee, NAMP has established collaborative associations to foster the exchange of scientific and technical information with professors in radiochemistry programs at different universities. This paper will present our accomplishments and the development of a curriculum for an intermediate radiochemistry course in cooperation with the EPA. These short (2-hour) webinar presentations on specific radiochemistry topics have been developed and will be presented. The webinars are recorded and will become a library or collection of information for on-line access from the NAMP website.

Patricia Paviet-Hartmann; Mansour Akbarzadeh

2012-08-01T23:59:59.000Z

342

Submersible Generator for Marine Hydrokinetics  

SciTech Connect (OSTI)

A submersible generator was designed as a distinct and critical subassembly of marine hydrokinetics systems, specifically tidal and stream energy conversion. The generator is designed to work with both vertical and horizontal axis turbines. The final product is a high-pole-count, radial-flux, permanent magnet, rim mounted generator, initially rated at twenty kilowatts in a two-meter-per-second flow, and designed to leverage established and simple manufacturing processes. The generator was designed to work with a 3 meter by 7 meter Gorlov Helical Turbine or a marine hydrokinetic version of the FloDesign wind turbine. The team consisted of experienced motor/generator design engineers with cooperation from major US component suppliers (magnetics, coil winding and electrical steel laminations). Support for this effort was provided by Lucid Energy Technologies and FloDesign, Inc. The following tasks were completed: � Identified the conditions and requirements for MHK generators. � Defined a methodology for sizing and rating MHK systems. � Selected an MHK generator topology and form factor. � Completed electromechanical design of submersible generator capable of coupling to multiple turbine styles. � Investigated MHK generator manufacturing requirements. � Reviewed cost implications and financial viability. � Completed final reporting and deliverables

Robert S. Cinq-Mars; Timothy Burke; Dr. James Irish; Brian Gustafson; Dr. James Kirtley; Dr. Aiman Alawa

2011-09-01T23:59:59.000Z

343

Generation Technologies  

E-Print Network [OSTI]

Many local governments are using green power in their facilities and providing assistance to local businesses and residents to do the same. Green power is a subset of renewable energy that is produced with no GHG emissions, typically from solar, wind, geothermal, biogas, biomass, or low-impact small hydroelectric sources, includes three types of products: utility products (i.e., green power purchased from the utility through the electricity grid), renewable energy certificates (RECs), and on-site generation. Opportunities to purchase these products are increasing significantly, with annual green power market growth rates

Green Power

2005-01-01T23:59:59.000Z

344

Florida Hydrogen Initiative  

SciTech Connect (OSTI)

The Florida Hydrogen Initiative (FHI) was a research, development and demonstration hydrogen and fuel cell program. The FHI program objectives were to develop Florida?s hydrogen and fuel cell infrastructure and to assist DOE in its hydrogen and fuel cell activities The FHI program funded 12 RD&D projects as follows: Hydrogen Refueling Infrastructure and Rental Car Strategies -- L. Lines, Rollins College This project analyzes strategies for Florida's early stage adaptation of hydrogen-powered public transportation. In particular, the report investigates urban and statewide network of refueling stations and the feasibility of establishing a hydrogen rental-car fleet based in Orlando. Methanol Fuel Cell Vehicle Charging Station at Florida Atlantic University ? M. Fuchs, EnerFuel, Inc. The project objectives were to design, and demonstrate a 10 kWnet proton exchange membrane fuel cell stationary power plant operating on methanol, to achieve an electrical energy efficiency of 32% and to demonstrate transient response time of less than 3 milliseconds. Assessment of Public Understanding of the Hydrogen Economy Through Science Center Exhibits, J. Newman, Orlando Science Center The project objective was to design and build an interactive Science Center exhibit called: ?H2Now: the Great Hydrogen Xchange?. On-site Reformation of Diesel Fuel for Hydrogen Fueling Station Applications ? A. Raissi, Florida Solar Energy Center This project developed an on-demand forecourt hydrogen production technology by catalytically converting high-sulfur hydrocarbon fuels to an essentially sulfur-free gas. The removal of sulfur from reformate is critical since most catalysts used for the steam reformation have limited sulfur tolerance. Chemochromic Hydrogen Leak Detectors for Safety Monitoring ? N. Mohajeri and N. Muradov, Florida Solar Energy Center This project developed and demonstrated a cost-effective and highly selective chemochromic (visual) hydrogen leak detector for safety monitoring at any facility engaged in transport, handling and use of hydrogen. Development of High Efficiency Low Cost Electrocatalysts for Hydrogen Production and PEM Fuel Cell Applications ? M. Rodgers, Florida Solar Energy Center The objective of this project was to decrease platinum usage in fuel cells by conducting experiments to improve catalyst activity while lowering platinum loading through pulse electrodeposition. Optimum values of several variables during electrodeposition were selected to achieve the highest electrode performance, which was related to catalyst morphology. Understanding Mechanical and Chemical Durability of Fuel Cell Membrane Electrode Assemblies ? D. Slattery, Florida Solar Energy Center The objective of this project was to increase the knowledge base of the degradation mechanisms for membranes used in proton exchange membrane fuel cells. The results show the addition of ceria (cerium oxide) has given durability improvements by reducing fluoride emissions by an order of magnitude during an accelerated durability test. Production of Low-Cost Hydrogen from Biowaste (HyBrTec?) ? R. Parker, SRT Group, Inc., Miami, FL This project developed a hydrogen bromide (HyBrTec?) process which produces hydrogen bromide from wet-cellulosic waste and co-produces carbon dioxide. Eelectrolysis dissociates hydrogen bromide producing recyclable bromine and hydrogen. A demonstration reactor and electrolysis vessel was designed, built and operated. Development of a Low-Cost and High-Efficiency 500 W Portable PEMFC System ? J. Zheng, Florida State University, H. Chen, Bing Energy, Inc. The objectives of this project were to develop a new catalyst structures comprised of highly conductive buckypaper and Pt catalyst nanoparticles coated on its surface and to demonstrate fuel cell efficiency improvement and durability and cell cost reductions in the buckypaper based electrodes. Development of an Interdisciplinary Hydrogen and Fuel Cell Technology Academic Program ? J. Politano, Florida Institute of Technology, Melbourne, FL This project developed a hydrogen and fuel cel

Block, David L

2013-06-30T23:59:59.000Z

345

GASIFICATION FOR DISTRIBUTED GENERATION  

SciTech Connect (OSTI)

A recent emphasis in gasification technology development has been directed toward reduced-scale gasifier systems for distributed generation at remote sites. The domestic distributed power generation market over the next decade is expected to be 5-6 gigawatts per year. The global increase is expected at 20 gigawatts over the next decade. The economics of gasification for distributed power generation are significantly improved when fuel transport is minimized. Until recently, gasification technology has been synonymous with coal conversion. Presently, however, interest centers on providing clean-burning fuel to remote sites that are not necessarily near coal supplies but have sufficient alternative carbonaceous material to feed a small gasifier. Gasifiers up to 50 MW are of current interest, with emphasis on those of 5-MW generating capacity. Internal combustion engines offer a more robust system for utilizing the fuel gas, while fuel cells and microturbines offer higher electric conversion efficiencies. The initial focus of this multiyear effort was on internal combustion engines and microturbines as more realistic near-term options for distributed generation. In this project, we studied emerging gasification technologies that can provide gas from regionally available feedstock as fuel to power generators under 30 MW in a distributed generation setting. Larger-scale gasification, primarily coal-fed, has been used commercially for more than 50 years to produce clean synthesis gas for the refining, chemical, and power industries. Commercial-scale gasification activities are under way at 113 sites in 22 countries in North and South America, Europe, Asia, Africa, and Australia, according to the Gasification Technologies Council. Gasification studies were carried out on alfalfa, black liquor (a high-sodium waste from the pulp industry), cow manure, and willow on the laboratory scale and on alfalfa, black liquor, and willow on the bench scale. Initial parametric tests evaluated through reactivity and product composition were carried out on thermogravimetric analysis (TGA) equipment. These tests were evaluated and then followed by bench-scale studies at 1123 K using an integrated bench-scale fluidized-bed gasifier (IBG) which can be operated in the semicontinuous batch mode. Products from tests were solid (ash), liquid (tar), and gas. Tar was separated on an open chromatographic column. Analysis of the gas product was carried out using on-line Fourier transform infrared spectroscopy (FT-IR). For selected tests, gas was collected periodically and analyzed using a refinery gas analyzer GC (gas chromatograph). The solid product was not extensively analyzed. This report is a part of a search into emerging gasification technologies that can provide power under 30 MW in a distributed generation setting. Larger-scale gasification has been used commercially for more than 50 years to produce clean synthesis gas for the refining, chemical, and power industries, and it is probable that scaled-down applications for use in remote areas will become viable. The appendix to this report contains a list, description, and sources of currently available gasification technologies that could be or are being commercially applied for distributed generation. This list was gathered from current sources and provides information about the supplier, the relative size range, and the status of the technology.

Ronald C. Timpe; Michael D. Mann; Darren D. Schmidt

2000-05-01T23:59:59.000Z

346

Energy Efficient State Building Initiative  

Broader source: Energy.gov [DOE]

In June 2008, Governor Mitch Daniels issued an executive order establishing an energy efficient state buildings initiative. The order requires the Indiana Department of Administration (DOA) to...

347

Sandia National Laboratories: Advanced Manufacturing Initiative  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwardsSafeguardsEngineersSandia/NewAdvanced Light

348

Sandia National Laboratories: Advanced Manufacturing Innovation Initiative  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwardsSafeguardsEngineersSandia/NewAdvanced

349

Systems Engineering Advancement Research Initiative  

E-Print Network [OSTI]

Systems Engineering Advancement Research Initiative RESEARCH PORTFOLIO Fall 2008 About SEAri http://seari.mit.edu The Systems Engineering Advancement Research Initiative brings together a set of sponsored research projects and a consortium of systems engineering leaders from industry, government, and academia. SEAri is positioned within

de Weck, Olivier L.

350

Thermoelectric generator  

SciTech Connect (OSTI)

A thermoelectric generator unit is described comprising: a hot side heat exchanger including a plate having extruded retention posts projecting from one surface of the plate, and fins adapted for contact with a heating source. The fins are positioned between two of the retention posts. Retention rods are inserted between the retention posts and the base of the fins to retain the fin in thermal contact with the plate surface upon insertion of the retention rod between the engaging surface of the post and the corresponding fin. Thermoelectric semi-conductor modules are in thermal contact with the opposite side of the hot side heat exchanger plate from the contact with the fins. The modules are arranged in a grid pattern so that heat flow is directed into each of the modules from the hot side heat exchanger. The modules are connected electrically so as to combine their electrical output; and a cold side heat exchanger is in thermal contact with the modules acting as a heat sink on the opposite side of the module from the hot side heat exchanger plate so as to produce a thermal gradient across the modules.

Shakun, W.; Bearden, J.H.; Henderson, D.R.

1988-03-29T23:59:59.000Z

351

Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy, quarter ending March 31, 1993  

SciTech Connect (OSTI)

This quarterly report discusses activities in the Safeguards Technology Program (STP) which is a program in LLNL`s Nuclear Chemistry Division that develop advanced, nondestructive-analysis (NDA) technology for measurement of special nuclear materials. The work focuses on R&D relating to x{minus} and gamma-ray spectrometry techniques and to the development of computer codes for interpreting the spectral data obtained by these techniques.

Ruhter, W.D.; Strait, R.S.; Mansur, D.L.; Davis, G.

1993-04-01T23:59:59.000Z

352

Thin-film optical initiator  

DOE Patents [OSTI]

A thin-film optical initiator having an inert, transparent substrate, a reactive thin film, which can be either an explosive or a pyrotechnic, and a reflective thin film. The resultant thin-film optical initiator system also comprises a fiber-optic cable connected to a low-energy laser source, an output charge, and an initiator housing. The reactive thin film, which may contain very thin embedded layers or be a co-deposit of a light-absorbing material such as carbon, absorbs the incident laser light, is volumetrically heated, and explodes against the output charge, imparting about 5 to 20 times more energy than in the incident laser pulse.

Erickson, Kenneth L. (Albuquerque, NM)

2001-01-01T23:59:59.000Z

353

Introduction Minimal generation  

E-Print Network [OSTI]

Introduction Minimal generation Random generation Minimal and probabilistic generation of finite generation of finite groups #12;Introduction Minimal generation Random generation Some motivation Let x1 random elements of G = x1, . . . , xk . (G is the group generated by x1, . . . , xk : all possible

St Andrews, University of

354

Initial measurements of BN-350 spent fuel in dry storage casks using the dual slab verification detonator  

SciTech Connect (OSTI)

The Dual Slab Verification Detector (DSVD) has been developed, built, and characterized by Los Alamos National Laboratory in cooperation with the International Atomic Energy Agency (IAEA) as part of the dry storage safeguards system for the spent fuel from the BN-350 fast reactor. The detector consists of two rows of 3He tubes embedded in a slab of polyethylene which has been designed to be placed on the outer surface of the dry storage cask. By performing DSVD measurements at several different locations around the outer surface of the DUC, a signature 'fingerprint' can be established for each DUC based on the neutron flux emanating from inside the dry storage cask. The neutron fingerprint for each individual DUC will be dependent upon the spatial distribution of nuclear material within the cask, thus making it sensitive to the removal of a certain amount of material from the cask. An initial set of DSVD measurements have been performed on the first set of dry storage casks that have been loaded with canisters of spent fuel and moved onto the dry storage pad to both establish an initial fingerprint for these casks as well as to quantify systematic uncertainties associated with these measurements. The results from these measurements will be presented and compared with the expected results that were determined based on MCNPX simulations of the dry storage facility. The ability to safeguard spent nuclear fuel is strongly dependent on the technical capabilities of establishing and maintaining continuity of knowledge (COK) of the spent fuel as it is released from the reactor core and either reprocessed or packaged and stored at a storage facility. While the maintenance of COK is often done using continuous containment and surveillance (C/S) on the spent fuel, it is important that the measurement capabilities exist to re-establish the COK in the event of a significant gap in the continuous CIS by performing measurements that independently confirm the presence and content of Plutonium (Pu) in the spent fuel. The types of non-destructive assay (NDA) measurements that can be performed on the spent fuel are strongly dependent on the type of spent fuel that is being safeguarded as well as the location in which the spent fuel is being stored. The BN-350 Spent Fuel Disposition Project was initiated to improve the safeguards and security of the spent nuclear fuel from the BN-350 fast-breeder reactor and was developed cooperatively to meet the requirements of the International Atomic Energy Agency (IAEA) as well as the terms of the 1993 CTR and MPC&A Implementing Agreements. The unique characteristics of fuel from the BN-350 fast-breeder reactor have allowed for the development of an integrated safeguards measurement program to inventory, monitor, and if necessary, re-verify Pu content of the spent fuel throughout the lifetime of the project. This approach includes the development of a safeguards measurement program to establish and maintain the COK on the spent fuel during the repackaging and eventual relocation of the spent-fuel assemblies to a long-term storage site. As part of the safeguards measurement program, the Pu content of every spent-fuel assembly from the BN-350 reactor was directly measured and characterized while the spent-fuel assemblies were being stored in the spent-fuel pond at the BN-350 facility using the Spent Fuel Coincidence Counter (SFCC). Upon completion of the initial inventory of the Pu content of the individual spent-fuel assemblies, the assemblies were repackaged into welded steel canisters that were filled with inert argon gas and held either four or six individual spent-fuel assemblies depending on the type of assembly that was being packaged. This repackaging of the spent-fuel assemblies was performed in order to improve the stability of the spent-fuel assemblies for long-term storage and increase the proliferation resistance of the spent fuel. To maintain the capability of verifying the presence of the spent-fuel assemblies inside the welded steel canisters, measurements were performed on the canis

Santi, Peter Angelo [Los Alamos National Laboratory; Browne, Michael C [Los Alamos National Laboratory; Freeman, Corey R [Los Alamos National Laboratory; Parker, Robert F [Los Alamos National Laboratory; Williams, Richard B [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

355

Initial  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFunInfrared Land Surface Emissivity in the Vicinity ofTorecrystallization

356

Energy Efficient Schools Initiative- Grants  

Broader source: Energy.gov [DOE]

The Energy Efficient Schools Initiative was created in May 2008 to provide grants and [http://www.dsireusa.org/incentives/incentive.cfm?Incentive_Code=TN57F&re... loans] to Tennessee school...

357

Jet initiation of PBX 9502  

SciTech Connect (OSTI)

This report details the progress of an effort to determine the quantitative aspects of the initiation of PBX 9502 (95% TATB, 5% Kel-F 800) by copper jets. The particular jet used was that produced by the LAW warhead (66-mm diameter, 42/sup 0/ angle cone, copper-lined, conical shaped charge). Fifteen experiments, in various configurations, have been fired to define the essential parameters for quantitatively measuring the jet performance and initiation of bare PBX 9502. 7 refs., 8 figs.

McAfee, J.M.

1987-07-01T23:59:59.000Z

358

Endstates Initiative | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in Review: TopEnergyIDIQ ContractEndstates Initiative Endstates Initiative Endstates

359

Shock Initiation of Energetic Materials at Different Initial Temperatures  

SciTech Connect (OSTI)

Shock initiation is one of the most important properties of energetic materials, which must transition to detonation exactly as intended when intentionally shocked and not detonate when accidentally shocked. The development of manganin pressure gauges that are placed inside the explosive charge and record the buildup of pressure upon shock impact has greatly increased the knowledge of these reactive flows. This experimental data, together with similar data from electromagnetic particle velocity gauges, has allowed us to formulate the Ignition and Growth model of shock initiation and detonation in hydrodynamic computer codes for predictions of shock initiation scenarios that cannot be tested experimentally. An important problem in shock initiation of solid explosives is the change in sensitivity that occurs upon heating (or cooling). Experimental manganin pressure gauge records and the corresponding Ignition and Growth model calculations are presented for two solid explosives, LX-17 (92.5 % triaminotrinitrobenzene (TATB) with 7.5 % Kel-F binder) and LX-04 (85 % octahydro-1,3,5,7-tetranitro-1,3,5,7-tetrazine (HMX) with 15 % Viton binder) at several initial temperatures.

Urtiew, P A; Tarver, C M

2005-01-14T23:59:59.000Z

360

IST EPFL Joint doctoral Initiative Thesis Topic Proposal Form  

E-Print Network [OSTI]

IST ­ EPFL Joint doctoral Initiative Thesis Topic Proposal Form TITLE: Blocking probability. Keywords: Blocking probability; Dam safety; Discharge capacity; Driftwood; Spillway. SUPERVISORS IST: Jorge block and thereby reduce the open flow area for water passage. The blocking generated by woody debris

Instituto de Sistemas e Robotica

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

IST EPFL Joint doctoral Initiative Thesis Topic Proposal Form  

E-Print Network [OSTI]

IST ­ EPFL Joint doctoral Initiative Thesis Topic Proposal Form TITLE: Pump-turbines with variable of the use of turbines and pump-turbines with variable speed drives in pressurized water pipe systems (e speed drives for electricity generation in pressurised pipe systems FOCUS AREA: Environmental Hydraulics

Instituto de Sistemas e Robotica

362

Understanding and Managing Generation Y  

E-Print Network [OSTI]

There are four generations in the workplace today; they consist of the Silent Generation, Baby Boom Generation, Generation X, and Generation Y. Generation Y, being the newest generation, is the least understood generation although marketers...

Wallace, Kevin

2007-12-14T23:59:59.000Z

363

AVAILABLE ONLINE AT: INITIATED BY:  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartmentStewardshipAdministration helps INITIATED BY: INITIATED BY:

364

AVAILABLE ONLINE AT: INITIATED BY:  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartmentStewardshipAdministration helps INITIATED BY: INITIATED BY:Project

365

AVAILABLE ONLINE AT: INITIATED BY:  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartmentStewardshipAdministration helps INITIATED BY: INITIATED

366

Thermoelectric generator apparatus and operation method  

SciTech Connect (OSTI)

A method of operating a thermoelectric generator includes: cyclically producing increasing then decreasing temperature differences in the thermoelectric material of the generator; and generating a cyclically increasing then decreasing electrical generator output signal, in response to such temperature differences, to transmit electrical power generated by the generator from the generator. Part of the thermoelectric material reaches temperatures substantially above the melting temperature of the material. The thermoelectric material of the generator forms a part of a closed electrical loop about a transformer core so that the inductor voltage for the loop serves as the output signal of the generator. A thermoelectric generator, which can be driven by the described method of operation, incorporates fins into a thermopile to conduct heat toward or away from the alternating spaces between adjacent layers of different types of thermoelectric material. The fins extend from between adjacent layers, so that they can also conduct electrical current between such layers, perpendicularly to the direction of stacking of the layers. The exhaust from an internal combustion engine can be employed to drive the thermoelectric generator, and, also, to act as a driver for a thermoelectric generator in accordance with the method of operation initially described.

Lowther, F.E.

1984-07-31T23:59:59.000Z

367

NILE BASIN INITIATIVE Claire Stodola  

E-Print Network [OSTI]

· Climate Change #12;Upstream states · Low water needs Downstream states · High water needs #12;Historical #12;Research Question How has the Nile Basin Initiative influenced the riparian states' management states 1959 ­ Still only BILATERAL 1960s to 1990s - Increasing frustration by upstream states #12;What

New Hampshire, University of

368

Managing Critical Management Improvement Initiatives  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Provides requirements and responsibilities for planning, executing and assessing critical management improvement initiatives within DOE. DOE N 251.59, dated 9/27/2004, extends this Notice until 10/01/2005. Archived 11-8-10. Does not cancel other directives.

2003-10-01T23:59:59.000Z

369

Energy Initiative Campus Steering Committee  

E-Print Network [OSTI]

1003 Kemper Hall Billy Sanders, Chief Executive Officer for the UC Davis Energy Institute provided* Energy Initiative Campus Steering Committee Meeting Minutes March 9, 2007, 3:00 p.m., in room building would need. Some examples included solar heating and cooling units, energy efficient biomass

Islam, M. Saif

370

Zentrum fr Nutzfahrzeugtechnologie Initial situation  

E-Print Network [OSTI]

with a vehicle model in the MKS software for the study of vehicle dynamic behavior. Schindler03_2012_03 Zentrum to calculate the tyre dynamic behavior when travelling through the soil surface. It can be fur- ther integratedZentrum fĂĽr Nutzfahrzeugtechnologie Initial situation: The study on the trafficability

Berns, Karsten

371

Innovation Program Student Initiated Project  

E-Print Network [OSTI]

Innovation Program Student Initiated Project Proposal Guidelines Eligibility The team must include be willing to present the project (regardless of its degree of success) at a showcase event Proposal Guideline Proposal limited to 1 page, 1" margins, and an 11 point or larger font Project title Team

Bertini, Robert L.

372

USDA Rural Community Development Initiative  

Broader source: Energy.gov [DOE]

The U.S. Department of Agriculture (USDA) Rural Housing Service is seeking applications for Rural Community Development Initiative (RCDI) grants that will be awarded to organizations to provide criticial financial and technical assistance to recipients to develop and strengthen their capacity to carry out housing, community facilities, and community and economic development projects.

373

Initiation disruptor systems and methods of initiation disruption  

DOE Patents [OSTI]

A system that may be used as an initiation disruption system (IDS) according to one embodiment includes an explosive charge; a plurality of particles in a layer at least partially surrounding the explosive charge; and a fire suppressant adjacent the plurality of particles. A method for disabling an object according to one embodiment includes placing the system as recited above near an object; and causing the explosive charge to initiate, thereby applying mechanical loading to the object such that the object becomes disabled. Additional systems and methods are also presented. A device according to another embodiment includes a plurality of particles bound by a binder thereby defining a sidewall having an interior for receiving an explosive; and a fire suppressant adjacent the plurality of particles and binder. Additional systems and methods are also presented.

Baum, Dennis W

2014-09-23T23:59:59.000Z

374

Feasibility Study on the Use of On-line Multivariate Statistical Process Control for Safeguards Applications in Natural Uranium Conversion Plants  

SciTech Connect (OSTI)

The objective of this work was to determine the feasibility of using on-line multivariate statistical process control (MSPC) for safeguards applications in natural uranium conversion plants. Multivariate statistical process control is commonly used throughout industry for the detection of faults. For safeguards applications in uranium conversion plants, faults could include the diversion of intermediate products such as uranium dioxide, uranium tetrafluoride, and uranium hexafluoride. This study was limited to a 100 metric ton of uranium (MTU) per year natural uranium conversion plant (NUCP) using the wet solvent extraction method for the purification of uranium ore concentrate. A key component in the multivariate statistical methodology is the Principal Component Analysis (PCA) approach for the analysis of data, development of the base case model, and evaluation of future operations. The PCA approach was implemented through the use of singular value decomposition of the data matrix where the data matrix represents normal operation of the plant. Component mole balances were used to model each of the process units in the NUCP. However, this approach could be applied to any data set. The monitoring framework developed in this research could be used to determine whether or not a diversion of material has occurred at an NUCP as part of an International Atomic Energy Agency (IAEA) safeguards system. This approach can be used to identify the key monitoring locations, as well as locations where monitoring is unimportant. Detection limits at the key monitoring locations can also be established using this technique. Several faulty scenarios were developed to test the monitoring framework after the base case or normal operating conditions of the PCA model were established. In all of the scenarios, the monitoring framework was able to detect the fault. Overall this study was successful at meeting the stated objective.

Ladd-Lively, Jennifer L [ORNL] [ORNL

2014-01-01T23:59:59.000Z

375

A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants  

SciTech Connect (OSTI)

This report describes an engineering-scale, mock UF6 feed and withdrawal (F&W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F&W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F&W system description. Continuous monitoring components on the mock F&W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF{sub 6} F&W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF{sub 6}. The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under plant operating conditions. The ultimate use of technologies tested on the engineering-scale test bed is to work with safeguards agencies to install them in operating plants (e.g., enrichment and fuel processing plants), thereby promoting new safeguards measures with minimal impact to operating plants. In addition, this system is useful in identifying features for new plants that can be incorporated as part of 'safeguards by design,' in which load cells and other monitoring technologies are specified to provide outputs for automated monitoring and inspector evaluation.

Krichinsky, Alan M [ORNL; Bates, Bruce E [ORNL; Chesser, Joel B [ORNL; Koo, Sinsze [ORNL; Whitaker, J Michael [ORNL

2009-12-01T23:59:59.000Z

376

Boston Architectural College Urban Sustainability Initiative  

SciTech Connect (OSTI)

The Boston Architectural College's Urban Sustainability initiative is a demonstration project as defined by the National Energy Technology Laboratory. BAC's proposed project with the U.S. Department of Energy - NETL, is a large part of that overall initiative. The BAC's Urban Sustainability Initiative is a multi-part project with several important goals and objectives that will have a significant impact on the surrounding neighborhood including: energy conservation, reduction of storm water runoff, generation of power through alternative energy sources, elimination/reduction of BAC carbon footprint, and to create a vehicle for ongoing public outreach and education. Education and outreach opportunities will serve to add to the already comprehensive Sustainability Design courses offered at BAC relative to energy savings, performance and conservation in building design. At the finish of these essential capital projects there will be technical materials created for the education of the design, sustainability, engineering, community development and historic preservation communities, to inform a new generation of environmentally-minded designers and practitioners, the city of Boston and the general public. The purpose of the initiative, through our green renovations program, is to develop our green alley projects and energy saving renovations to the BAC physical plant, to serve as a working model for energy efficient design in enclosed 19th century and 20th century urban sites and as an educational laboratory for teaching ecological and sustainable technologies to students and the public while creating jobs. The scope of our project as it relates to the BAC and the U.S. Department of Energy- NETL combined efforts includes: Task I of the project is Phase II (Green Alley). Task I encompasses various renovation activities that will demonstrate the effectiveness of permeable paving and ground water recharge systems. It will aid in the reduction of storm water runoff into the Charles River Basin in one of its most significantly polluted sections and, will provide a green renovation mechanism for the redirected storm water of a public alley way. This activity is designed to improve the quality of water recharging the ground water and protecting the vulnerable wood pilings under many of the historic masonry buildings in Boston's Back Bay. Sustainable design research and system monitoring opportunities will also be incorporated, providing ongoing tools for public outreach and education through innovative signage and "virtual tour" technology. The monitoring will include a "building performance dash board" that reflects real time operating conditions and improvements in environmental and economic performance to be prominently displayed on the face of our 320 Newbury Street building (approximately 1.5 million people walk by annually). The project site and demonstration area is located at the rear of 951 Boylston Street, Boston, MA 02115 and the parking area adjacent to Public Alley #444 in Boston's historic Back Bay. Task II of the project is Geothermal Solution. This task involves the installation of approximately seven Geothermal wells which will tap into the earth's constant underground temperatures to provide air-conditioning and heating for BAC facilities. The environmentally friendly geothermal system uses no fossil fuel, produces no emissions and runs silently, providing a sustainable model for commercial and residential buildings throughout Boston. Ultimately the combination of this project and other projects will assist in making the BAC "carbon-neutral", and could generate enough additional energy to provide free power to the Engine 33 and Ladder 15 Firehouse located at 941 Boylston Street. The project is located at the rear of 951 Boylston Street, Boston, MA 02115 and the parking area adjacent to Public Alley #444 in Boston's historic Back Bay. Task III of the project is the Sustainability Design Curriculum at the BAC. The BAC is the nation’s largest independent, multi-disciplinary college of spatial design, and a leader in

Byers, Arthur C.

2013-07-31T23:59:59.000Z

377

Cornell's Urban Sustainability Initiatives ACSF Lunch Summary  

E-Print Network [OSTI]

Sustainability Initiatives lunch. After introductions of participants, Josh Cerra (Landscape Architecture) gave sustainability initiatives conducted in cooperation with Landscape Architecture in the ethnically diverseCornell's Urban Sustainability Initiatives ACSF Lunch Summary Compiled by Marianne Krasny (NTRES

Angenent, Lars T.

378

California Solar Initiative California Public Utilities Commission  

E-Print Network [OSTI]

..................................................................................... 30 5.8 California Solar Initiative Increases Statewide GridInstalled Capacity by 40 Percent since California Solar Initiative California Public Utilities Commission Staff Progress Report July 2008 #12;California Solar Initiative, CPUC Staff Progress Report, July 2008

379

Green Button Initiative Growing | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Initiative Growing Green Button Initiative Growing May 17, 2013 - 1:17pm Addthis The Green Button initiative, which is the common-sense idea that electricity customers should...

380

California Solar Initiative California Public Utilities Commission  

E-Print Network [OSTI]

California Solar Initiative California Public Utilities Commission Staff Progress Report January 2008 #12;California Solar Initiative, CPUC Staff Progress Report, January 2008 This page intentionally left blank. #12;California Solar Initiative, CPUC Staff Progress Report, January 2008 Table of Contents

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

California Public Utilities Commission California Solar Initiative  

E-Print Network [OSTI]

California Public Utilities Commission California Solar Initiative Program Handbook May 2014 #12, Sonoma, CA Courtesy: SolarCraft #12;Table of Contents i California Solar Initiative Program Handbook September 2012 1. Introduction: California Solar Initiative Program

382

Generation gaps in engineering?  

E-Print Network [OSTI]

There is much enthusiastic debate on the topic of generation gaps in the workplace today; what the generational differences are, how to address the apparent challenges, and if the generations themselves are even real. ...

Kim, David J. (David Jinwoo)

2008-01-01T23:59:59.000Z

383

CONSULTANT REPORT DISTRIBUTED GENERATION  

E-Print Network [OSTI]

CONSULTANT REPORT DISTRIBUTED GENERATION INTEGRATION COST STUDY Analytical Framework energy development, or distributed generation, in California. In May 2012, Southern California Edison Southern California Edison's approach to evaluating distributed generation impacts, and to conduct

384

Guam Initial Technical Assessment Report  

SciTech Connect (OSTI)

Under an interagency agreement, funded by the Department of Interior's (DOI) Office of Insular Affairs (OIA), the National Renewable Energy Laboratory (NREL) was tasked to deliver technical assistance to the island of Guam by conducting an island initial technical assessment that would lay out energy consumption and production data and establish a baseline. This assessment will be used to conduct future analysis and studies by NREL that will estimate energy efficiency and renewable energy potential for the island of Guam.

Baring-Gould, I.; Conrad, M.; Haase, S.; Hotchkiss, E.; McNutt, P.

2011-04-01T23:59:59.000Z

385

Gravitational waves from known pulsars: results from the initial detector era  

E-Print Network [OSTI]

We present the results of searches for gravitational waves from a large selection of pulsars using data from the most recent science runs (S6, VSR2 and VSR4) of the initial generation of interferometric gravitational wave ...

Aggarwal, Nancy

386

Advanced Manufacturing Initiative Improves Turbine Blade Productivity...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Advanced Manufacturing Initiative Improves Turbine Blade Productivity Advanced Manufacturing Initiative Improves Turbine Blade Productivity May 20, 2011 - 2:56pm Addthis This is an...

387

Voluntary Initiative on Incentives: Toolkit Training Webinar...  

Energy Savers [EERE]

Voluntary Initiative on Incentives: Toolkit Training Webinar Voluntary Initiative on Incentives: Toolkit Training Webinar March 26, 2015 12:30PM to 2:0...

388

Innovative Corridors Initiative: Business Model Analysis  

E-Print Network [OSTI]

Wenger, Joyce. Business Models for Vehicle InfrastructureCorridors Initiative: Business Model Analysis Rachel S.Corridors Initiative: Business Model Analysis Task Order

Shaheen, Susan; Lingham, Viginia; Finson, Rachel S.

2007-01-01T23:59:59.000Z

389

California Low Carbon Fuels Infrastructure Investment Initiative...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Low Carbon Fuels Infrastructure Investment Initiative California Low Carbon Fuels Infrastructure Investment Initiative 2012 DOE Hydrogen and Fuel Cells Program and Vehicle...

390

2006 NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS  

Broader source: Energy.gov (indexed) [DOE]

NUCLEAR ENERGY RESEARCH INITIATIVE AWARDS Lead Organization Project Title Collaborators Advanced Fuel Cycle Initiative Massachusetts Institute of Technology The Development and...

391

Energy Innovation: Green Button Initiative Empowering Americans...  

Office of Environmental Management (EM)

Innovation: Green Button Initiative Empowering Americans to Save Energy and Money Energy Innovation: Green Button Initiative Empowering Americans to Save Energy and Money February...

392

The President's Biofuels Initiative | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

The President's Biofuels Initiative The President's Biofuels Initiative Presentation by Neil Rossmeissl at the October 24, 2006 Bio-Derived Liquids to Hydrogen Distributed...

393

Energy Transition Initiative: Islands Playbook (Book) | OSTI...  

Office of Scientific and Technical Information (OSTI)

Energy Transition Initiative: Islands Playbook (Book) Re-direct Destination: The Island Energy Playbook (the Playbook) provides an action-oriented guide to successfully initiating,...

394

Small Generator Aggregation (Maine)  

Broader source: Energy.gov [DOE]

This section establishes requirements for electricity providers to purchase electricity from small generators, with the goal of ensuring that small electricity generators (those with a nameplate...

395

Concentrated Solar Power Generation.  

E-Print Network [OSTI]

??Solar power generation is the most promising technology to transfer energy consumption reliance from fossil fuel to renewable sources. Concentrated solar power generation is a… (more)

Jin, Zhilei

2013-01-01T23:59:59.000Z

396

Triangle geometry processing for surface modeling and cartesian grid generation  

DOE Patents [OSTI]

Cartesian mesh generation is accomplished for component based geometries, by intersecting components subject to mesh generation to extract wetted surfaces with a geometry engine using adaptive precision arithmetic in a system which automatically breaks ties with respect to geometric degeneracies. During volume mesh generation, intersected surface triangulations are received to enable mesh generation with cell division of an initially coarse grid. The hexagonal cells are resolved, preserving the ability to directionally divide cells which are locally well aligned.

Aftosmis, Michael J. (San Mateo, CA) [San Mateo, CA; Melton, John E. (Hollister, CA) [Hollister, CA; Berger, Marsha J. (New York, NY) [New York, NY

2002-09-03T23:59:59.000Z

397

Application of curium measurements for safeguarding at reprocessing plants. Study 1: High-level liquid waste and Study 2: Spent fuel assemblies and leached hulls  

SciTech Connect (OSTI)

In large-scale reprocessing plants for spent fuel assemblies, the quantity of plutonium in the waste streams each year is large enough to be important for nuclear safeguards. The wastes are drums of leached hulls and cylinders of vitrified high-level liquid waste. The plutonium amounts in these wastes cannot be measured directly by a nondestructive assay (NDA) technique because the gamma rays emitted by plutonium are obscured by gamma rays from fission products, and the neutrons from spontaneous fissions are obscured by those from curium. The most practical NDA signal from the waste is the neutron emission from curium. A diversion of waste for its plutonium would also take a detectable amount of curium, so if the amount of curium in a waste stream is reduced, it can be inferred that there is also a reduced amount of plutonium. This report studies the feasibility of tracking the curium through a reprocessing plant with neutron measurements at key locations: spent fuel assemblies prior to shearing, the accountability tank after dissolution, drums of leached hulls after dissolution, and canisters of vitrified high-level waste after separation. Existing pertinent measurement techniques are reviewed, improvements are suggested, and new measurements are proposed. The authors integrate these curium measurements into a safeguards system.

Rinard, P.M.; Menlove, H.O.

1996-03-01T23:59:59.000Z

398

Graduate Education at UNH Next Generation Leadership  

E-Print Network [OSTI]

.gradschool.unh.edu #12;Graduate education at the University of New Hampshire prepares the next generation of leaders doctoral degrees, graduate study at UNH is the catalyst for maintaining the state of New Hampshire's highly Graduate education forges vital partnerships in many public health and human services initiatives statewide

New Hampshire, University of

399

Initial Decision and Risk Analysis  

SciTech Connect (OSTI)

Decision and Risk Analysis capabilities will be developed for industry consideration and possible adoption within Year 1. These tools will provide a methodology for merging qualitative ranking of technology maturity and acknowledged risk contributors with quantitative metrics that drive investment decision processes. Methods and tools will be initially introduced as applications to the A650.1 case study, but modular spreadsheets and analysis routines will be offered to industry collaborators as soon as possible to stimulate user feedback and co-development opportunities.

Engel, David W.

2012-02-29T23:59:59.000Z

400

Initial Steps | Argonne National Laboratory  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFunInfrared Land Surface Emissivity in the VicinitySrTiO3(100). | EMSLInitial

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

AVAILABLE ONLINE AT: INITIATED BY:  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartmentStewardshipAdministration helps INITIATED BY:

402

Spectrum of Initial Perturbations in Open and Closed Inflationary Models  

E-Print Network [OSTI]

Spectrum of initial scalar and tensor perturbations created during an inflationary stage producing a closed or open FRW universe now is discussed. In the closed case, the CMB temperature anisotropy ${\\Delta T/T}$ generated by scalar perturbations is enhanced for low multipoles. It is argued that in the open case there is no suppression of low multipoles. A possibility of the existence of a preferred space direction in the open case is noted.

A. A. Starobinsky

1996-03-15T23:59:59.000Z

403

Energy dependent growth of the nucleon and hydrodynamic initial conditions  

E-Print Network [OSTI]

Due to gluon saturation, the growth of the inelastic nucleon-nucleon cross section with increasing collision energy sqrt(s) results in a broadening of the nucleon's density distribution in position space. This leads to a natural smoothing of the initial energy density distribution in the transverse plane of the matter created near midrapidity in heavy-ion collisions. We study this effect for fluctuating initial conditions generated with the Monte Carlo Kharzeev-Levin-Nardi (MC-KLN) model for Au+Au collisions at the Relativistic Heavy Ion Collider (RHIC) and the Large Hadron Collider (LHC). We argue that at the LHC viscous hydrodynamics is applicable at earlier times than at RHIC, not only because of the higher temperature but also since the length scale over which the initial pressure fluctuates increases with collision energy.

Ulrich W. Heinz; J. Scott Moreland

2011-10-19T23:59:59.000Z

404

Generation of Web Service Descriptions and Web Service  

E-Print Network [OSTI]

Generation of Web Service Descriptions and Web Service Module Implementation for Concept University of Science and Technology Software Systems Institute (STS) #12;Abstract Nowadays web services in order to initiate the communication. A web services endpoint communication interface utilizes

405

ENERGY GENERATION RESEARCH PIER Energy Generation Research  

E-Print Network [OSTI]

ENERGY GENERATION RESEARCH PIER Energy Generation Research www.energy.ca.gov/research/ renewable/ November 2010 Sonoma County RESCO A Local Level Approach to Renewable Energy Portfolios. The Issue To address energy usage that contributes to climate change, California has enacted legislation to guide

406

Gamma ray generator  

DOE Patents [OSTI]

An embodiment of a gamma ray generator includes a neutron generator and a moderator. The moderator is coupled to the neutron generator. The moderator includes a neutron capture material. In operation, the neutron generator produces neutrons and the neutron capture material captures at least some of the neutrons to produces gamma rays. An application of the gamma ray generator is as a source of gamma rays for calibration of gamma ray detectors.

Firestone, Richard B; Reijonen, Jani

2014-05-27T23:59:59.000Z

407

Generation to Generation: The Heart of Family Medicine  

E-Print Network [OSTI]

Ageism in the Workplace. Generations Spring, 5. Westman,of caring for multiple generations simultaneously. StronglyGeneration to Generation: The Heart of Family Medicine

Winter, Robin O

2012-01-01T23:59:59.000Z

408

American Samoa Initial Technical Assessment Report  

SciTech Connect (OSTI)

This document is an initial energy assessment for American Samoa, the first of many steps in developing a comprehensive energy strategy. On March 1, 2010, Assistant Secretary of the Interior Tony Babauta invited governors and their staff from the Interior Insular Areas to meet with senior principals at the National Renewable Energy Laboratory (NREL). Meeting discussions focused on ways to improve energy efficiency and increase the deployment of renewable energy technologies in the U.S. Pacific Territories. In attendance were Governors Felix Camacho (Guam), Benigno Fitial (Commonwealth of the Northern Mariana Islands), and Togiola Tulafono, (American Samoa). This meeting brought together major stakeholders to learn and understand the importance of developing a comprehensive strategic plan for implementing energy efficiency measures and renewable energy technologies. For several decades, dependence on fossil fuels and the burden of high oil prices have been a major concern but never more at the forefront as today. With unstable oil prices, the volatility of fuel supply and the economic instability in American Samoa, energy issues are a high priority. In short, energy security is critical to American Samoa's future economic development and sustainability. Under an interagency agreement, funded by the Department of Interior's Office of Insular Affairs, NREL was tasked to deliver technical assistance to the islands of American Samoa. Technical assistance included conducting an initial technical assessment to define energy consumption and production data, establish an energy consumption baseline, and assist with the development of a strategic plan. The assessment and strategic plan will be used to assist with the transition to a cleaner energy economy. NREL provided an interdisciplinary team to cover each relevant technical area for the initial energy assessments. Experts in the following disciplines traveled to American Samoa for on-island site assessments: (1) Energy Efficiency and Building Technologies; (2) Integrated Wind-Diesel Generation; (3) Transmission and Distribution; (4) Solar Technologies; and (5) Biomass and Waste-to-Energy. In addition to these core disciplines, team capabilities also included expertise in program analysis, project financing, energy policy and energy planning. The intent of the technical assessment was to provide American Samoa with a baseline energy assessment. From the baseline, various scenarios and approaches for deploying cost effective energy efficiency and renewable energy technologies could be created to meet American Samoa's objectives. The information provided in this energy assessment will be used as input in the development of a draft strategic plan and the development of scenarios and strategies for deploying cost-effective energy efficiency and renewable products.

Busche, S.; Conrad, M.; Funk, K.; Kandt, A.; McNutt, P.

2011-09-01T23:59:59.000Z

409

Plug-in Hybrid Initiative  

SciTech Connect (OSTI)

Our main project objective was to implement Plug-in Electric Vehicles (PEV) and charging infrastructure into our electric distribution service territory and help reduce barriers in the process. Our research demonstrated the desire for some to be early adopters of electric vehicles and the effects lack of education plays on others. The response of early adopters was tremendous: with the initial launch of our program we had nearly 60 residential customers interested in taking part in our program. However, our program only allowed for 15 residential participants. Our program provided assistance towards purchasing a PEV and installation of Electric Vehicle Supply Equipment (EVSE). The residential participants have all come to love their PEVs and are more than enthusiastic about promoting the many benefits of driving electric.

Goodman, Angie; Moore, Ray; Rowden, Tim

2013-09-27T23:59:59.000Z

410

Cylindrical neutron generator  

DOE Patents [OSTI]

A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360.degree. and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Leung, Ka-Ngo

2005-06-14T23:59:59.000Z

411

Cylindrical neutron generator  

DOE Patents [OSTI]

A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360.degree. and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Leung, Ka-Ngo (Hercules, CA)

2008-04-22T23:59:59.000Z

412

Cylindrical neutron generator  

DOE Patents [OSTI]

A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360.degree. and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Leung, Ka-Ngo (Hercules, CA)

2009-12-29T23:59:59.000Z

413

Safeguards and Security Program  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Ensures appropriate levels of protection against unauthorized access; theft, diversion, loss of custody, or destruction of nuclear weapons, or weapons components; espionage; loss or theft of classified matter or Government property; and other hostile acts that may cause unacceptable adverse impacts on national security or on the health and safety of Department of Energy (DOE) and contractor employees, the public, or the environment. DOE N 251.40, dated 5/3/01, extends this directive until 12/31/01. Cancels DOE 5630.11B, DOE 5630.13A, DOE 5630.14A, DOE 5630.15, DOE 5630.16A, DOE 5630.17, DOE 5631.1C, DOE 5631.4A, DOE 5634.1B, DOE 5634.3, DOE 5639.3, and Chapter IX of DOE M 5632.1C-1

1995-09-28T23:59:59.000Z

414

Safeguarding indoor air quality  

SciTech Connect (OSTI)

California has created and implemented the first state program devoted exclusively to the investigation of nonindustrial indoor air quality. The program is responsible for promoting and conducting research on the determining factors of healthful indoor environments and is structured to obtain information about emission sources, ventilation effects, indoor concentrations, human activity patterns, exposures, health risks, control measures and public policy options. Data are gathered by a variety of methods, including research conducted by staff members, review of the available scientific literature, participation in technical meetings, contractual agreements with outside agencies, cooperative research projects with other groups and consultation with experts. 23 references, 1 figure, 1 table.

Sexton, K.; Wesolowski, J.J.

1985-01-01T23:59:59.000Z

415

Facility Safeguardability Assessment Report  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNational NuclearhasAdministration77Nuclear SecurityFAPAC-NM | NationalFY

416

safeguards and security  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF8/%2A ennike |1/%2A en9/%2Arussia

417

New generation enrichment monitoring technology for gas centrifuge enrichment plants  

SciTech Connect (OSTI)

The continuous enrichment monitor, developed and fielded in the 1990s by the International Atomic Energy Agency, provided a go-no-go capability to distinguish between UF{sub 6} containing low enriched (approximately 4% {sup 235}U) and highly enriched (above 20% {sup 235}U) uranium. This instrument used the 22-keV line from a {sup 109}Cd source as a transmission source to achieve a high sensitivity to the UF{sub 6} gas absorption. The 1.27-yr half-life required that the source be periodically replaced and the instrument recalibrated. The instrument's functionality and accuracy were limited by the fact that measured gas density and gas pressure were treated as confidential facility information. The modern safeguarding of a gas centrifuge enrichment plant producing low-enriched UF{sub 6} product aims toward a more quantitative flow and enrichment monitoring concept that sets new standards for accuracy stability, and confidence. An instrument must be accurate enough to detect the diversion of a significant quantity of material, have virtually zero false alarms, and protect the operator's proprietary process information. We discuss a new concept for advanced gas enrichment assay measurement technology. This design concept eliminates the need for the periodic replacement of a radioactive source as well as the need for maintenance by experts. Some initial experimental results will be presented.

Ianakiev, Kiril D [Los Alamos National Laboratory; Alexandrov, Boian S. [Los Alamos National Laboratory; Boyer, Brian D. [Los Alamos National Laboratory; Hill, Thomas R. [Los Alamos National Laboratory; Macarthur, Duncan W. [Los Alamos National Laboratory; Marks, Thomas [Los Alamos National Laboratory; Moss, Calvin E. [Los Alamos National Laboratory; Sheppard, Gregory A. [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory

2008-06-13T23:59:59.000Z

418

Initial Risk Analysis and Decision Making Framework  

SciTech Connect (OSTI)

Commercialization of new carbon capture simulation initiative (CCSI) technology will include two key elements of risk management, namely, technical risk (will process and plant performance be effective, safe, and reliable) and enterprise risk (can project losses and costs be controlled within the constraints of market demand to maintain profitability and investor confidence). Both of these elements of risk are incorporated into the risk analysis subtask of Task 7. Thus far, this subtask has developed a prototype demonstration tool that quantifies risk based on the expected profitability of expenditures when retrofitting carbon capture technology on a stylized 650 MW pulverized coal electric power generator. The prototype is based on the selection of specific technical and financial factors believed to be important determinants of the expected profitability of carbon capture, subject to uncertainty. The uncertainty surrounding the technical performance and financial variables selected thus far is propagated in a model that calculates the expected profitability of investments in carbon capture and measures risk in terms of variability in expected net returns from these investments. Given the preliminary nature of the results of this prototype, additional work is required to expand the scope of the model to include additional risk factors, additional information on extant and proposed risk factors, the results of a qualitative risk factor elicitation process, and feedback from utilities and other interested parties involved in the carbon capture project. Additional information on proposed distributions of these risk factors will be integrated into a commercial implementation framework for the purpose of a comparative technology investment analysis.

Engel, David W.

2012-02-01T23:59:59.000Z

419

Schneider Electric Director Initiates Strategy to Recruit IAC Graduates |  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment,Institutes and Response EventsSafeguardsPerformance in North America

420

Electrical initiation of an energetic nanolaminate film  

DOE Patents [OSTI]

A heating apparatus comprising an energetic nanolaminate film that produces heat when initiated, a power source that provides an electric current, and a control that initiates the energetic nanolaminate film by directing the electric current to the energetic nanolaminate film and joule heating the energetic nanolaminate film to an initiation temperature. Also a method of heating comprising providing an energetic nanolaminate film that produces heat when initiated, and initiating the energetic nanolaminate film by directing an electric current to the energetic nanolaminate film and joule heating the energetic nanolaminate film to an initiation temperature.

Tringe, Joseph W. (Walnut Creek, CA); Gash, Alexander E. (Brentwood, CA); Barbee, Jr., Troy W. (Palo Alto, CA)

2010-03-30T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

New wave generation  

E-Print Network [OSTI]

We present the results of a combined experimental and numerical study of the generation of internal waves using the novel internal wave generator design of Gostiaux et al. (Exp. Fluids, vol. 42, 2007, pp. 123–130). This ...

Mercier, Matthieu J.

422

Electron generation of leptons and hadrons with reciprocal -quantized lifetimes and masses  

E-Print Network [OSTI]

1 Electron generation of leptons and hadrons with reciprocal -quantized lifetimes and masses generation occurs via an initial "-leap" from an electron pair to a "platform state" M, and then subsequent in the generation of hadron masses. In fact, the role of the electron in generating lepton masses has never been

423

Childhood Cancer Tracking Initiative in Massachusetts  

E-Print Network [OSTI]

Childhood Cancer Tracking Initiative in Massachusetts: Developing a New Electronic Tool Presented (CEH) Massachusetts Department of Public Health (MDPH) #12;Childhood Cancer Tracking Initiative "Develop methods for linking environmental databases with childhood cancer incidence data to identify

424

CALIFORNIA SOLAR INITIATIVE-THERMAL PROGRAMHANDBOOK  

E-Print Network [OSTI]

CALIFORNIA SOLAR INITIATIVE-THERMAL PROGRAMHANDBOOK CALIFORNIA PUBLIC UTILITIES California Solar Initiative Thermal Program Handbook i 1. Introduction to CSI-Thermal Program COMMISSION May 2010 #12; The California Public

425

A comparison of the additional protocols of the five nuclear weapon states and the ensuing safeguards benefits to international nonproliferation efforts  

SciTech Connect (OSTI)

With the 6 January 2009 entry into force of the Additional Protocol by the United States of America, all five declared Nuclear Weapon States that are part of the Nonproliferation Treaty have signed, ratified, and put into force the Additional Protocol. This paper makes a comparison of the strengths and weaknesses of the five Additional Protocols in force by the five Nuclear Weapon States with respect to the benefits to international nonproliferation aims. This paper also documents the added safeguards burden to the five declared Nuclear Weapon States that these Additional Protocols put on the states with respect to access to their civilian nuclear programs and the hosting of complementary access activities as part of the Additional Protocol.

Uribe, Eva C [Los Alamos National Laboratory; Sandoval, M Analisa [Los Alamos National Laboratory; Sandoval, Marisa N [Los Alamos National Laboratory; Boyer, Brian D [Los Alamos National Laboratory; Leitch, Rosalyn M [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

426

Clean Energy Manufacturing Initiative Industrial Efficiency and...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Industrial Efficiency and Energy Productivity Video Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video Addthis Description Industrial...

427

Air, Health, Clean Energy, and Related Economic Impacts: Assessing the Many Benefits of State and Local Clean Energy Initiatives Multiple Benefits of Clean Energy Initiatives  

E-Print Network [OSTI]

Reducing energy demand and/or increasing renewable energy generation from state and local clean energy initiatives—such as goals, standards, codes, funds, and programs—can generate many benefits, including: ••Security, diversity, and overall reliability improvements for the electric system. ••Improved environmental quality, human health, and quality of life. ••Positive economic gains through energy costs saved, avoided medical costs, higher disposable incomes, increased labor productivity, and more jobs. This brief is part of a series and focuses on environmental and human health benefits. State and local governments can analyze their clean energy initiatives using methods and tools described in EPA’s Assessing the

unknown authors

428

California Solar Initiative California Public Utilities Commission  

E-Print Network [OSTI]

California Solar Initiative California Public Utilities Commission Staff Progress Report January 2009 #12;2 California Solar Initiative CPUC Staff Progress Report - January 2009 The California Public progress on the California Solar Initiative, the country's largest solar incentive program. In January 2007

429

California Solar Initiative California Public Utilities Commission  

E-Print Network [OSTI]

California Solar Initiative California Public Utilities Commission Staff Progress Report October 2008 #12;2 California Solar Initiative CPUC Staff Progress Report - October 2008 The California Public progress on the California Solar Initiative, the country's largest solar incentive program. In January 2007

430

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect (OSTI)

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K. NNL

2011-01-13T23:59:59.000Z

431

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect (OSTI)

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Boyer, B. D. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K., NNL

2010-11-24T23:59:59.000Z

432

a549 cells initial: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Juan A. Valiente Kroon 2007-12-20 93 Column Initialization 1 Initializing Distillation Column Models 1 Mathematics Websites Summary: Column Initialization 1 Initializing...

433

aav initiator protein: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Juan A. Valiente Kroon 2007-12-20 94 Column Initialization 1 Initializing Distillation Column Models 1 Mathematics Websites Summary: Column Initialization 1 Initializing...

434

aquifex aeolicus initiates: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Juan A. Valiente Kroon 2007-12-20 44 Column Initialization 1 Initializing Distillation Column Models 1 Mathematics Websites Summary: Column Initialization 1 Initializing...

435

Voltage controlled MESFET pulse shape generator  

SciTech Connect (OSTI)

A programmable pulse shape generator capable of producing pulse shapes for Nova and Beamlet has been designed and simulated using the circuit code SPICE. The design utilizes power MESFETS, which are commonly used in microwave amplifiers. The pulse shape is varied by setting a bias voltage on each in a chain of MESFETS with a 200 ps temporal resolution. The electrical pulse then drives an integrated electro-optic modulator similar to what is on Beamlet. Pulse shapes 22 and 25, used on Nova, have been generated by this design. There is no fundamental barrier to making such a pulse generator for use on the National Ignition Facility. In fact, the longer time scales on the NIF pulse will ease the high speed requirements of the pulse shape generator allowing the use of less expensive components. The next step will be to build a prototype circuit for initial testing on Beamlet and Nova.

Burkhart, S.C.

1994-10-26T23:59:59.000Z

436

Summary Report of Summer 2009 NGSI Human Capital Development Efforts at Lawrence Livermore National Laboratory  

SciTech Connect (OSTI)

In 2009, Lawrence Livermore National Laboratory (LLNL) engaged in several activities to support NA-24's Next Generation Safeguards Initiative (NGSI). This report outlines LLNL's efforts to support Human Capital Development (HCD), one of five key components of NGSI managed by Dunbar Lockwood in the Office of International Regimes and Agreements (NA-243). There were five main LLNL summer safeguards HCD efforts sponsored by NGSI: (1) A joint Monterey Institute of International Studies/Center for Nonproliferation Studies-LLNL International Safeguards Policy and Information Analysis Course; (2) A Summer Safeguards Policy Internship Program at LLNL; (3) A Training in Environmental Sample Analysis for IAEA Safeguards Internship; (4) Safeguards Technology Internships; and (5) A joint LLNL-INL Summer Safeguards Lecture Series. In this report, we provide an overview of these five initiatives, an analysis of lessons learned, an update on the NGSI FY09 post-doc, and an update on students who participated in previous NGSI-sponsored LLNL safeguards HCD efforts.

Dougan, A; Dreicer, M; Essner, J; Gaffney, A; Reed, J; Williams, R

2009-11-16T23:59:59.000Z

437

Potential growth of nuclear and coal electricity generation in the US  

SciTech Connect (OSTI)

Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs.

Bloomster, C.H.; Merrill, E.T.

1989-08-01T23:59:59.000Z

438

Heat engine generator control system  

DOE Patents [OSTI]

An electrical power generation system includes a heat engine having an output member operatively coupled to the rotor of a dynamoelectric machine. System output power is controlled by varying an electrical parameter of the dynamoelectric machine. A power request signal is related to an engine speed and the electrical parameter is varied in accordance with a speed control loop. Initially, the sense of change in the electrical parameter in response to a change in the power request signal is opposite that required to effectuate a steady state output power consistent with the power request signal. Thereafter, the electrical parameter is varied to converge the output member speed to the speed known to be associated with the desired electrical output power.

Rajashekara, Kaushik (Carmel, IN); Gorti, Bhanuprasad Venkata (Towson, MD); McMullen, Steven Robert (Anderson, IN); Raibert, Robert Joseph (Fishers, IN)

1998-01-01T23:59:59.000Z

439

Heat engine generator control system  

DOE Patents [OSTI]

An electrical power generation system includes a heat engine having an output member operatively coupled to the rotor of a dynamoelectric machine. System output power is controlled by varying an electrical parameter of the dynamoelectric machine. A power request signal is related to an engine speed and the electrical parameter is varied in accordance with a speed control loop. Initially, the sense of change in the electrical parameter in response to a change in the power request signal is opposite that required to effectuate a steady state output power consistent with the power request signal. Thereafter, the electrical parameter is varied to converge the output member speed to the speed known to be associated with the desired electrical output power. 8 figs.

Rajashekara, K.; Gorti, B.V.; McMullen, S.R.; Raibert, R.J.

1998-05-12T23:59:59.000Z

440

Creating a Cognitive Agent in a Virtual World: Planning, Navigation, and Natural Language Generation  

E-Print Network [OSTI]

Generation . . . . . . . . . . . . . . . . . . . . .Language Generation . . . . . . . . . . . . . . . . .Language Generation . . . . . . . . . . . . . . . . . . . .

Hewlett, William

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "generation safeguards initiative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source is disclosed. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances. 4 figs.

Moldenhauer, J.E.

1987-08-25T23:59:59.000Z

442

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances.

Moldenhauer, James E. (Simi Valley, CA)<