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1

1990 update for the applications guide to pedestrian SNM (special nuclear material) monitors  

SciTech Connect

The physical principles of special nuclear material (SNM) monitoring have not changed in the five years since the writing of the Los Alamos report, An Applications Guide to Pedestrian SNM Monitors (AL-10633-MS).'' However, during those years, there has been evidence for the start of significant change in the practice of SNM monitoring. Recently revised Department of Energy orders allow flexibility in selecting material-control measures by addressing both abrupt and protracted theft or diversion of SNM and by grading the material according to its attractiveness. Other new guideline on how to apply, test, and maintain SNM monitors and metal detectors are becoming available from the American Society for Testing and Materials. But perhaps the most noticeable change to the Applications Guide is in Part 3, the catalog of commercial pedestrian SNM monitors, where many obsolete entries have been replaced by new monitors. This update for the Applications Guide catalogs new pedestrian SNM monitors and discusses what is new and what is changing in the practice of SNM monitoring. 31 refs., 11 figs.

Fehlau, P.E.

1990-12-01T23:59:59.000Z

2

1997 update for the applications guide to vehicle SNM monitors  

SciTech Connect

Ten years have elapsed since the publication of the original applications guide to vehicle special nuclear material (SNM) monitors. During that interval, use of automatic vehicle monitors has become more commonplace, and formal procedures for monitor upkeep and evaluation have become available. New concepts for vehicle monitoring are being explored, as well. This update report reviews the basics of vehicle SNM monitoring, discusses what is new in vehicle SNM monitoring, and catalogs the vehicle SNM monitors that are commercial available.

York, R.L.; Fehlau, P.E.

1997-04-01T23:59:59.000Z

3

Special nuclear material simulation device  

DOE Patents (OSTI)

An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

2014-08-12T23:59:59.000Z

4

Applications guide to pedestrian SNM monitors  

SciTech Connect

The applications guide introduces readers to the pedestrian special nuclear material (SNM) monitors that provide nuclear material control at DOE contractor facilities. It explains the principles of operation, the strong and weak points, and steps for calibration and maintenance of the monitors. Administrators and security specialists will find an overview of pedestrain monitor application and upkeep in Part 1 of the guide and a descriptive catalog of present-day monitors in Part 3. Technically oriented readers will be interested in the more detailed discussion of SNM monitoring physics and SNM monitor design principles found in Part 2. 18 refs., 33 figs., 9 tabs.

Fehlau, P.E.

1986-02-01T23:59:59.000Z

5

Special nuclear material radiation monitors for the 1980's  

SciTech Connect

During the two decades that automatic gamma-radiation monitors have been applied to detecting special nuclear material (SNM), little attention has been devoted to how well the monitors perform in plant environments. Visits to 11 DOE facilities revealed poor information flow between developers, manufacturers, and maintainers of SNM radiation monitors. To help users achieve best performance from their monitors or select new ones, Los Alamos National Laboratory developed a hand-held monitor user's guide, calibration manuals for some commercial SNM pedestrian monitors, and an application guide for SNM pedestrian monitors. In addition, Los Alamos evaluated new commercial SNM monitors, considered whether to apply neutron detection to SNM monitoring, and investigated the problem of operating gamma-ray SNM monitors in variable plutonium gamma-radiation fields. As a result, the performance of existing SNM monitors will improve and alternative monitoring methods will become commerciallly available during the 1980s. 9 refs., 6 figs., 1 tab.

Fehlau, P.E.

1985-01-01T23:59:59.000Z

6

An applications guide to vehicle SNM monitors  

SciTech Connect

The applications guide introduces its readers to the vehicle special nuclear material (SNM) monitors that are becoming part of safeguards and security measures for nuclear material control at DOE facilities. Building on the foundation provided by an applications guide to pedestrian SNM monitors published in 1986 and a technical report on vehicle monitoring published in 1982, the guide provides an overview of vehicle monitoring in Part 1, a discussion of technical aspects of vehicle monitoring in Part 2, and a catalog of vehicle SNM monitors available to DOE facilities in Part 3. Vehicle monitor upkeep, calibration, testing, and performance are important topics in Part 1. The short technical discussion in Part 2 is devoted to new developments and unique features of vehicle monitors.

Fehlau, P.E.

1987-03-01T23:59:59.000Z

7

Age Dating of Mixed SNM--Preliminary Investigations  

SciTech Connect

Recently we investigated the nuclear forensics problem of age determination for mixed special nuclear material (SNM). Through limited computational mixing experiments and interactive age analysis, it was observed that age dating results are generally affected by the mixing of samples with different assays or even by small radioactive material contamination. The mixing and contamination can be detected through interactive age analysis, a function provided by the Decay Interaction, Visualization and Analysis (DIVA) software developed by NSTec. It is observed that for mixed SNM with two components, the age estimators typically fall into two distinct clusters on the time axis. This suggests that averaging or other simple statistical methods may not always be suitable for age dating SNM mixtures. Instead, an interactive age analysis would be more suitable for age determination of material components of such SNM mixtures. This work was supported by the National Center for Nuclear Security (NCNS).

Yuan, D., Guss, P. P., Yfantis, E., Klingensmith, A., Emer, D.

2011-12-01T23:59:59.000Z

8

A portable, automatic SNM monitor for nuclear safeguards: Development, evaluation, and applications  

SciTech Connect

The portable SNM monitor is a lightweight, full-size, automatic monitor, suitable for temporary service (such as demonstrations or for use during maintenance) or as a permanent replacement for hand- held monitors. The authors based the monitor on the TSA Systems, Ltd., modular SNM monitor design and, through evaluation and improvement of the commercial modules, obtained adequate sensitivity in a single- cabinet monitor that is easily portable. Complete monitoring of pedestrians with a single detector cabinet is achieved by requiring the pedestrian to stand in front of the detectors and turn around through 360 deg while being observed by a security inspector. The monitor is available commercially as the TSA Systems Model PMD-701, and it is beginning to be used in both temporary and permanent applications.

Fehlau, P.E.

1993-09-01T23:59:59.000Z

9

Methods of Verification, Accountability and Control of Special Nuclear Material  

SciTech Connect

This session demonstrates nondestructive assay (NDA) measurement, surveillance and analysis technology required to protect, control and account (MPC and A) for special nuclear materials (SNM) in sealed containers. These measurements, observations and analyses comprise state-of-the art, strengthened, SNM safeguards systems. Staff member specialists, actively involved in research, development, training and implementation worldwide, will present six NDA verification systems and two software tools for integration and analysis of facility MPC and A data.

Stewart, J.E.

1999-05-03T23:59:59.000Z

10

Standard guide for application of radiation monitors to the control and physical security of special nuclear material  

E-Print Network (OSTI)

1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

American Society for Testing and Materials. Philadelphia

1999-01-01T23:59:59.000Z

11

Nuclear Materials Management Program at the NNSS  

SciTech Connect

The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the gaps and stand up a functional and compliant NMM Program at the NNSS.

,

2012-06-08T23:59:59.000Z

12

A NEW ALGORITHM FOR RADIOISOTOPE IDENTIFICATION OF SHIELDED AND MASKED SNM/RDD MATERIALS  

SciTech Connect

Detection and identification of shielded and masked nuclear materials is crucial to national security, but vast borders and high volumes of traffic impose stringent requirements for practical detection systems. Such tools must be be mobile, and hence low power, provide a low false alarm rate, and be sufficiently robust to be operable by non-technical personnel. Currently fielded systems have not achieved all of these requirements simultaneously. Transport modeling such as that done in GADRAS is able to predict observed spectra to a high degree of fidelity; our research is focusing on a radionuclide identification algorithm that inverts this modeling within the constraints imposed by a handheld device. Key components of this work include incorporation of uncertainty as a function of both the background radiation estimate and the hypothesized sources, dimensionality reduction, and nonnegative matrix factorization. We have partially evaluated performance of our algorithm on a third-party data collection made with two different sodium iodide detection devices. Initial results indicate, with caveats, that our algorithm performs as good as or better than the on-board identification algorithms. The system developed was based on a probabilistic approach with an improved approach to variance modeling relative to past work. This system was chosen based on technical innovation and system performance over algorithms developed at two competing research institutions. One key outcome of this probabilistic approach was the development of an intuitive measure of confidence which was indeed useful enough that a classification algorithm was developed based around alarming on high confidence targets. This paper will present and discuss results of this novel approach to accurately identifying shielded or masked radioisotopes with radiation detection systems.

Jeffcoat, R.

2012-06-05T23:59:59.000Z

13

Special Nuclear Material Portal Monitoring at the Nevada Test Site  

SciTech Connect

Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

DeAnn Long; Michael Murphy

2008-07-01T23:59:59.000Z

14

NUCLEAR MATERIAL ATTRACTIVENESS: AN ASSESSMENT OF MATERIAL ASSOCIATED WITH A CLOSED FUEL CYCLE  

SciTech Connect

This paper examines the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the various processing steps required for a closed fuel cycle. This paper combines the results from earlier studies that examined the attractiveness of SNM associated with the processing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR with new results for the final, repeated burning of SNM in fast-spectrum reactors: fast reactors and accelerator driven systems (ADS). The results of this paper suggest that all reprocessing products evaluated so far need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of "attractiveness levels" that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, or undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

Bathke, C. G.; Ebbinghaus, B.; Sleaford, Brad W.; Wallace, R. K.; Collins, Brian A.; Hase, Kevin R.; Robel, Martin; Jarvinen, G. D.; Bradley, Keith S.; Ireland, J. R.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

2010-06-11T23:59:59.000Z

15

Nuclear Reactor Materials and Fuels  

Science Journals Connector (OSTI)

Nuclear reactor materials and fuels can be classified into six categories: Nuclear fuel materials Nuclear clad materials Nuclear coolant materials Nuclear poison materials Nuclear moderator materials

Dr. James S. Tulenko

2012-01-01T23:59:59.000Z

16

Muon Tracking to Detect Special Nuclear Materials  

SciTech Connect

Previous experiments have proven that nuclear assemblies can be imaged and identified inside of shipping containers using vertical trajectory cosmic-ray muons with two-sided imaging. These experiments have further demonstrated that nuclear assemblies can be identified by detecting fission products in coincidence with tracked muons. By developing these technologies, advanced sensors can be designed for a variety of warhead monitoring and detection applications. The focus of this project is to develop tomographic-mode imaging using near-horizontal trajectory muons in conjunction with secondary particle detectors. This will allow imaging in-situ without the need to relocate the objects and will enable differentiation of special nuclear material (SNM) from other high-Z materials.

Schwellenbach, D. [NSTec; Dreesen, W. [NSTec; Green, J. A. [NSTec; Tibbitts, A. [NSTec; Schotik, G. [NSTec; Borozdin, K. [LANL; Bacon, J. [LANL; Midera, H. [LANL; Milner, C. [LANL; Morris, C. [LANL; Perry, J. [LANL; Barrett, S. [UW; Perry, K. [UW; Scott, A. [UW; Wright, C. [UW; Aberle, D. [NSTec

2013-03-18T23:59:59.000Z

17

SNM detection by active muon interrogation  

SciTech Connect

Muons are charged particles with mass between the electron and proton and can be produced indirectly through pion decay by interaction of a charged-particle beam with a target. There are several distinct features of the muon interaction with matter attractive as a probe for detection of SNM at moderate ranges. These include muon penetration of virtually any amount of material without significant nuclear interaction until stopped by ionization loss in a short distance. When stopped, high-energy penetrating x-rays (in the range of 6 MeV for uranium,) unique to isotopic composition are emitted in the capture process. The subsequent interaction with the nucleus produces additional radiation useful in assessing SNM presence. A focused muon beam can be transported through the atmosphere, at a range limited mainly by beam-size growth through scattering. A muonbeam intensity of > 10{sup 9} /second is required for efficient interrogation and, as in any other technique, dose limits are to be respected. To produce sufficient muons a high-energy (threshold {approx}140 MeV) high-intensity (<1 mA) proton or electron beam is needed implying the use of a linear accelerator to bombard a refractory target. The muon yield is fractionally small, with large angle and energy dispersion, so that efficient collection is necessary in all dimensions of phase space. To accomplish this Los Alamos has proposed a magnetic collection system followed by a unique linear accelerator that provides the requisite phase-space bunching and allows an energy sweep to successively stop muons throughout a large structure such as a sea-going vessel. A possible maritime application would entail fitting the high-gradient accelerators on a large ship with a helicopter-borne detection system. We will describe our experimental results for muon effects and particle collection along with our current design and program for a muon detection system.

Jason, Andrew J [Los Alamos National Laboratory; Miyadera, Haruo [Los Alamos National Laboratory; Turchi, Peter J [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

18

Perimeter radiation monitors for the control and physical security of special nuclear materials  

SciTech Connect

Perimeter radiation monitors are gamma-ray and neutron measurement systems that can provide timely notice of theft or diversion of special nuclear material (SNM). The monitors may be hand-held instruments operated by security inspectors or automatic pedestrian or vehicle monitors located in exit pathways. A monitor's performance depends on its design, the characteristics of SNM and the operating environment, and proper monitor calibration and maintenance. Goals of ASTM Subcommittee C26.12 are to describe monitoring technology, how to apply it, and how to test its performance. 3 refs., 6 figs.

Fehlau, P.E.

1990-01-01T23:59:59.000Z

19

Calibrating and training of neutron based NSA techniques with less SNM standards  

SciTech Connect

Accessing special nuclear material (SNM) standards for the calibration of and training on nondestructive assay (NDA) instruments has become increasingly difficult in light of enhanced safeguards and security regulations. Limited or nonexistent access to SNM has affected neutron based NDA techniques more than gamma ray techniques because the effects of multiplication require a range of masses to accurately measure the detector response. Neutron based NDA techniques can also be greatly affected by the matrix and impurity characteristics of the item. The safeguards community has been developing techniques for calibrating instrumentation and training personnel with dwindling numbers of SNM standards. Monte Carlo methods have become increasingly important for design and calibration of instrumentation. Monte Carlo techniques have the ability to accurately predict the detector response for passive techniques. The Monte Carlo results are usually benchmarked to neutron source measurements such as californium. For active techniques, the modeling becomes more difficult because of the interaction of the interrogation source with the detector and nuclear material; and the results cannot be simply benchmarked with neutron sources. A Monte Carlo calculated calibration curve for a training course in Indonesia of material test reactor (MTR) fuel elements assayed with an active well coincidence counter (AWCC) will be presented as an example. Performing training activities with reduced amounts of nuclear material makes it difficult to demonstrate how the multiplication and matrix properties of the item affects the detector response and limits the knowledge that can be obtained with hands-on training. A neutron pulse simulator (NPS) has been developed that can produce a pulse stream representative of a real pulse stream output from a detector measuring SNM. The NPS has been used by the International Atomic Energy Agency (IAEA) for detector testing and training applications at the Agency due to the lack of appropriate SNM standards. This paper will address the effect of reduced access to SNM for calibration and training of neutron NDA applications along with the advantages and disadvantages of some solutions that do not use standards, such as the Monte Carlo techniques and the NPS.

Geist, William H [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Bracken, David S [Los Alamos National Laboratory; Freeman, Corey R [Los Alamos National Laboratory; Newell, Matthew R [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

20

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

SciTech Connect

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

Note: This page contains sample records for the topic "nuclear material snm" 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.


21

Bayesian network analysis of nuclear acquisitions  

E-Print Network (OSTI)

(SNM). 5 The definition of SNM currently encompasses plutonium and uranium with the isotopes of uranium-233 (U-233) or uranium-235 (U-235) being enriched to greater than twenty percent. Materials for Nuclear Weapons Uranium is contained in soils... the standpoint of preventing the spread of nuclear weapons, the short list of material usable for this purpose may be confined to those that are used for fission based weapons, uranium and plutonium, which are commonly referred to as Special Nuclear Materials...

Freeman, Corey Ross

2009-05-15T23:59:59.000Z

22

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards...

23

Comprehensive Nuclear Materials  

SciTech Connect

This book encompasses a rich seam of current information on the vast and multidisciplinary field of nuclear materials employed in fission and prototype fusion systems. Discussion includes both historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds leading scientists and engineers. Synthesizes pertinent current science to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

Konings, Dr. Rudy J. M. [European Commission Joint Research Centre; Allen, Todd R. [University of Wisconsin, Madison; Stoller, Roger E [ORNL; Yamanaka, Prof. Shinsuke [Osaka University

2012-01-01T23:59:59.000Z

24

FURTHER ASSESSMENTS OF THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FROM A SAFEGUARDS PERSPECTIVE  

SciTech Connect

This paper summarizes the results of an extension to an earlier study [ ] that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) associated with the PUREX, UREX+, and COEX reprocessing schemes. This study focuses on the materials associated with the UREX, COEX, THOREX, and PYROX reprocessing schemes. This study also examines what is required to render plutonium as unattractive. Furthermore, combining the results of this study with those from the earlier study permits a comparison of the uranium and thorium based fuel cycles on the basis of the attractiveness of the SNM associated with each fuel cycle. Both studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of attractiveness levels that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities [ ]. The methodology and key findings will be presented. Additionally, how these attractiveness levels relate to proliferation resistance (e.g. by increasing impediments to the diversion, theft, undeclared production of SNM for the purpose of acquiring a nuclear weapon), and how they could be used to help inform policy makers, will be discussed.

Bathke, C. G.; Jarvinen, G. D.; Wallace, R. K.; Ireland, J. R.; Johnson, M. W.; Sleaford, Brad W.; Ebbinghaus, B. B.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

2008-10-01T23:59:59.000Z

25

Absolute nuclear material assay  

DOE Patents (OSTI)

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

26

Management of Nuclear Materials  

Directives, Delegations, and Requirements

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 5660.1B.

2009-08-17T23:59:59.000Z

27

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

SciTech Connect

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

28

Management of Nuclear Materials  

Directives, Delegations, and Requirements

To establish requirements and procedures for the management of nuclear materials within the Department of Energy (DOE). Cancels DOE 5660.1A. Canceled by DOE O 410.2.

1994-05-26T23:59:59.000Z

29

Management of Nuclear Materials  

Directives, Delegations, and Requirements

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 410.2. Admin Chg 1 dated 4-10-2014, cancels DOE O 410.2.

2009-08-17T23:59:59.000Z

30

Nuclear Material Packaging Manual  

Directives, Delegations, and Requirements

The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered contamination barrier. No cancellation. Certified 11-18-10.

2008-03-07T23:59:59.000Z

31

A Continuous Automated Vault Inventory System (CAVIS) for accountability monitoring of stored nuclear materials  

SciTech Connect

Nearly all facilities that store hazardous (radioactive or non-radioactive) materials must comply with prevailing federal, state, and local laws. These laws usually have components that require periodic physical inspections to insure that all materials remain safely and securely stored. The inspections are generally labor intensive, slow, put personnel at risk, and only find anomalies after they have occurred. The system described in this paper was developed for monitoring stored nuclear materials resulting from weapons dismantlement, but its applications extend to any storage facility that meets the above criteria. The traditional special nuclear material (SNM) accountability programs, that are currently used within most of the Department of Energy (DOE) complex, require the physical entry of highly trained personnel into SNM storage vaults. This imposes the need for additional security measures, which typically mandate that extra security personnel be present while SNM inventories are performed. These requirements increase labor costs and put additional personnel at risk to radiation exposure. In some cases, individuals have received radiation exposure equivalent to the annual maximum during just one inventory verification. With increasing overhead costs, the current system is rapidly becoming too expensive to operate, the need for an automated method of inventory verification is evident. The Continuous Automated Vault Inventory System (CAVIS) described in this paper was designed and prototyped as a low cost, highly reliable, and user friendly system that is capable of providing, real-time weight, gamma. and neutron energy confirmation from each item stored in a SNM vault. This paper describes the sensor technologies, the CAVIS prototype system (built at Y- 12 for highly enriched uranium storage), the technical requirements that must be achieved to assure successful implementation, and descriptions of sensor technologies needed for a plutonium facility.

Pickett, C.A.; Barham, M.A.; Gafford, T.A.; Hutchinson, D.P.; Jordan, J.K.; Maxey, L.C.; Moran, B.W.; Muhs, J.; Nodine, R.; Simpson, M.L. [and others

1994-12-08T23:59:59.000Z

32

Special Nuclear Material Detection with a Water Cherenkov based Detector  

SciTech Connect

Fission events from Special Nuclear Material (SNM), such as highly enriched uranium or plutonium, produce a number of neutrons and high energy gamma-rays. Assuming the neutron multiplicity is approximately Poissonian with an average of 2 to 3, the observation of time correlations between these particles from a cargo container would constitute a robust signature of the presence of SNM inside. However, in order to be sensitive to the multiplicity, one would require a high total efficiency. There are two approaches to maximize the total efficiency; maximizing the detector efficiency or maximizing the detector solid angle coverage. The advanced detector group at LLNL is investigating one way to maximize the detector size. We are designing and building a water Cerenkov based gamma and neutron detector for the purpose of developing an efficient and cost effective way to deploy a large solid angle car wash style detector. We report on our progress in constructing a larger detector and also present preliminary results from our prototype detector that indicates detection of neutrons.

Sweany, M; Bernstein, A; Bowden, N; Dazeley, S; Svoboda, R

2008-11-10T23:59:59.000Z

33

Recommendations to the NRC on acceptable standard format and content for the Fundamental Nuclear Material Control (FNMC) Plan required for low-enriched uranium enrichment facilities  

SciTech Connect

A new section, 10 CFR 74.33, has been added to the material control and accounting (MC A) requirements of 10 CFR Part 74. This new section pertains to US Nuclear Regulatory Commission (NRC)-licensed uranium enrichment facilities that are authorized to produce and to possess more than one effective kilogram of special nuclear material (SNM) of low strategic significance. The new section is patterned after 10 CFR 74.31, which pertains to NRC licensees (other than production or utilization facilities licensed pursuant to 10 CFR Part 50 and 70 and waste disposal facilities) that are authorized to possess and use more than one effective kilogram of unencapsulated SNM of low strategic significance. Because enrichment facilities have the potential capability of producing SNM of moderate strategic significance and also strategic SNM, certain performance objectives and MC A system capabilities are required in 10 CFR 74.33 that are not contained in 10 CFR 74.31. This document recommends to the NRC information that the licensee or applicant should provide in the fundamental nuclear material control (FNMC) plan. This document also describes methods that should be acceptable for compliance with the general performance objectives. While this document is intended to cover various uranium enrichment technologies, the primary focus at this time is gas centrifuge and gaseous diffusion.

Moran, B.W.; Belew, W.L. (Oak Ridge K-25 Site, TN (United States)); Hammond, G.A.; Brenner, L.M. (21st Century Industries, Inc., Gaithersburg, MD (United States))

1991-11-01T23:59:59.000Z

34

Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data  

SciTech Connect

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

NONE

1995-07-14T23:59:59.000Z

35

Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management  

SciTech Connect

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

NONE

1995-07-14T23:59:59.000Z

36

Nuclear Resonance Fluorescence and Isotopic Mapping of Containers  

SciTech Connect

National security programs have expressed interest in developing systems to isotopically map shipping containers, fuel assemblies, and waste barrels for various materials including special nuclear material (SNM). Current radiographic systems offer little more than an ambiguous density silhouette of a container's contents. In this paper we will present a system being developed at LLNL to isotopically map containers using the nuclear resonance fluorescence (NRF) method. Recent experimental measurements on NRF strengths in SNM are discussed.

Johnson, M S; McNabb, D P

2008-08-08T23:59:59.000Z

37

A Neutron Based Interrogation System For SNM In Cargo  

SciTech Connect

A complete system has been simulated using experimentally obtained input parameters for the detection of special nuclear materials (SNM). A variation of the associated particle imaging (API) technique, referred to as reverse associated particle imaging detection (RAPID), has been developed in the context of detecting 5-kg spherical samples of U-235 in cargo. The RAPID technique allows for the interrogation of containers at neutron production rates between {approx}1x10{sup 8} neutrons/s and {approx}3x10{sup 8} neutrons/s. The merit of performance for the system is the time to detect the threat material with 95% probability of detection and 10{sup -4} false positive rate per interrogated voxel of cargo. Detection times of 5 minutes were found for a maximally loaded cargo container uniformly filled with iron and as low as 1 second in containers loaded to 1/4 of full capacity with either iron or wood. The worse case system performance, 30 minutes interrogation time, occurs for a maximally loaded container containing wood at 0.4 g/cm{sup 3}.

Kane, Steven Z.; Koltick, David S. [Purdue University, Physics Department, 525 Northwestern Avenue, W. Lafayette, IN 47907 (United States)

2011-06-01T23:59:59.000Z

38

A unified risk-Informed framework to assess the proliferation risk and license the proliferation performance of nuclear energy systems  

E-Print Network (OSTI)

In order to strengthen the current non-proliferation regime it is necessary to guarantee high standards of security for the sites that use, store, produce, or reprocess special nuclear materials (SNM). The current surge ...

Cavalieri d'Oro, Edoardo

2011-01-01T23:59:59.000Z

39

A Unified Risk-Informed Framework to Assess the Proliferation Risk and License the Proliferation Performace of Nuclear Energy  

E-Print Network (OSTI)

In order to strengthen the current non-proliferation regime it is necessary to guarantee high standards of security for the sites that use, store, produce, or reprocess special nuclear materials (SNM). The current surge ...

d'Oro, Edoardo Cavalieri

40

Nuclear Material Control and Accountability  

Directives, Delegations, and Requirements

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6. Admin Chg 1, 8-3-11.

2011-06-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Nuclear materials management storage study  

SciTech Connect

The Office of Weapons and Materials Planning (DP-27) requested the Planning Support Group (PSG) at the Savannah River Site to help coordinate a Departmental complex-wide nuclear materials storage study. This study will support the development of management strategies and plans until Defense Programs` Complex 21 is operational by DOE organizations that have direct interest/concerns about or responsibilities for nuclear material storage. They include the Materials Planning Division (DP-273) of DP-27, the Office of the Deputy Assistant Secretary for Facilities (DP-60), the Office of Weapons Complex Reconfiguration (DP-40), and other program areas, including Environmental Restoration and Waste Management (EM). To facilitate data collection, a questionnaire was developed and issued to nuclear materials custodian sites soliciting information on nuclear materials characteristics, storage plans, issues, etc. Sites were asked to functionally group materials identified in DOE Order 5660.1A (Management of Nuclear Materials) based on common physical and chemical characteristics and common material management strategies and to relate these groupings to Nuclear Materials Management Safeguards and Security (NMMSS) records. A database was constructed using 843 storage records from 70 responding sites. The database and an initial report summarizing storage issues were issued to participating Field Offices and DP-27 for comment. This report presents the background for the Storage Study and an initial, unclassified summary of storage issues and concerns identified by the sites.

Becker, G.W. Jr.

1994-02-01T23:59:59.000Z

42

Computational Age Dating of Special Nuclear Materials  

SciTech Connect

This slide-show presented an overview of the Constrained Progressive Reversal (CPR) method for computing decays, age dating, and spoof detecting. The CPR method is: Capable of temporal profiling a SNM sample; Precise (compared with known decay code, such a ORIGEN); Easy (for computer implementation and analysis). ? We have illustrated with real SNM data using CPR for age dating and spoof detection. If SNM is pure, may use CPR to derive its age. If SNM is mixed, CPR will indicate that it is mixed or spoofed.

None

2012-06-30T23:59:59.000Z

43

Nuclear Material Control and Accountability  

Directives, Delegations, and Requirements

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Cancels: DOE M 474.1-1B DOE M 474.1-2A

2005-08-26T23:59:59.000Z

44

Nuclear Material Control and Accountability  

Directives, Delegations, and Requirements

The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Chg 1, dated 8-14-06. Canceled by DOE O 474.2.

2005-08-26T23:59:59.000Z

45

Nuclear Material Control and Accountability  

Directives, Delegations, and Requirements

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6, Admin Chg 1, 8-26-05. Admin Chg 2, dated 11-19-12, cancels DOE M 474.2 Admin Chg 1.

2011-06-27T23:59:59.000Z

46

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

clandestine material with nuclear resonance fluorescence.E. Norman, UC Berkeley Dept. of Nuclear Engineering, privatepp. 349. G. Warren et al. Nuclear Resonance Fluorescence of

Quiter, Brian

2010-01-01T23:59:59.000Z

47

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

48

UNITED STATES NUCLEAR REGULATORY COMMISSION  

Office of Legacy Management (LM)

WASHINGTON, 0. C. 20555 WASHINGTON, 0. C. 20555 AUG i 3 1979 ,,~---Y--*. FCAF:Wi3 )I 70-364 : i: SNM-414,jAmendment No. 3 --A Babcock and Wilcox Company Nuclear Materials Division ATTN: Mr. Michael A. Austin Manager, Technical Control 609 North Warren Avenue Apollo, Pennsylvania 15613 Gentiemen: (1 i' \ (. \ In accordance with your application dated June 18, 1979, and pursuant to Title 10, Code of Federal Regulations, Part 70, Materials License SNM-414 is hereby amended to: 1. Delete the function of the Regulatory Projects Coordinator, and 2. Alter the experience requirements for the function of Licensing and Nuclear Safety Specialist. Replacement pages for the license and condition section of the application are attached. Included are changes to License SNM-414 pages to reflect

49

Exporting automatic vehicle SNM monitoring technology  

SciTech Connect

Controlling the transportation of nuclear materials is still one of the most effective nuclear proliferation barriers. The recent increase of global nuclear material proliferation has expanded the application of vehicle monitor technology to prevent the diversion of special nuclear material across international borders. To satisfy this new application, a high-sensitivity vehicle monitor, which is easy to install and capable of operating in high-traffic areas, is required. A study of a new detector configuration for a drive-through vehicle monitor is discussed in this paper.

York, R.L.; Fehlau, P.E.; Close, D.A.

1995-10-01T23:59:59.000Z

50

Cleanup Contractor Achieves 'Elite' Nuclear Material Accountability...  

Energy Savers (EERE)

Cleanup Contractor Achieves 'Elite' Nuclear Material Accountability Status Cleanup Contractor Achieves 'Elite' Nuclear Material Accountability Status September 30, 2014 - 12:00pm...

51

Transportation of Nuclear Materials | Department of Energy  

Energy Savers (EERE)

Transportation of Nuclear Materials Transportation of Nuclear Materials GC-52 provides legal advice to DOE on legal and regulatory requirements and standards for transportation of...

52

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site  

SciTech Connect

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

NONE

1995-06-01T23:59:59.000Z

53

Nuclear Materials Disposition | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Spent Nuclear Fuel Spent nuclear fuel (SNF) is fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. SNF may include: (1) intact, non-defective fuel assemblies or fuel rods; (2) failed fuel assemblies or fuel rods; (3) segments of fuel rods or pieces of fuel derived from spent fuel rods; and

54

Material control and accountability alternatives  

SciTech Connect

Department of Energy and Nuclear Regulatory Commission regulations governing material control and accountability in nuclear facilities have become more restrictive in the past decade, especially in areas that address the insider threat. As the insider threat receives greater credibility, regulations have been strengthened to increase the probability of detecting insider activity and to prevent removal of a significant quantity of Special Nuclear Material (SNM) from areas under control of the protective force.

NONE

1991-08-12T23:59:59.000Z

55

The role of SNM portal monitoring in the Russian MPC & A program  

SciTech Connect

Controlling the movement of nuclear materials is still the most effective nonproliferation measure. Pedestrian and vehicle portal monitors have been an established tool for preventing the unauthorized movement of SNM across US nuclear facility boundaries for 15 years. Because the portals are reliable and easy to install, they are an efficient first step to improve the security at Russian nuclear facilities. The portals were first furnished to Russian facilities for testing and evaluation. After Russian technical experts gained experience with the operating parameters, the instruments were implemented at appropriate locations at each facility. This process has been executed at IPPE, VNIEF, VNIITF, RCC KI, and SKhK. The transfer of the portal monitoring technology to Russian institutes to promote the manufacture of Russian instruments is also an important goal of the program. The process was started with two portal monitor workshops attended by representatives of Russian facilities at ORNL and followed by technical collaborations at the individual Russian facilities. The success of this effort is illustrated by the recent workshop hosted by VNIIA at the SCI in Obninsk where specialists from thirty-two Russian nuclear facilities met to discuss their experience in portal monitoring. Twelve institutes and firms reported on the status of Russian designed and manufactured instruments. Details of this program will be presented in this paper.

York, R.L.

1997-05-01T23:59:59.000Z

56

Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section A report, existing conditions calculations/supporting information  

SciTech Connect

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. Based upon US Department of Energy (DOE) Albuquerque Operations (DOE/Al) Office and LANL projections, storage space limitations/restrictions will begin to affect LANL`s ability to meet its missions between 1998 and 2002.

NONE

1995-07-14T23:59:59.000Z

57

Materials Challenges in Nuclear Energy  

SciTech Connect

Nuclear power currently provides about 13% of the worldwide electrical power, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light water reactors are reviewed. The materials degradation issues for the Zr alloy clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants is discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are 5 key bulk radiation degradation effects (low temperature radiation hardening and embrittlement, radiation-induced and modified solute segregation and phase stability, irradiation creep, void swelling, and high temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials.

Zinkle, Steven J [ORNL] [ORNL; Was, Gary [University of Michigan] [University of Michigan

2013-01-01T23:59:59.000Z

58

The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios  

SciTech Connect

This paper is an extension to earlier studies1,2 that examined the attractiveness of materials mixtures containing special nuclear materials (SNM) and alternate nuclear materials (ANM) associated with the PUREX, UREX, COEX, THOREX, and PYROX reprocessing schemes. This study extends the figure of merit (FOM) for evaluating attractiveness to cover a broad range of proliferant state and sub-national group capabilities. The primary conclusion of this study is that all fissile material needs to be rigorously safeguarded to detect diversion by a state and provided the highest levels of physical protection to prevent theft by sub-national groups; no silver bullet has been found that will permit the relaxation of current international safeguards or national physical security protection levels. This series of studies has been performed at the request of the United States Department of Energy (DOE) and is based on the calculation of "attractiveness levels" that are expressed in terms consistent with, but normally reserved for nuclear materials in DOE nuclear facilities.3 The expanded methodology and updated findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security are discussed.

Bathke, C. G.; Wallace, R. K.; Ireland, J. R.; Johnson, M. W.; Hase, Kevin R.; Jarvinen, G. D.; Ebbinghaus, B. B.; Sleaford, Brad W.; Bradley, Keith S.; Collins, Brian A.; Smith, Brian W.; Prichard, Andrew W.

2010-09-01T23:59:59.000Z

59

Responsible stewardship of nuclear materials  

SciTech Connect

The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful.

Hannum, W.H.

1994-10-01T23:59:59.000Z

60

Nuclear Material Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1194-2011 JUNE 2011 ──────────────── CHANGE NOTICE NO.2 DECEMBER 2012 ──────────────── CHANGE NOTICE NO.3 OCTOBER 2013 DOE STANDARD NUCLEAR MATERIALS CONTROL AND ACCOUNTABILITY U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ATTACHMENT 1 Change Notice No. 3 DOE -STD-1194-2011 October 2013 Nuclear Materials Control and Accountability Table of Changes Page/Section Change Page 57/Section 6.4.4.1. Change from, - Accounting records and source documents shall include item identification, material type, form, quantity, location, gross

Note: This page contains sample records for the topic "nuclear material snm" 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

Preventing Proliferation of Nuclear Materials and Technology...  

National Nuclear Security Administration (NNSA)

Preventing Proliferation of Nuclear Materials and Technology | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile...

62

Liquefied Noble Gas (LNG) detectors for detection of nuclear materials  

Science Journals Connector (OSTI)

Liquefied-noble-gas (LNG) detectors offer, in principle, very good energy resolution for both neutrons and gamma rays, fast response time (hence high-count-rate capabilities), excellent discrimination between neutrons and gamma rays, and scalability to large volumes. They do, however, need cryogenics. LNG detectors in sizes of interest for fissionable material detection in cargo are reaching a certain level of maturity because of the ongoing extensive R&}D effort in high-energy physics regarding their use in the search for dark matter and neutrinoless double beta decay. The unique properties of LNG detectors, especially those using Liquid Argon (LAr) and Liquid Xenon (LXe), call for a study to determine their suitability for Non-Intrusive Inspection (NII) for Special Nuclear Materials (SNM) and possibly for other threats in cargo. Rapiscan Systems Laboratory, Yale University Physics Department, and Adelphi Technology are collaborating in the investigation of the suitability of LAr as a scintillation material for large size inspection systems for air and maritime containers and trucks. This program studies their suitability for NII, determines their potential uses, determines what improvements in performance they offer and recommends changes to their design to further enhance their suitability. An existing 3.1 liter LAr detector (microCLEAN) at Yale University, developed for R&}D on the detection of weakly interacting massive particles (WIMPs) was employed for testing. A larger version of this detector (15 liters), more suitable for the detection of higher energy gamma rays and neutrons is being built for experimental evaluation. Results of measurements and simulations of gamma ray and neutron detection in microCLEAN and a larger detector (326 liter CL38) are presented.

J A Nikkel; T Gozani; C Brown; J Kwong; D N McKinsey; Y Shin; S Kane; C Gary; M Firestone

2012-01-01T23:59:59.000Z

63

Application of Wald's sequential probability ratio test to nuclear materials control  

SciTech Connect

We have replaced traditional analysis methods for nuclear material control monitoring with hypothesis testing, specifically with Wald's sequential-probability-ratio test. Our evaluation of Walds'd method, applied in both vehicle and pedestrian SNM monitors, is by Monte Carlo calculation to determine the alarm probability and average monitoring times of the monitors. The vehicle monitor with Wald's test has a much shorter monitoring delay than with traditional methods, without serious compensating changes in operating characteristics. The pedestrian monitor with Wald's method also has advantages over traditional single-interval test, in that the Wald method duplicates the advantages of a moving-average technique. We verified the Monte Carlo calculations for the pedestrian monitor by means of a special program for the monitor's microprocessor controller. The observations of false-alarm probability and average monitoring time for over 500,000 tests verified the Monte Carlo results.

Fehlau, P.E.; Coop, K.L.; Markin, J.T.

1984-01-01T23:59:59.000Z

64

Nuclear Materials Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

JUNE 2011 JUNE 2011 ──────────────── CHANGE NOTICE NO.1 AUGUST 2011 DOE STANDARD NUCLEAR MATERIALS CONTROL AND ACCOUNTABILITY U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ATTACHMENT 1 Change Notice No. 1 DOE -STD-1194-2011 August 2011 Nuclear Materials Control and Accountability Table of Changes Page/Section Change Title Page Formatting and font size adjusted. Page 2/Section 4.h. Reference to document was updated from DOE M 470.4-1 Chg 2, Safeguards and Security Program Planning and Management, dated 10-2-10 to DOE O 470.4B, Safeguards and Security Program, dated 7-21-11. Page 2/Section 4.i. Reference to document was updated from DOE M

65

Nuclear Materials Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

June 2011 June 2011 DOE STANDARD Nuclear Materials Control and Accountability U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1194-2011 i This page is intentionally left blank. DOE-STD-1194-2011 ii TABLE OF CONTENTS FOREWORD ..................................................................................................................................................................................... iii 1 . S C O P E ........................................................................................................................................................................................... 1 2

66

material consolidation | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

of Material Consolidation and Civilian Sites (MCCS) is responsible for three key nuclear nonproliferation initiatives.Material Protection, Control, and Accounting (MPC&A) Upgrades:...

67

weapons material protection | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

weapons material protection | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

68

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:...

69

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

to learn MCNPX and nuclear safeguards, Bill B. , Steve K. ,Introduction 1.1 Nuclear Safeguards . . . . . . . . . . . .Programme to IAEA Safeguards. STUK-YTO-TR 170. Helsinki

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

70

GTRI's Nuclear and Radiological Material Protection | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Protection | National Nuclear Protection | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog GTRI's Nuclear and Radiological Material Protection Home > About Us > Our Programs > Nonproliferation > Global Threat Reduction Initiative > GTRI's Nuclear and Radiological Material Protection GTRI's Nuclear and Radiological Material Protection

71

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

72

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

73

Tags and seals for controling nuclear materials, Arms control and nonproliferation technologies. Second quarter 1993  

SciTech Connect

This issue of Arms Control and Nonproliferation Technologies summarizes demonstrations and addresses related topics. The first article, ``Basic Nuclear Material Control and Accountability Concepts as Might be Applied to the Uranium from the US-Russian HEU Purchase,`` describes safeguards sybsystems necessary for effective nuclear material safeguards. It also presents a general discussion on HEU-to-low-enrichment uranium (LEU) commingling processes and suggests applicable key measurement points. The second article, ``A Framework for Evaluating Tamper-Indicating-Device Technologies (TIDs),`` describes their uses, proper selection, and evaluation. The final three articles discuss the tags and seals applications and general characteristics of several nuclear material containers: the Type 30B uranium hexafluoride container, the AT-400R container, and the DOT Specification 6M container for SNM. Finally, the Appendix displays short descriptions and illustrations of seven tags and seals, including: the E-cup and wire seal, the python seal, the secure loop inspectable tag/seal (SLITS), bolt-and-loop type electronic identification devices, and the shrink-wrap seal.

Staehle, G; Talaber, C; Stull, S; Moulthrop, P [eds.

1993-12-31T23:59:59.000Z

74

Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

The order prescribes DOE minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission {NRC). Cancels DOE O 5633.3. Canceled by DOE O 5633.3B.

1993-02-12T23:59:59.000Z

75

Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

DOE O 474.1 prescribes Department of Energy (DOE) requirements for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission (NRC). Cancels DOE 5633.3B

1999-08-11T23:59:59.000Z

76

Nuclear Engineering Division Irradiated Materials Laboratory  

E-Print Network (OSTI)

Nuclear Engineering Division Irradiated Materials Laboratory The Irradiated Materials Laboratory (IML) in Argonne's Nuclear Engineering Division is used to conduct research on the behavior. #12;C O N TA C T > Dr. Michael C. Billone | 630-252-7146 | billone@anl.gov | Nuclear Engineering

Kemner, Ken

77

Fissile Materials Disposition | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Fissile Materials Disposition | National Nuclear Security Administration Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Fissile Materials Disposition Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition Fissile Materials Disposition Since the end of the Cold War, significant quantities of plutonium and

78

International Materials Protection and Cooperation | National Nuclear  

National Nuclear Security Administration (NNSA)

Materials Protection and Cooperation | National Nuclear Materials Protection and Cooperation | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog International Materials Protection and Cooperation Home > About Us > Our Programs > Nonproliferation > International Materials Protection and Cooperation International Materials Protection and Cooperation

79

Optimizing Inspection Parameters for Long Stand-Off Detection of SNM  

SciTech Connect

Detection of special nuclear material (SNM) at extended ranges (>100 m) through the utilization of high energy (>20 MeV) bremsstrahlung photons requires optimizing the structure and interrelation of irradiation (beam-on) and detection (counting) periods. Conventional inspection schemes at lower energies and smaller distances primarily operate by pulsing an accelerator at frequencies of 0.1-1 kHz while collecting emitted radiation from the target under inspection for the few milliseconds in between pulses. Simulation and experimental results for long stand-off scenarios with source photons >20 MeV, however, indicate that two primary phenomena--(1) induced photoneutrons in proximity to the accelerator and (2) beam induced activation of air and soil--preclude the use of conventional inspection schemes. By considering the time structure and magnitude of the beam-induced photon and neutron backgrounds, signals of interest from the target, and natural backgrounds, inspection schemes have been developed to maximize signal to noise ratios (SNR). Analysis of the data indicates that the highest SNR values are found with short (2-5 s) irradiations followed by a 1-2 s period of collecting emitted neutron and photon signatures.

Johnson, Erik; Blackburn, Brandon; Hynes, Michael [Raytheon Integrated Defense Systems, 50 Apple Hill Drive, Tewksbury, MA 01876 (United States); Hausladen, Paul [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831 (United States)

2011-12-13T23:59:59.000Z

80

SNM neutron detection using a time-gated synthetic aperture hybrid approach  

SciTech Connect

This work focuses on using forward and adjoint transport in a hybrid application of 3-D deterministic (PENTRAN) and Monte Carlo (MCNP5) codes to model a series of neutron detector blocks. These blocks, or 'channels, ' contain a unique set of moderators with 4 atm He-3 detectors tuned to detect and profile a gross energy spectrum of a passing neutron (SNM) source. Ganging the units together as a large area system enables one to apply time gating the source-detector response to maximize signal to noise responses from a passing source with minimal background; multiple units may be positioned as a collective synthetic aperture detector array to be used as a way of performing real time neutron spectroscopy for detecting special nuclear materials in moving vehicles. The initial design, detector response coupling, confirmation of initial design functionality using adjoint transport calculations, and realistic simulation using PENTRAN and MCNP5 are presented. Future work will include optimization and application to realistic scenarios and additional sources. (authors)

Molinar, M.; Yi, C.; Edgar, C. A.; Manalo, K.; Chin, M.; Sjoden, G. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State Street, Atlanta GA 30332-0745 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

To prescribe Department of Energy (DOE) requirements, including those for the National Nuclear Security Administration (NNSA), for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission (NRC). DOE N 251.60, dated 11-19-04, extends this directive until 11-19-05. Cancels DOE O 474.1.

2000-11-20T23:59:59.000Z

82

Material Control & Accountability | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Control & Accountability | National Nuclear Security Control & Accountability | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Material Control & Accountability Home > About Us > Our Programs > Nuclear Security > Material Control & Accountability Material Control & Accountability Safeguards First Principles Initiative

83

Material Control & Accountability | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Control & Accountability | National Nuclear Security Control & Accountability | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Material Control & Accountability Home > About Us > Our Programs > Nuclear Security > Material Control & Accountability Material Control & Accountability Safeguards First Principles Initiative

84

UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number:...

85

NNSA: Securing Domestic Radioactive Material | National Nuclear...  

National Nuclear Security Administration (NNSA)

2011 In April 2009, President Obama outlined an ambitious agenda to secure vulnerable nuclear material around the world within four years, calling the danger of a terrorist...

86

Y-12 Removes Nuclear Materials from Two Facilities to Reduce...  

National Nuclear Security Administration (NNSA)

Removes Nuclear Materials from Two Facilities to Reduce Site's Nuclear Footprint (Alpha 5 and 9720-38 No Longer Designated as Nuclear Facilities) | National Nuclear Security...

87

Nuclear Materials Management and Safeguards System (NMMSS)  

SciTech Connect

This paper describes the Nuclear Materials Management and Safeguards System (NMMSS) which is sponsored by the Department of Energy and the Nuclear Regulatory Commission. The system serves national security and program management interests, and international interests in the programs for the peaceful application of nuclear energy and non-proliferation of nuclear weapons. Within the scope of the NMMSS are found all nuclear materials applied and controlled under United States law and related international agreements, including U.S. nuclear materials production programs and US private nuclear industrial activities. In addition, its national and international scope enables it to provide services to other organizations such as the Arms Control and Disarmament Agency, the Department of State, and the US Congress.

Jacobsen, S.E.; Matthews, W.B. III; McKamy, E.D.; Pedigo, R.B.

1991-01-01T23:59:59.000Z

88

Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

To prescribe the Department of Energy (DOE) minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE O 5633.2A and DOE O 5633.3A. Canceled by DOE O 474.1

1994-09-07T23:59:59.000Z

89

Nuclear Material Recovery | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

nuclear material domestically and internationally is one part of Y-12's nuclear nonproliferation business. Miscellaneous scrap material is a diverse group of scrap materials...

90

UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

Nuclear Materials Management & Safeguards System Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number: Project Title: Associated Materials: Programmatic RIS Previous Project Number(s) Status Code Allotment Code (S=Supplier, U=User) I authorize that the information listed above is for the NMMSS Program to use as part of the project number conversion process for this facility.

91

Materials in space nuclear power systems  

SciTech Connect

Man's presence in space has been limited by the availability of reliable lightweight sources of power. Over the course of the last 30 years, a variety of space nuclear power systems have been designed and, in some cases, built and flown. Although a number of technology issues effect the overall performance of these systems, technical issues associated with the materials of construction have most often been a major limitation in obtaining the desired system performance goals. This paper will review selected materials limitations associated with the three major nuclear power systems being considered at this time: radioisotope power, nuclear power, and nuclear propulsion systems.

Cooper, R.H.; Moore, J.P.

1991-01-01T23:59:59.000Z

92

Nuclear materials stewardship: Our enduring mission  

SciTech Connect

The US Department of Energy (DOE) and its predecessors have handled a remarkably wide variety of nuclear materials over the past 50 yr. Two fundamental changes have occurred that shape the current landscape regarding nuclear materials. If one recognizes the implications and opportunities, one sees that the stewardship of nuclear materials will be a fundamental and important job of the DOE for the foreseeable future. The first change--the breakup of the Soviet Union and the resulting end to the nuclear arms race--altered US objectives. Previously, the focus was on materials production, weapon design, nuclear testing, and stockpile enhancements. Now the attention is on dismantlement of weapons, excess special nuclear material inventories, accompanying increased concern over the protection afforded to such materials; new arms control measures; and importantly, maintenance of the safety and reliability of the remaining arsenal without testing. The second change was the raised consciousness and sense of responsibility for dealing with the environmental legacies of past nuclear arms programs. Recognition of the need to clean up radioactive contamination, manage the wastes, conduct current operations responsibly, and restore the environment have led to the establishment of what is now the largest program in the DOE. Two additional features add to the challenge and drive the need for recognition of nuclear materials stewardship as a fundamental, enduring, and compelling mission of the DOE. The first is the extraordinary time frames. No matter what the future of nuclear weapons and no matter what the future of nuclear power, the DOE will be responsible for most of the country`s nuclear materials and wastes for generations. Even if the Yucca Mountain program is successful and on schedule, it will last more than 100 yr. Second, the use, management, and disposition of nuclear materials and wastes affect a variety of nationally important and diverse objectives, from national security to the future of nuclear power in this country and abroad, to the care of the environment. Sometimes these objectives are in concert, but often they are seen as competing or being in conflict. By recognizing the corporate responsibility for these materials and the accompanying programs, national decision making will be improved.

Isaacs, T.H. [Lawrence Livermore National Lab., CA (United States)

1998-12-31T23:59:59.000Z

93

Global nuclear material flow/control model  

SciTech Connect

This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The nuclear danger can be reduced by a system for global management, protection, control, and accounting as part of an international regime for nuclear materials. The development of an international fissile material management and control regime requires conceptual research supported by an analytical and modeling tool which treats the nuclear fuel cycle as a complete system. The prototype model developed visually represents the fundamental data, information, and capabilities related to the nuclear fuel cycle in a framework supportive of national or an international perspective. This includes an assessment of the global distribution of military and civilian fissile material inventories, a representation of the proliferation pertinent physical processes, facility specific geographic identification, and the capability to estimate resource requirements for the management and control of nuclear material. The model establishes the foundation for evaluating the global production, disposition, and safeguards and security requirements for fissile nuclear material and supports the development of other pertinent algorithmic capabilities necessary to undertake further global nuclear material related studies.

Dreicer, J.S.; Rutherford, D.S.; Fasel, P.K.; Riese, J.M.

1997-10-01T23:59:59.000Z

94

Nuclear Concrete Materials Database Phase I Development  

SciTech Connect

The FY 2011 accomplishments in Phase I development of the Nuclear Concrete Materials Database to support the Light Water Reactor Sustainability Program are summarized. The database has been developed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In this Phase I development, the database has been successfully designed and constructed to manage documents in the Portable Document Format generated from the Structural Materials Handbook that contains nuclear concrete materials data and related information. The completion of the Phase I database has established a solid foundation for Phase II development, in which a digital database will be designed and constructed to manage nuclear concrete materials data in various digitized formats to facilitate electronic and mathematical processing for analysis, modeling, and design applications.

Ren, Weiju [ORNL; Naus, Dan J [ORNL

2012-05-01T23:59:59.000Z

95

Fundamentals of materials accounting for nuclear safeguards  

SciTech Connect

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

96

Counterproliferation of nuclear raw materials. Study project  

SciTech Connect

In light of the ongoing INF and START I agreements and the pending ratification of the START II agreement, the quantities of nuclear-weapon-usable `fissile` materials from the former USSR will expand drastically. Some newly rich rogue oil states and terrorist groups with anti-U.S. sentiments may attempt to procure fissile materials in order to manufacture nuclear weapons. This project will explore the scope of the fissile material proliferation problem, describe a number of recent cases where fissile material was illegally diverted, and discuss the U.S. policies, methods and means available to halt or reduce the spread of weapons-usable nuclear material. Finally, it provides recommendations for improvements in the U.S. program and for areas meriting further study.

Sanders, R.L.

1996-02-26T23:59:59.000Z

97

Fusion & Materials for Nuclear Systems Division | ornl.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

Fusion & Materials for Nuclear Systems SHARE Fusion & Materials for Nuclear Systems Division Fusion holds the promise of significant power with no carbon emissions and minimal...

98

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Summary-1995.html[6/27/2011 12:50:20 PM] Summary-1995.html[6/27/2011 12:50:20 PM] SUMMARY The Atomic Energy Commission (AEC), a predecessor agency of the Department of Energy (DOE), established the Savannah River Site (SRS) in the early 1950s for the production of special radioactive isotopes. The primary SRS mission was to produce strategic isotopes (plutonium-239 and tritium) used in the development and production of nuclear weapons for national defense. The Site produced other special isotopes (californium-252, plutonium-238, americium-241, etc.) to support research in nuclear medicine, space exploration, and commercial applications. The historic production cycle at the SRS involved the fabrication of metal fuel and target assemblies for irradiation in the Site reactors, followed by chemical dissolution, separation, and conversion of the radioisotopes into solid forms for use

99

Calibrating the Jomar JPM-22 pedestrian SNM monitor  

SciTech Connect

The Jomar JPM-22 is a commercial version of a portal monitor developed at Los Alamos. The monitor operates as a walk-through or wait-in SNM monitor. This manual describes how to calibrate the monitor's detection system and how to set its operating parameters for walk-through or wait-in operation. 4 figs., 2 tabs.

Fehlau, P.E.

1989-08-01T23:59:59.000Z

100

Materials Research Needs for Near-Term Nuclear Reactors  

Science Journals Connector (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Material

John R. Weeks

Note: This page contains sample records for the topic "nuclear material snm" 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.


101

Technologies for detection of nuclear materials  

SciTech Connect

Detection of smuggled nuclear materials at transit points requires monitoring unknown samples in large closed packages. This review contends that high-confidence nuclear-material detection requires induced fission as the primary mechanism, with passive radiation screening in a complementary role. With the right equipment, even small quantities of nuclear materials are detectable with a high probability at transit points. The equipment could also be linked synergistically with detectors of other contrabond. For screening postal mail and packages, passive monitors are probably more cost-effective. When a suspicious item is detected, a single active probe could then be used. Until active systems become mass produced, this two-stage screening/interrogation role for active/passive equipment is more economic for cargo at border crossings. For widespread monitoring of nuclear smuggling, it will probably be necessary to develop a system for simultaneously detecting most categories of contraband, including explosives and illicit drugs. With control of nuclear materials at known storage sites being the first line of defense, detection capabilities at international borders could establish a viable second line of defense against smuggling.

DeVolpi, A.

1996-03-30T23:59:59.000Z

102

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

Heubeck, N.B.

1998-09-08T23:59:59.000Z

103

National and international nuclear material monitoring  

SciTech Connect

The status of nuclear materials in both the U.S. and Former Soviet Union is changing based upon the execution of agreements relative to weapons materials production and weapon dismantlement. The result of these activities is that a considerably different emphasis is being placed on how nuclear materials are viewed and utilized. Even though much effort is being expended on the final disposition of these materials, the interim need for storage and security of the material is increasing. Both safety and security requirements exist to govern activities when these materials are placed in storage. These requirements are intended to provide confidence that the material is not being misused and that the storage operations are conducted safely. Both of these goals can be significantly enhanced if technological monitoring of the material is performed. This paper will briefly discuss the traditional manual methods of U.S. and international material monitoring and then present approaches and technology that are available to achieve the same goals under the evolving environment.

Waddoups, I.G.

1996-07-01T23:59:59.000Z

104

Nuclear Materials: Reconsidering Wastes and Assets - 13193  

SciTech Connect

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

Michalske, T.A. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

105

Transportation Security Rulemaking Activities at the U.S. Nuclear Regulatory Commission  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

AT THE AT THE U.S. NUCLEAR REGULATORY COMMISSION R. Clyde Ragland, P.E. Office of Nuclear Security and Incident Response 2011 DOE National Transportation Stakeholders Forum May 11, 2011 2 NRC Focus Prior to September 11, 2001 * Historically, NRC Transportation Security Regulations Focused on Highest Risk Radioactive Material, consisted of Special Nuclear Material (SNM) and Spent Nuclear Fuel (SNF) NRC Actions Since September 11, 2001 * Domestically, reviewed materials transported by NRC licensees and re- evaluated security requirements considering: - applicable threats to shipments - material considerations - magnitude of adverse consequences * Internationally, participated in the development of the IAEA Code of Conduct on the Safety and Security of Radioactive

106

Nuclear Resonance Fluorescence for Materials Assay  

SciTech Connect

This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX?s photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

Quiter, Brian J.; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

2009-06-29T23:59:59.000Z

107

Nuclear Resonance Fluorescence for Materials Assay  

SciTech Connect

This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX's photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

Quiter, Brian; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

2009-06-05T23:59:59.000Z

108

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

nuclear forensics, and safeguards for nuclear fuel cyclesIndex TermsNuclear Safeguards, non-destructive analysis,radiological source, nuclear safeguards including measuring

Quiter, Brian

2010-01-01T23:59:59.000Z

109

Assessment tool for nuclear material acquisition pathways  

E-Print Network (OSTI)

be obtained. The two types of material used in nuclear weapons are Highly Enriched Uranium (HEU) and Plutonium (Pu). Uranium is an element found in nature and is contained in the soil all over the world. However, certain geological formations contain a... (LEU) portion of the network ..................................... 22 Figure 11 Last seciton of the Pu (LEU) portion of the network...................................... 23 Figure 12 Plutonium Section of the Network produced via Natural Uranium...

Ford, David Grant

2009-05-15T23:59:59.000Z

110

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

National Nuclear Security Administration (NNSA)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

111

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

NLE Websites -- All DOE Office Websites (Extended Search)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

112

Nuclear Fuels & Materials Spotlight Volume 4  

SciTech Connect

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: The first identification of silver and palladium migrating through the SiC layer in TRISO fuel A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension Results of high-temperature safety testing on coated particle fuels irradiated in the ATR New methods for testing the integrity of irradiated plate-type reactor fuel Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

2014-04-01T23:59:59.000Z

113

Manual for Control And Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

DOE M 474.1-1 prescribes Department of Energy (DOE) requirements and procedures for nuclear material control and accountability (MC&A). This Manual supplements DOE O 474.1, Control and Accountability of Nuclear Materials.

1999-08-11T23:59:59.000Z

114

Spent Nuclear Fuel Self-Induced XRF to Predict Pu to U Content  

E-Print Network (OSTI)

area of interest, would improve input accountability and shipper/receiver differences. XRF measurements were made on individual PWR fuel rods with varying fuel ages and final burn-ups at Oak Ridge National Laboratory (ORNL) in July 2008 and January... Committee NRF Nuclear Resonance Fluorescence viii ORNL Oak Ridge National Laboratory Pu Plutonium PUREX Plutonium and Uranium Recovery by Extraction PWR Pressurized Water Reactor RPP Reprocessing Plant SNM Special Nuclear Material...

Stafford, Alissa Sarah

2010-10-12T23:59:59.000Z

115

Evaluation of special nuclear material monitoring instruments  

SciTech Connect

A statistical method to protect against the loss of strategic special nuclear material (SSNM) is presented. A simplified step by step approach to the test procedure is described. Strategic special nuclear material (SSNM) is protected using several layers of physical and administrative controls. In a facility having both enriched and depleted uranium, extensive control is exercised to prevent a diversion of the SSNM, but assurance must also be provided that depleted material is not being removed inasmuch as its low would indicate the possible loss of SSNM through surreptitious substitution. One option for identifying loss of material is to place walkthrough monitors at the pedestrian exits leaving the perimeter of the security boundary enclosing the uranium processing area. Within this security perimeter are the SSNM areas having tight control and restricted access. The monitors for the SSNM are within buildings and are in the benign environment of a working area. Perimeter monitors on the other hand are located at the boundary rotogates and are subject to the ambient conditions varying with the seasons.

Bowman, K.O. (Oak Ridge National Lab., TN (USA). Mathematical Sciences Section); Wallace, S.A. (Oak Ridge Y-12 Plant, TN (USA))

1990-02-01T23:59:59.000Z

116

Safeguards for nuclear material transparency monitoring  

SciTech Connect

The US and the Russian Federation are currently engaged in negotiating or implementing several nuclear arms and nuclear material control agreements. These involve placing nuclear material in specially designed containers within controlled facilities. Some of the agreements require the removal of nuclear components from stockpile weapons. These components are placed in steel containers that are then sealed and tagged. Current strategies for monitoring the agreements involve taking neutron and gamma radiation measurements of components in their containers to monitor the presence, mass, and composition of plutonium or highly enriched uranium, as well as other attributes that indicate the use of the material in a weapon. If accurate enough to be useful, these measurements will yield data containing information about the design of the weapon being monitored. In each case, the design data are considered sensitive by one or both parties to the agreement. To prevent the disclosure of this information in a bilateral or trilateral inspection scenario, so-called information barriers have evolved. These barriers combine hardware, software, and procedural safeguards to contain the sensitive data within a protected volume, presenting to the inspector only the processed results needed for verification. Interlocks and volatile memory guard against disclosure in case of failure. Implementing these safeguards requires innovation in radiation measurement instruments and data security. Demonstrating their reliability requires independent testing to uncover any flaws in design. This study discusses the general problem and gives a proposed solution for a high resolution gamma ray detection system. It uses historical examples to illustrate the evolution of other successful systems.

MacArthur, D A; Wolford, J K

1999-06-02T23:59:59.000Z

117

United States Department of Energy Nuclear Materials Stewardship  

SciTech Connect

The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on the progress of the Nuclear Materials Stewardship Initiative in evaluating and implementing these opportunities, and the remaining challenges in integrating the long-term management of nuclear materials.

Newton, J. W.

2002-02-27T23:59:59.000Z

118

Implementation Plan and Initial Development of Nuclear Concrete Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program The FY10 activities for development of a nuclear concrete materials database to support the Light Water Reactor Sustainability Program are summarized. The database will be designed and constructed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

119

Implementation Plan and Initial Development of Nuclear Concrete Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program The FY10 activities for development of a nuclear concrete materials database to support the Light Water Reactor Sustainability Program are summarized. The database will be designed and constructed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

120

E-Print Network 3.0 - active snm detection Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

- database Duplicate detection, entity resolution... ordered) JCDL 2007 12;2 Conference Name Here 7 Sorted Neighborhood Method (SNM) classical method simple... window sizes...

Note: This page contains sample records for the topic "nuclear material snm" 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

SRS - Programs - H Area Nuclear Materials Disposition  

NLE Websites -- All DOE Office Websites (Extended Search)

H Area Nuclear Materials Disposition H Area Nuclear Materials Disposition The primary mission of the H-Canyon Complex is to dissolve, purify and blend-down surplus highly enriched uranium (HEU) and aluminum-clad foreign and domestic research reactor fuel to produce a low enriched uranium (LEU) solution suitable for conversion to commercial reactor fuel. A secondary mission for H-Canyon is to dissolve excess plutonium (Pu) not suitable for MOX and transfer it for vitrification in the Defense Waste Processing Facility at SRS. H Canyon was constructed in the early 1950s and began operations in 1955. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains the process vessels. It is approximately 1,000 feet long with several levels to accommodate the various stages of material stabilization, including control rooms to monitor overall equipment and operating processes, equipment and piping gallery for solution transport, storage, and disposition, and unique overhead bridge cranes to support overall process operations. All work is remotely controlled, and employees are further protected from radiation by thick concrete walls.

122

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

et al. Investigation of Nuclear Structure by Resonance1996, pp. G. Warren et al. Nuclear Resonance Fluorescenceof 235U IEEE Nuclear Science Symposium 2006, pp. 914. W.

Quiter, Brian J.

2010-01-01T23:59:59.000Z

123

Office of Material Consolidation & Civilian Sites | National Nuclear  

National Nuclear Security Administration (NNSA)

Material Consolidation & Civilian Sites | National Nuclear Material Consolidation & Civilian Sites | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Office of Material Consolidation & Civilian Sites Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices > Office of International Material

124

Loose Nukes: Nuclear Material Security in G.P.Gilfoyle  

E-Print Network (OSTI)

-standing policy of nuclear nonproliferation. · A nuclear blast would have horrific consequences; loss of lifeLoose Nukes: Nuclear Material Security in Russia G.P.Gilfoyle Physics Department, University of Richmond, Virginia Outline: 1. Nuclear Weapons 101 2. What are loose nukes and why should you care? 3. What

Gilfoyle, Jerry

125

Nuclear Forensic Reference Materials (RM) for Attribution of Urban Nuclear Terrorism  

E-Print Network (OSTI)

· Debris from a nuclear explosion · Debris from a radiological dispersal device Nuclear Forensic GoalsNuclear Forensic Reference Materials (RM) for Attribution of Urban Nuclear Terrorism Kenneth G relationships Nuclear Forensics require high-level expertise, undisputed signatures & extremely high fidelity

Perkins, Richard A.

126

Nuclear Materials Management and Safeguards System Reporting and Data Submission  

Directives, Delegations, and Requirements

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

127

material protection | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

protection | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

128

Absolute nuclear material assay using count distribution (LAMBDA) space  

DOE Patents (OSTI)

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-06-05T23:59:59.000Z

129

Cleanup Contractor Achieves Elite Nuclear Material Accountability Status  

Energy.gov (U.S. Department of Energy (DOE))

PADUCAH, Ky. EMs cleanup contractor at the Paducah site has received national acclaim for timeliness of reporting and promptness in reconciling nuclear material inventories.

130

Commission. The Nuclear Materials Management and Safeguards System...  

National Nuclear Security Administration (NNSA)

Revision 7, ''Instructions for Completing Nuclear Material Transaction Reports (DOENRC Forms 741 and 740M).'' Page 3 April 2014 April 2014 Topics Needed for the Industry...

131

Design Basis Threat | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Design Basis Threat | National Nuclear Security Administration Design Basis Threat | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Design Basis Threat Home > About Us > Our Programs > Nuclear Security > Design Basis Threat Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM)

132

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National  

National Nuclear Security Administration (NNSA)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Insider Threat to Nuclear and Radiological Materials: ... Fact Sheet Insider Threat to Nuclear and Radiological Materials: Fact Sheet

133

Tiny device can detect hidden nuclear weapons, materials  

NLE Websites -- All DOE Office Websites (Extended Search)

Tiny Tiny device can detect hidden nuclear weapons, materials Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Tiny device can detect hidden nuclear weapons, materials This tiny wafer can detect hidden nuclear weapons and materials NUCLEAR DETECTOR -- This small wafer could become the key component in

134

Analysis of the role of an interfacility SNM accounting system  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) undertook the task of analyzing the actual and potential value of an interfacility NRC material accounting system in deterring and detecting both material diversion and facility material accounting data falsification. The most important conclusion is that only relatively minor changes are needed to upgrade the current NRC interfacility reporting system. The emphasis of the task was on evaluating the usefulness of an NRC-monitored material accounting information system in providing protection against accounting fraud at the plant management or corporate level. The Nuclear Materials Management and Safeguards System (NMMSS) and the NRC Safeguards Status Report System (SSRS), the principal constituents of the current interfacility NRC material accounting information system, are described. Their relationship is shown in two information flow diagrams. Deterministic accounting checks and balances are discussed, both for the current NRC interfacility material accounting system and for an upgraded system. Detection mechanisms are described that would use currently available data and that could be exercised by the NRC in its safeguards management role. Additional checks and balances are recommended, with corresponding changes in data reporting requirements, to upgrade NRC interfacility material accounting system.

McDonnel, J.L.; Chilton, P.D.; Kufahl, G.E.; Vergari, A.A.; Dunn, D.R.

1982-02-22T23:59:59.000Z

135

Gamma/neutron analysis for SNM signatures at high-data rates(greater than 107 cps) for single-pulse active interrogation  

SciTech Connect

We are developing a high data gamma/neutron spectrometer suitable for active interrogation of special nuclear materials (SNM) activated by a single burst from an intense source. We have tested the system at Naval Research Laboratory's (NRL) Mercury pulsed-power facility at distances approaching 10 meters from a depleted uranium (DU) target. We have found that the gamma-ray field in the target room 'disappears' 10 milliseconds after the x-ray flash, and that gamma ray spectroscopy will then be dominated by isomeric states/beta decay of fission products. When a polyethylene moderator is added to the DU target, a time-dependent signature of the DU is produced by thermalized neutrons. We observe this signature in gamma-spectra measured consecutively in the 0.1-1.0 ms time range. These spectra contain the Compton edge line (2.2 MeV) from capture in hydrogen, and a continuous high energy gamma-spectrum from capture or fission in minority constituents of the DU.

Forman L.; Dioszegi, I.; Salwen, C.

2011-04-26T23:59:59.000Z

136

BSc in Nuclear Science and Materials H821 MEng in Nuclear Engineering H822  

E-Print Network (OSTI)

BSc in Nuclear Science and Materials H821 MEng in Nuclear Engineering H822 Research and education in nuclear engineering, waste management and decommissioning holds the key to sustainable energy production on an ambitious programme of commissioning nuclear energy, creating opportunities for graduates from plant design

Miall, Chris

137

Nuclear Energy Advisory Committee Meeting Materials | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Advisory Committee Meeting Materials Nuclear Energy Advisory Committee Meeting Materials Nuclear Energy Advisory Committee Meeting Materials November 26, 2013 MEETING MATERIALS: DECEMBER 19, 2013 Washington Marriott at Metro Center Ballroom A 775 12th Street, NW Washington, DC 20005 June 13, 2013 MEETING MATERIALS: JUNE 13, 2013 L'Enfant Plaza Hotel Ballroom D, (Main Floor) Washington, D.C. 20024 December 6, 2012 Meeting Materials: December 6, 2012 L'Enfant Plaza Hotel Quorum Room, (Main Floor) Washington, D.C. 20024 June 12, 2012 Meeting Materials: June 12, 2012 L'Enfant Plaza Hotel Monet Ballroom, (2nd Floor), Washington, D.C. 20024 December 13, 2011 Meetings Materials: December 13, 2011 L'Enfant Plaza Hotel Ballroom A - 1st Floor Washington, D.C. 20024 June 15, 2011 Meeting Materials: June 15, 2011 L'Enfant Plaza Hotel

138

SNM accounting systems: dBase versus C  

SciTech Connect

The Fuel Manufacturing Facility (FMF) at Argonne National Laboratories-West (ANL-W) in Idaho Falls accomplishes its internal special nuclear material accounting with a PC-based DYnamic Material ACcounting (PC/DYMAC) system developed as a collaboration between FMF and Los Alamos National Laboratory staff members. This system comprises four computers communicating via floppy disks containing transfer information. The accounting software was written in dBase and compiled under Clipper. The decision was made to network the computers and to speed the accounting process. Moreover, it was decided to extend the collaboration to Sandia National Laboratory staff and to incorporate their recently developed CAMUS and WATCH systems to automate data input and to provide a measure of material control. The current version of the code is being translated into the C language. The implications of such a change will be discussed. 9 refs., 3 figs.

Bearse, R.C.; Tisinger, R.M.; Ballmann, J.S.

1989-01-01T23:59:59.000Z

139

Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials & Waste » Nuclear Materials & Waste » Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 105-K building houses the K-Area Material Storage (KAMS) facility, designated for the consolidated storage of surplus plutonium at Savannah River Site pending disposition. The plutonium shipped to KAMS is sealed inside a welded 3013 containers that are nested in 9975 shipping containers. 105-K building houses the K-Area Material Storage (KAMS) facility, designated for the consolidated storage of surplus plutonium at Savannah River Site pending disposition. The plutonium shipped to KAMS is sealed inside a welded 3013 containers that are nested in 9975 shipping

140

NNSA: Securing Domestic Radioactive Material | National Nuclear...  

National Nuclear Security Administration (NNSA)

established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify, secure, remove andor...

Note: This page contains sample records for the topic "nuclear material snm" 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

Commercial Products Show Potential to serve as Nuclear Material and  

NLE Websites -- All DOE Office Websites (Extended Search)

Commercial Products Show Potential to serve as Nuclear Material and Commercial Products Show Potential to serve as Nuclear Material and Activity Monitoring Technologies | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Commercial Products Show Potential to serve as ... Commercial Products Show Potential to serve as Nuclear Material and

142

Commercial Products Show Potential to serve as Nuclear Material and  

National Nuclear Security Administration (NNSA)

Commercial Products Show Potential to serve as Nuclear Material and Commercial Products Show Potential to serve as Nuclear Material and Activity Monitoring Technologies | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Commercial Products Show Potential to serve as ... Commercial Products Show Potential to serve as Nuclear Material and

143

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

144

Atomic Energy and Nuclear Materials Program (Tennessee) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials Program (Tennessee) Nuclear Materials Program (Tennessee) Atomic Energy and Nuclear Materials Program (Tennessee) < Back Eligibility Commercial Construction Developer General Public/Consumer Industrial Investor-Owned Utility Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Atomic Energy and Nuclear Materials section of the Tennessee Code covers all of the regulations, licenses, permits, siting requirements, and practices relevant to a nuclear energy development. In addition to the Tennessee Code the Department of Environment and Conservation has a rule pertaining to the licensing and registration of sources of radiation. The Department's rules state that any contractor or subcontractor of the U.S.

145

NNSA: Securing Domestic Radioactive Material | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

NNSA: Securing Domestic Radioactive Material | National Nuclear Security NNSA: Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > NNSA: Securing Domestic Radioactive Material Fact Sheet NNSA: Securing Domestic Radioactive Material Apr 12, 2013 The Department of Energy's National Nuclear Security Administration (NNSA),

146

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

National Nuclear Security Administration (NNSA)

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

147

Compressive sensing for nuclear security.  

SciTech Connect

Special nuclear material (SNM) detection has applications in nuclear material control, treaty verification, and national security. The neutron and gamma-ray radiation signature of SNMs can be indirectly observed in scintillator materials, which fluoresce when exposed to this radiation. A photomultiplier tube (PMT) coupled to the scintillator material is often used to convert this weak fluorescence to an electrical output signal. The fluorescence produced by a neutron interaction event differs from that of a gamma-ray interaction event, leading to a slightly different pulse in the PMT output signal. The ability to distinguish between these pulse types, i.e., pulse shape discrimination (PSD), has enabled applications such as neutron spectroscopy, neutron scatter cameras, and dual-mode neutron/gamma-ray imagers. In this research, we explore the use of compressive sensing to guide the development of novel mixed-signal hardware for PMT output signal acquisition. Effectively, we explore smart digitizers that extract sufficient information for PSD while requiring a considerably lower sample rate than conventional digitizers. Given that we determine the feasibility of realizing these designs in custom low-power analog integrated circuits, this research enables the incorporation of SNM detection into wireless sensor networks.

Gestner, Brian Joseph

2013-12-01T23:59:59.000Z

148

Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS).  

SciTech Connect

Sandia National Laboratories was tasked with developing the Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS) with the sponsorship of NA-125.3 and the concurrence of DOE/NNSA field and area offices. The purpose of IIIMS was to modernize nuclear materials management information systems at the enterprise level. Projects over the course of several years attempted to spearhead this modernization. The scope of IIIMS was broken into broad enterprise-oriented materials management and materials forecasting. The IIIMS prototype was developed to allow multiple participating user groups to explore nuclear material requirements and needs in detail. The purpose of material forecasting was to determine nuclear material availability over a 10 to 15 year period in light of the dynamic nature of nuclear materials management. Formal DOE Directives (requirements) were needed to direct IIIMS efforts but were never issued and the project has been halted. When restarted, duplicating or re-engineering the activities from 1999 to 2003 is unnecessary, and in fact future initiatives can build on previous work. IIIMS requirements should be structured to provide high confidence that discrepancies are detected, and classified information is not divulged. Enterprise-wide materials management systems maintained by the military can be used as overall models to base IIIMS implementation concepts upon.

Aas, Christopher A.; Lenhart, James E.; Bray, Olin H.; Witcher, Christina Jenkin

2004-11-01T23:59:59.000Z

149

In-field analysis and assessment of nuclear material  

SciTech Connect

Los Alamos National Laboratory has actively developed and implemented a number of instruments to monitor, detect, and analyze nuclear materials in the field. Many of these technologies, developed under existing US Department of Energy programs, can also be used to effectively interdict nuclear materials smuggled across or within national borders. In particular, two instruments are suitable for immediate implementation: the NAVI-2, a hand-held gamma-ray and neutron system for the detection and rapid identification of radioactive materials, and the portable mass spectrometer for the rapid analysis of minute quantities of radioactive materials. Both instruments provide not only critical information about the characteristics of the nuclear material for law-enforcement agencies and national authorities but also supply health and safety information for personnel handling the suspect materials.

Morgado, R.E.; Myers, W.S.; Olivares, J.A.; Phillips, J.R.; York, R.L.

1996-05-01T23:59:59.000Z

150

Integrated neutron/gamma-ray portal monitors for nuclear safeguards  

SciTech Connect

Radiation monitoring is one nuclear-safeguards measure used to protect against the theft of special nuclear materials (SNM) by pedestrians departing from SNM access areas. The integrated neutron/gamma-ray portal monitor is an ideal radiation monitor for the task when the SNM is plutonium. It achieves high sensitivity for detecting both bare and shielded plutonium by combining two types of radiation detector. One type is a neutron-chamber detector, comprising a large, hollow, neutron moderator that contains a single thermal-neutron proportional counter. The entrance wall of each chamber is thin to admit slow neutrons from plutonium contained in a moderating shield, while the other walls are thick to moderate fast neutrons from bare or lead-shielded plutonium so that they can be detected. The other type of detector is a plastic scintillator that is primarily for detecting gamma rays from small amounts of unshielded plutonium. The two types of detector are easily integrated by making scintillators part of the thick back wall of each neutron chamber or by inserting them into each chamber void. We compared the influence of the two methods of integration on detecting neutrons and gamma rays, and we examined the effectiveness of other design factors and the methods for signal detection as well.

Fehlau, P.E.

1993-09-01T23:59:59.000Z

151

TAMCN: a tool for aggregate modeling of civil nuclear materials  

E-Print Network (OSTI)

involved in the creation, storage, and utilization of potentially destructive nuclear material. Western Europe and Japan, namely France, Belgium, the United Kingdom, Germany, Switzerland, and Japan, were chosen as a starting point because the issues...

Watson, Aaron Michael

2002-01-01T23:59:59.000Z

152

Manual for Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

The manual prescribes requirements and procedures for nuclear material control and accountability (MC&A). Cancels DOE M 474.1-1. Canceled by DOE M 474.1-1B.

2000-11-22T23:59:59.000Z

153

Manual for Control and Accountability of Nuclear Materials  

Directives, Delegations, and Requirements

The manual prescribes requirements and assign responsibilities for nuclear material control and accountability. Cancels DOE M 474.1-1A. Canceled by DOE M 470.4-6.

2003-06-13T23:59:59.000Z

154

Limits on Nuclear Materials for Arms Reduction: Complexities and Uncerainties  

Science Journals Connector (OSTI)

...there is little risk because the United...would ignore the nuclear materials production...capability ofthe Soviet power reactors and the...Savannah River Plant (SRP) reactors...U.S. would risk its national security...reactors at full power is not attractive...concomitant ban on nuclear tests would perpetuate...

W. G. SUTCLIFFE

1988-09-02T23:59:59.000Z

155

Limits on Nuclear Materials for Arms Reduction: Complexities and Uncerainties  

Science Journals Connector (OSTI)

...is little risk because the...ignore the nuclear materials...ofthe Soviet power reactors...Savannah River Plant (SRP) reactors...S. would risk its national security in this way...reactors at full power is not attractive...concomitant ban on nuclear tests would...

W. G. SUTCLIFFE

1988-09-02T23:59:59.000Z

156

Special nuclear material inventory sampling plans  

SciTech Connect

This paper presents improved procedures for obtaining statistically valid sampling plans for nuclear facilities. The double sampling concept and methods for developing optimal double sampling plans are described. An algorithm is described that is satisfactory for finding optimal double sampling plans and choosing appropriate detection and false alarm probabilities. (ACR)

Vaccaro, H.S.; Goldman, A.S.

1987-01-01T23:59:59.000Z

157

A Uniform Framework of Global Nuclear Materials Management  

SciTech Connect

Global Nuclear Materials Management (GNMM) anticipates and supports a growing international recognition of the importance of uniform, effective management of civilian, excess defense, and nuclear weapons materials. We expect thereto be a continuing increase in both the number of international agreements and conventions on safety, security, and transparency of nuclear materials, and the number of U.S.-Russian agreements for the safety, protection, and transparency of weapons and excess defense materials. This inventory of agreements and conventions may soon expand into broad, mandatory, international programs that will include provisions for inspection, verification, and transparency, To meet such demand the community must build on the resources we have, including State agencies, the IAEA and regional organizations. By these measures we will meet the future expectations for monitoring and inspection of materials, maintenance of safety and security, and implementation of transparency measures.

Dupree, S.A.; Mangan, D.L.; Sanders, T.L; Sellers, T.A.

1999-04-20T23:59:59.000Z

158

Status of nuclear weapons material disposition in Russia  

SciTech Connect

The security of nuclear weapons and fissile material in Russia, the disposition of weapons-usable fissile material in Russia, the Clinton administration`s policies and programs for assisting Russia in improving its security over nuclear weapons and fissile material, and the disposal of Russian weapons-usable fissile materials are discussed in this paper. There are {approximately}30,000 nuclear warheads in the former Soviet Union, {approximately}1000 t of weapon-usable high-enriched uranium (HEU), {approximately} 160 t of separated plutonium in weapons or available for weapons, and {approximately}30 t of separated civil plutonium stored in Russia. Most, if not all, of these inventories are stored under inadequate conditions of physical security and of material control and accounting.

Cochran, T.B.

1994-12-31T23:59:59.000Z

159

E-Print Network 3.0 - accountability nuclear materials Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

nuclear materials Search Powered by Explorit Topic List Advanced Search Sample search results for: accountability nuclear materials Page: << < 1 2 3 4 5 > >> 1 Los Alamos National...

160

A treaty to ban nuclear smuggling: The next step in nuclear material control?  

SciTech Connect

Since the demise of the Soviet Union, reports have continued to surface that weapons-usable nuclear material has been smuggled out of former Soviet territory into the hands of proliferant states. So far, few examples of nuclear smuggling have involved serious quantities of weapons-usable material, and much purported smuggling has involved attempted fraud rather than an effort to transfer fissile material. In no instance has an actual transfer to a potential proliferant state been verified.

Carnahan, B.M. [Science Applications International Corp., McLean, VA (United States); Smith, J.R.

1994-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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.


161

The U.S. national nuclear forensics library, nuclear materials information program, and data dictionary  

SciTech Connect

Nuclear forensics assessments to determine material process history requires careful comparison of sample data to both measured and modeled nuclear material characteristics. Developing centralized databases, or nuclear forensics libraries, to house this information is an important step to ensure all relevant data will be available for comparison during a nuclear forensics analysis and help expedite the assessment of material history. The approach most widely accepted by the international community at this time is the implementation of National Nuclear Forensics libraries, which would be developed and maintained by individual nations. This is an attractive alternative toan international database since it provides an understanding that each country has data on materials produced and stored within their borders, but eliminates the need to reveal any proprietary or sensitive information to other nations. To support the concept of National Nuclear Forensics libraries, the United States Department of Energy has developed a model library, based on a data dictionary, or set of parameters designed to capture all nuclear forensic relevant information about a nuclear material. Specifically, information includes material identification, collection background and current location, analytical laboratories where measurements were made, material packaging and container descriptions, physical characteristics including mass and dimensions, chemical and isotopic characteristics, particle morphology or metallurgical properties, process history including facilities, and measurement quality assurance information. While not necessarily required, it may also be valuable to store modeled data sets including reactor burn-up or enrichment cascade data for comparison. It is fully expected that only a subset of this information is available or relevant to many materials, and much of the data populating a National Nuclear Forensics library would be process analytical or material accountability measurement data as opposed to a complete forensic analysis of each material in the library.

Lamont, Stephen Philip [Los Alamos National Laboratory; Brisson, Marcia [DOE-IN; Curry, Michael [DEPT. OF STATE

2011-02-17T23:59:59.000Z

162

A dual neutron/gamma source for the Fissmat Inspection for Nuclear Detection (FIND) system.  

SciTech Connect

Shielded special nuclear material (SNM) is very difficult to detect and new technologies are needed to clear alarms and verify the presence of SNM. High-energy photons and neutrons can be used to actively interrogate for heavily shielded SNM, such as highly enriched uranium (HEU), since neutrons can penetrate gamma-ray shielding and gamma-rays can penetrate neutron shielding. Both source particles then induce unique detectable signals from fission. In this LDRD, we explored a new type of interrogation source that uses low-energy proton- or deuteron-induced nuclear reactions to generate high fluxes of mono-energetic gammas or neutrons. Accelerator-based experiments, computational studies, and prototype source tests were performed to obtain a better understanding of (1) the flux requirements, (2) fission-induced signals, background, and interferences, and (3) operational performance of the source. The results of this research led to the development and testing of an axial-type gamma tube source and the design/construction of a high power coaxial-type gamma generator based on the {sup 11}B(p,{gamma}){sup 12}C nuclear reaction.

Doyle, Barney Lee (Sandia National Laboratories, Albuquerque, NM); King, Michael; Rossi, Paolo (Sandia National Laboratories, Albuquerque, NM); McDaniel, Floyd Del (Sandia National Laboratories, Albuquerque, NM); Morse, Daniel Henry; Antolak, Arlyn J.; Provencio, Paula Polyak (Sandia National Laboratories, Albuquerque, NM); Raber, Thomas N.

2008-12-01T23:59:59.000Z

163

Nuclear forensics of special nuclear material at Los Alamos: three recent studies  

SciTech Connect

Nuclear forensics of special nuclear materials is a highly specialized field because there are few analytical laboratories in the world that can safely handle nuclear materials, perform high accuracy and precision analysis using validated analytical methods. The goal of nuclear forensics is to establish an unambiguous link between illicitly trafficked nuclear material and its origin. The Los Alamos National Laboratory Nuclear Materials Signatures Program has implemented a graded 'conduct of operations' type approach for determining the unique nuclear, chemical, and physical signatures needed to identify the manufacturing process, intended use, and origin of interdicted nuclear material. In our approach an analysis flow path was developed for determining key signatures necessary for attributing unknown materials to a source. This analysis flow path included both destructive (i.e., alpha spectrometry, ICP-MS, ICP-AES, TIMS, particle size distribution, density and particle fractionation) and non-destructive (i.e., gamma-ray spectrometry, optical microscopy, SEM, XRD, and x-ray fluorescence) characterization techniques. Analytical techniques and results from three recent cases characterized by this analysis flow path along with an evaluation of the usefulness of this approach will be discussed in this paper.

Tandon, Lav [Los Alamos National Laboratory; Gallimore, David L [Los Alamos National Laboratory; Garduon, Katherine [Los Alamos National Laboratory; Keller, Russell C [Los Alamos National Laboratory; Kuhn, Kevin J [Los Alamos National Laboratory; Lujan, Elmer J [Los Alamos National Laboratory; Martinez, Alexander [Los Alamos National Laboratory; Myers, Steven C [Los Alamos National Laboratory; Moore, Steve S [Los Alamos National Laboratory; Porterfield, Donivan R [Los Alamos National Laboratory; Schwartz, Daniel S [Los Alamos National Laboratory; Spencer, Khalil J [Los Alamos National Laboratory; Townsend, Lisa E [Los Alamos National Laboratory; Xu, Ning [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

164

Nuclear materials control and accountability criteria for upgrades measures  

SciTech Connect

As a result of major political and societal changes in the past several years, methods of nuclear material control may no longer be as effective as in the past in Russia, the Newly Independent States (NIS), and the Baltic States (BS). The objective of the Department of Energy (DOE) Material Protection, Control, and Accounting Program (MPC and A) is to reduce the threat of nuclear proliferation by collaborating with Russia, NIS, and BS governments to promote western-style MPC and A. This cooperation will improve the MPC and A on all weapons useable nuclear materials and will establish a sustainable infrastructure to provide future support and maintenance for these technology-based improvements. Nuclear materials of proliferation concern include materials of the types and quantities that can be most easily and directly used in a nuclear weapon. Sabotage of nuclear material is an event of great concern and potentially disastrous consequences to both the US and the host country. However, sabotage is currently beyond the scope of program direction and cannot be used to justify US-funded MPC and A upgrades. Judicious MPC and A upgrades designed to protect against insider and outsider theft scenarios would also provide addition, although not comprehensive, protection against saboteurs. This paper provides some suggestions to establish consistency in prioritizing system-enhancement efforts at nuclear material facilities. The suggestions in this paper are consistent with DOE policy and directions and should be used as a supplement to any policy directives issued by NN-40, DOE Russia/NIS Task Force.

Erkkila, B.H.; Hatcher, C.R.

1998-11-01T23:59:59.000Z

165

An overview of measurement methods for special nuclear material in spent nuclear fuel  

SciTech Connect

Summary results from a survey of nondestructive assay measurement methods applicable to the measurement of the special nuclear material content of spent nuclear fuel are described. The role of nuclear materials measurements in the domestic and international safeguarding of spent nuclear fuel in the United States' federal waste management system has yet to be determined. An understanding of the characteristics and capabilities of the potentially applicable measurement systems should provide valuable information to the developers of the safeguards approaches for the monitored retrievable storage and final disposal systems. The discussion focuses on the general characteristics of the identified direct and indirect measurement methods. 3 refs., 1 tab.

Moran, B.W.; Reich, W.J.

1989-07-01T23:59:59.000Z

166

Detecting fission from special nuclear material sources  

DOE Patents (OSTI)

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

Rowland, Mark S. (Alamo, CA); Snyderman, Neal J. (Berkeley, CA)

2012-06-05T23:59:59.000Z

167

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enabling Technologies (NEET) Reactor Materials Enabling Technologies (NEET) Reactor Materials Award Recipient Estimated Award Amount* Award Location Supporting Organizations Project Description University of Nebraska $979,978 Lincoln, NE Massachusetts Institute of Technology (Cambridge, MA), Texas A&M (College Station, TX) Project will explore the development of advanced metal/ceramic composites. These improvements could lead to more efficient production of electricity in advanced reactors. Oak Ridge National Laboratory $849,000 Oak Ridge, TN University of Wisconsin-Madison (Madison, WI) Project will develop novel high-temperature high-strength steels with the help of computational modeling, which could lead to increased efficiency in advanced reactors. Pacific Northwest National Laboratory

168

Potential applications of nanostructured materials in nuclear waste management.  

SciTech Connect

This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

2003-09-01T23:59:59.000Z

169

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

NLE Websites -- All DOE Office Websites (Extended Search)

Aerial photo of Argonne National Laboratory Argonne National Laboratory University of Chicago Chicago Photography courtesy Thomas F Ewing Privacy and Security Notice The MMSNF Workshops The goal of the Materials Modeling and Simulation for Nuclear Fuels (MMSNF) workshops is to stimulate research and discussions on modeling and simulations of nuclear fuels, to assist the design of improved fuels and the evaluation of fuel performance. In addition to research focused on existing or improved types of LWR reactors, recent modeling programs, networks, and links have been created to develop innovative nuclear fuels and materials for future generations of nuclear reactors. Examples can be found in Europe (e.g. F-BRIDGE project and ACTINET network and SAMANTHA cooperative network), in the USA (e.g. CASL, NEAMS, CESAR and CMSN network

170

Survey of hazardous materials used in nuclear testing  

SciTech Connect

The use of hazardous'' materials in routine underground nuclear tests at the Nevada Test Site has been reviewed. In addition the inventory of test yields, originally reported in 1976 has been updated. A trail down-hole inventory'' has been conducted for a selected test. The inorganic hazardous materials introduced during testing (with the exception of lead and the fissionable materials) produce an incremental change in the quantity of such materials already present in the geologic media surrounding the test points. 1 ref., 3 tabs.

Bryant, E.A.; Fabryka-Martin, J.

1991-02-01T23:59:59.000Z

171

Westinghouse Hanford Company FY 1995 Materials Management Plan (MMP)  

SciTech Connect

The safe and sound operation of facilities and storage of nuclear material are top priorities within Hanford`s environmental management, site restoration mission. The projected materials estimates, based on the Materials Management Plan (MMP) assumptions outlined below, were prepared for Department of Energy (DOE) use in long-range planning. The Hanford MMP covers the period FY 1995 through FY 2005, as directed by DOE. All DOE Richland Operations (RL) Office facilities are essentially funded by the Office of Transition and Facilities Management, Environmental Restoration and Waste Management (EM). These facilities include PUREX, the UO{sub 3} plant, N-Reactor, T-Plant, K-Basins, FFTF, PFP and the 300 Area Fuel Fabrication facilities. Currently DP provides partial funding for the latter two facilities. Beginning in FY 1996 (in accordance with DOE-HQ MMP assumptions), EM will fund expenses related to the storage, monitoring, and safeguarding of all Special Nuclear Material (SNM) in the PFP. Ownership and costs related to movement and/or stabilization of that material will belong to EM programs (excluding NE material). It is also assumed that IAEA will take over inventory validation and surveillance of EM owned SNM at this time (FY 1996).

Higginson, M.C.

1994-10-01T23:59:59.000Z

172

IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION  

SciTech Connect

Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

Mickalonis, J.; Dunn, K.; Clifton, B.

2012-10-01T23:59:59.000Z

173

Nuclear Resonant Scattering on Earth Materials using Synchrotron Radiation  

NLE Websites -- All DOE Office Websites (Extended Search)

NRS2005 Home NRS2005 Home Agenda Organizing Committee Nuclear Resonant Scattering on Earth Materials using Synchrotron Radiation February 12-13, 2005 Advanced Photon Source Argonne National Laboratory - Argonne, Illinois, USA Nuclear Resonant Scattering (NRS) techniques provide the Earth and planetary science community with opportunities for new and exciting results on the properties of materials at high pressure and temperature conditions. Such NRS experiments have become possible due to the extreme brightness of third-generation synchrotron radiation sources. NRS techniques fall into two broad areas, which are in many ways ideally or even uniquely suited for addressing a number of important geophysical questions: Nuclear Resonant Inelastic X-ray Scattering (NRIXS) provides information on

174

Adhesion layer for etching of tracks in nuclear trackable materials  

DOE Patents (OSTI)

A method for forming nuclear tracks having a width on the order of 100-200 nm in nuclear trackable materials, such as polycarbonate (LEXAN) without causing delamination of the LEXAN. The method utilizes an adhesion film having a inert oxide which allows the track to be sufficiently widened to >200 nm without delamination of the nuclear trackable materials. The adhesion film may be composed of a metal such as Cr, Ni, Au, Pt, or Ti, or composed of a dielectric having a stable surface, such as silicon dioxide (SiO.sub.2), silicon nitride (SiN.sub.x), and aluminum oxide (AlO). The adhesion film can either be deposited on top of the gate metal layer, or if the properties of the adhesion film are adequate, it can be used as the gate layer. Deposition of the adhesion film is achieved by standard techniques, such as sputtering or evaporation.

Morse, Jeffrey D. (Martinez, CA); Contolini, Robert J. (Lake Oswego, OR)

2001-01-01T23:59:59.000Z

175

Storage of nuclear materials by encapsulation in fullerenes  

DOE Patents (OSTI)

A method of encapsulating radioactive materials inside fullerenes for stable long-term storage. Fullerenes provide a safe and efficient means of disposing of nuclear waste which is extremely stable with respect to the environment. After encapsulation, a radioactive ion is essentially chemically isolated from its external environment.

Coppa, Nicholas V. (Los Alamos, NM)

1994-01-01T23:59:59.000Z

176

IMPROVED TECHNNOLOGY TO PREVENT ILLICIT TRAFFICKING IN NUCLEAR MATERIALS  

SciTech Connect

The proliferation of nuclear, chemical, and biological weapons (collectively known as weapons of mass destruction, or WMD) and the potential acquisition and use of WMD against the world by terrorists are extremely serious threats to international security. These threats are complex and interrelated. There are myriad routes to weapons of mass destruction--many different starting materials, material sources, and production processes. There are many possible proliferators--threshold countries, rogue states, state-sponsored or transnational terrorists groups, domestic terrorists, and even international crime organizations. Motives for acquiring and using WMD are similarly wide ranging--from a desire to change the regional power balance, deny access to a strategic area, or alter international policy to extortion, revenge, or hate. Because of the complexity of this threat landscape, no single program, technology, or capability--no silver bullet--can solve the WMD proliferation and terrorism problem. An integrated program is needed that addresses the WMD proliferation and terrorism problem from end to end, from prevention to detection, reversal, and response, while avoiding surprise at all stages, with different activities directed specifically at different types of WMD and proliferators. Radiation detection technologies are an important tool in the prevention of proliferation. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. The radiation properties of nuclear materials, particularly highly enriched uranium (HEU), make the detection of smuggled nuclear materials technically difficult. A number of efforts are under way to devise improved detector materials and instruments and to identify novel signatures that could be detected. Key applications of this work include monitoring for radioactive materials at choke points, searching for nuclear materials, and developing instruments for response personnel.

Richardson, J H

2005-07-20T23:59:59.000Z

177

Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development  

SciTech Connect

The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

Jon Carmack

2014-01-01T23:59:59.000Z

178

USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?  

SciTech Connect

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable (assets) to worthless (wastes). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or in the case of high level waste awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Sites (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as waste include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

Magoulas, V.

2013-06-03T23:59:59.000Z

179

Nuclear materials 1993 annual report. Volume 8, No. 2  

SciTech Connect

This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

NONE

1995-05-01T23:59:59.000Z

180

E-Print Network 3.0 - advanced nuclear materials Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Powered by Explorit Topic List Advanced Search Sample search results for: advanced nuclear materials Page: << < 1 2 3 4 5 > >> 1 Enabling a Sustainable Nuclear Energy Future...

Note: This page contains sample records for the topic "nuclear material snm" 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

Management of nuclear materials and non-HLW | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the consolidation and disposition of nuclear materials, including plutonium, uranium, and nuclear waste in accordance with applicable statutes, DOE Orders and international...

182

Use of Imaging for Nuclear Material Control and Accountability  

SciTech Connect

The recent addition of imaging to the Nuclear Materials and Identification System (NMIS) using a small portable DT neutron generator with an embedded alpha detector to time and directionally tag neutrons from the DT reaction is discussed. The generator weighs {approx}35 lbs including power supplies (5 x 10{sup 7} n/sec) and operates on 50 watts power. Thus, the source can be easily moved to a variety of locations within an operational facility with minimum impact on operations or can be used at a fixed location for example to monitor receipts. Imaging NMIS (INMIS) not only characterizes the detailed shape of a containerized object by transmission tomography but determines the presence of fissile material by measuring the emitted radiation from induced fission. Previous work has shown that this type of imaging has a variety of applications other than nuclear material control and accountability (NMC&A). These include nonproliferation applications such as verification of configuration of nuclear weapons/components shipped or received, warhead authentication behind an information barrier, and traceability of weapons components both fissile and non fissile in dismantlement and counter terrorism. This paper concentrates on the use for NMC&A. Some of the NMC&A applications discussed are: verifying inventory and receipts, making more accurate holdup measurements especially where thicknesses of materials affect gamma ray spectrometry , determining the shape of unknown configurations of fissile materials where the material type may be known but not the form, determining the oxidation of fissile metal in storage cans, fingerprinting the content of storage containers going into a storage facility, and determining unknown configurations for criticality safety.

Mullens, James Allen [ORNL] [ORNL; Hausladen, Paul [ORNL] [ORNL; Bingham, Philip R [ORNL] [ORNL; Archer, Daniel E [ORNL] [ORNL; Grogan, Brandon R [ORNL] [ORNL; Mihalczo, John T [ORNL] [ORNL

2007-01-01T23:59:59.000Z

183

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review  

SciTech Connect

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

Thiel, E.C.; Fuhrman, P.W.

2002-05-30T23:59:59.000Z

184

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review  

SciTech Connect

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

Thiel, Elizabeth Chilcote

2002-05-01T23:59:59.000Z

185

Piezoelectric material for use in a nuclear reactor core  

SciTech Connect

In radiation environments ultrasonic nondestructive evaluation has great potential for improving reactor safety and furthering the understanding of radiation effects and materials. In both nuclear power plants and materials test reactors, elevated temperatures and high levels of radiation present challenges to ultrasonic NDE methodologies. The challenges are primarily due to the degradation of the ultrasonic sensors utilized. We present results from the operation of a ultrasonic piezoelectric transducer, composed of bulk single crystal AlN, in a nuclear reactor core for over 120 MWHrs. The transducer was coupled to an aluminum cylinder and operated in pulse echo mode throughout the irradiation. In addition to the pulse echo testing impedance data were obtained. Further, the piezoelectric coefficient d{sub 33} was measured prior to irradiation and found to be 5.5 pC/N which is unchanged from as-grown samples, and in fact higher than the measured d{sub 33} for many as-grown samples.

Parks, D. A.; Reinhardt, Brian; Tittmann, B. R. [EES Department, Penn State University, University Park, PA 16802 (United States)

2012-05-17T23:59:59.000Z

186

Publications [Corrosion and Mechanics of Materials] - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Publications Publications Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Selection of Publications Bookmark and Share Journal Articles Manufacturing of representative axial stress corrosion cracks in tube specimens for eddy current testing C.B. Bahn, S. Bakhtiari, J.Y. Park, S. Majumdar Nuclear Engineering and Design, Volume 256, March 2013, Pages 38-44 Leak behavior of steam generator tube-to-tubesheet joints under

187

Non-intrusive, nuclear component discrimination with a micro-channel plate gamma-ray detector  

SciTech Connect

We describe the function of a micro-channel plate gamma-ray detector designed for non-intrusive detection of physically obscured special nuclear material (SNM), including nuclear weapons. An example application of such a detector is a cooperative inspection distinguishing between nuclear and non-nuclear weapons where legitimate numbers of each may be present. In this type of scenario, the information needed would be the number of each type of weapon. Another example scenario would be a weapon-type classification based on a benchmarked gamma-ray count rate from each package type (nuclear type A or nuclear type B). In both of these scenarios, we desire the location of nuclear weapons.

Rowland, M.

1993-11-01T23:59:59.000Z

188

Gamma-ray identification of nuclear weapon materials  

SciTech Connect

There has been an accelerating national interest in countering nuclear smuggling. This has caused a corresponding expansion of interest in the use of gamma-ray spectrometers for checkpoint monitoring, nuclear search, and within networks of nuclear and collateral sensors. All of these are fieldable instruments--ranging from large, fixed portal monitors to hand-held and remote monitoring equipment. For operational reasons, detectors with widely varying energy resolution and detection efficiency will be employed. In many instances, such instruments must be sensitive to weak signals, always capable of recognizing the gamma-ray signatures from nuclear weapons materials (NWM), often largely insensitive to spectral alteration by radiation transport through intervening materials, capable of real-time implementation, and able to discriminate against signals from commonly encountered legitimate gamma-ray sources, such as radiopharmaceuticals. Several decades of experience in classified programs have shown that all of these properties are not easily achieved and successful approaches were of limited scope--such as the detection of plutonium only. This project was originally planned as a two-year LDRD-ER. Since funding for 1997 was not sustained, this is a report of the first year's progress.

Gosnell, T. B., LLNL; Hall, J. M.; Jam, C. L.; Knapp, D. A.; Koenig, Z. M.; Luke, S. J.; Pohl, B. A.; Schach von Wittenau, A.; Wolford, J. K.

1997-02-03T23:59:59.000Z

189

X-ray backscatter imaging of nuclear materials  

DOE Patents (OSTI)

The energy of an X-ray beam and critical depth are selected to detect structural discontinuities in a material having an atomic number Z of 57 or greater. The critical depth is selected by adjusting the geometry of a collimator that blocks backscattered radiation so that backscattered X-ray originating from a depth less than the critical depth is not detected. Structures of Lanthanides and Actinides, including nuclear fuel rod materials, can be inspected for structural discontinuities such as gaps, cracks, and chipping employing the backscattered X-ray.

Chapman, Jeffrey Allen; Gunning, John E; Hollenbach, Daniel F; Ott, Larry J; Shedlock, Daniel

2014-09-30T23:59:59.000Z

190

Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material  

SciTech Connect

The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access.

Nicholson, Lary G.; Purvis, James W.

1999-07-21T23:59:59.000Z

191

Robotic control architecture development for automated nuclear material handling systems  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) is engaged in developing automated systems for handling materials for mixed waste treatment, nuclear pyrochemical processing, and weapon components disassembly. In support of these application areas there is an extensive robotic development program. This paper will describe the portion of this effort at LLNL devoted to control system architecture development, and review two applications currently being implemented which incorporate these technologies.

Merrill, R.D.; Hurd, R.; Couture, S.; Wilhelmsen, K.

1995-02-01T23:59:59.000Z

192

Journal of Nuclear Materials 196-198 (1992) 680-685 North-Holland  

E-Print Network (OSTI)

Journal of Nuclear Materials 196-198 (1992) 680-685 North-Holland jnurnalef nuclear materials. Ehst Argonne National Laboratory, Fusion PowerProgram, 9700 South CassAvenue, Argonne, IL 60439, USA

Harilal, S. S.

193

Advanced ceramic materials for next-generation nuclear applications  

Science Journals Connector (OSTI)

The nuclear industry is at the eye of a 'perfect storm' with fuel oil and natural gas prices near record highs, worldwide energy demands increasing at an alarming rate, and increased concerns about greenhouse gas (GHG) emissions that have caused many to look negatively at long-term use of fossil fuels. This convergence of factors has led to a growing interest in revitalization of the nuclear power industry within the United States and across the globe. Many are surprised to learn that nuclear power provides approximately 20% of the electrical power in the US and approximately 16% of the world-wide electric power. With the above factors in mind, world-wide over 130 new reactor projects are being considered with approximately 25 new permit applications in the US. Materials have long played a very important role in the nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced reactor systems and fuel cycles that minimize waste and increase proliferation resistance, materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Advanced metallic and ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles, advanced alloy fuels for 'deep-burn' applications, as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, a number of fuel reprocessing operations are being investigated. Advanced materials continue to provide a vital contribution in 'closing the fuel cycle' by stabilization of associated low-level and high-level wastes in highly durable cements, ceramics, and glasses. Beyond this fission energy application, fusion energy will demand advanced materials capable of withstanding the extreme environments of high-temperature plasma systems. Fusion reactors will likely depend on lithium-based ceramics to produce tritium that fuels the fusion plasma, while high-temperature alloys or ceramics will contain and control the hot plasma. All the while, alloys, ceramics, and ceramic-related processes continue to find applications in the management of wastes and byproducts produced by these processes.

John Marra

2011-01-01T23:59:59.000Z

194

CORROSION OF LEAD SHIELDING IN NUCLEAR MATERIALS PACKAGES  

SciTech Connect

Inspection of United States-Department of Energy (US-DOE) model 9975 nuclear materials shipping package revealed corrosion of the lead shielding induced by off-gas constituents from organic components in the package. Experiments were performed to determine the corrosion rate of lead when exposed to off-gas or degradation products of these organic materials. The results showed that the room temperature vulcanizing (RTV) sealant was the most corrosive organic species followed by the polyvinyl acetate (PVAc) glue. The fiberboard material induced corrosion to a much lesser extent than the PVAc glue and RTV, and only in the presence of condensed water. The results indicated faster corrosion at temperatures higher than ambient and with condensed water as expected. A corrosion rate of 0.05 mm/year measured for coupons exposed to the most aggressive conditions was recommended as a conservative estimate for use in package performance calculations.

Subramanian, K; Kerry Dunn, K

2007-11-16T23:59:59.000Z

195

Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo  

DOE Patents (OSTI)

A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

Slaughter, Dennis R. (Oakland, CA); Pohl, Bertram A. (Berkeley, CA); Dougan, Arden D. (San Ramon, CA); Bernstein, Adam (Palo Alto, CA); Prussin, Stanley G. (Kensington, CA); Norman, Eric B. (Oakland, CA)

2008-04-15T23:59:59.000Z

196

Vapor etching of nuclear tracks in dielectric materials  

DOE Patents (OSTI)

A process involving vapor etching of nuclear tracks in dielectric materials for creating high aspect ratio (i.e., length much greater than diameter), isolated cylindrical holes in dielectric materials that have been exposed to high-energy atomic particles. The process includes cleaning the surface of the tracked material and exposing the cleaned surface to a vapor of a suitable etchant. Independent control of the temperatures of the vapor and the tracked materials provide the means to vary separately the etch rates for the latent track region and the non-tracked material. As a rule, the tracked regions etch at a greater rate than the non-tracked regions. In addition, the vapor-etched holes can be enlarged and smoothed by subsequent dipping in a liquid etchant. The 20-1000 nm diameter holes resulting from the vapor etching process can be useful as molds for electroplating nanometer-sized filaments, etching gate cavities for deposition of nano-cones, developing high-aspect ratio holes in trackable resists, and as filters for a variety of molecular-sized particles in virtually any liquid or gas by selecting the dielectric material that is compatible with the liquid or gas of interest.

Musket, Ronald G. (Danville, CA); Porter, John D. (Berkeley, CA); Yoshiyama, James M. (Fremont, CA); Contolini, Robert J. (Lake Oswego, OR)

2000-01-01T23:59:59.000Z

197

Tagging and fissile material verification concepts for nuclear warhead dismantlement  

SciTech Connect

Arms control treaties that reduce the number of deployable nuclear-warhead delivery systems might also lead to provisions for the verified dismantlement of nuclear weapons. Based on public information and very simple conceptual models of nuclear warheads, one can visualize a set of procedural and technological requirements to account for warheads removed from deployed sites and ultimately dismantled. To accomplish the accounting function, verification-quality tags and/or seals might be needed in order that the warheads taken out of storage can be tracked to the dismantlement site. These tags/seals would represent an overlay on the existing chain of custody. The verified dismantlement of the warheads poses special problems in confirming their identity and in avoiding the loss of sensitive information. A central factor is the publicly recognized need for some minimum quantity of fissile material to constitute a nuclear warhead. A measurement system that could make such a determination without giving away unnecessary information would be desired. Some approaches based on existing fissile assay methods are discussed. 1 ref., 2 figs.

DeVolpi, A.

1990-01-01T23:59:59.000Z

198

Novel Approach to Plasma Facing Materials in Nuclear Fusion Reactors  

SciTech Connect

A novel material design in nuclear fusion reactors is proposed based on W-nDiamond nanostructured composites. Generally, a microstructure refined to the nanometer scale improves the mechanical strength due to modification of plasticity mechanisms. Moreover, highly specific grain-boundary area raises the number of sites for annihilation of radiation induced defects. However, the low thermal stability of fine-grained and nanostructured materials demands the presence of particles at the grain boundaries that can delay coarsening by a pinning effect. As a result, the concept of a composite is promising in the field of nanostructured materials. The hardness of diamond renders nanodiamond dispersions excellent reinforcing and stabilization candidates and, in addition, diamond has extremely high thermal conductivity. Consequently, W-nDiamond nanocomposites are promising candidates for thermally stable first-wall materials. The proposed design involves the production of W/W-nDiamond/W-Cu/Cu layered castellations. The W, W-nDiamond and W-Cu layers are produced by mechanical alloying followed by a consolidation route that combines hot rolling with spark plasma sintering (SPS). Layer welding is achieved by spark plasma sintering. The present work describes the mechanical alloying processsing and consolidation route used to produce W-nDiamond composites, as well as microstructural features and mechanical properties of the material produced Long term plasma exposure experiments are planned at ISTTOK and at FTU (Frascati)

Livramento, V.; Correia, J. B.; Shohoji, N.; Osawa, E. [INETI, Departamento de Materiais e Tecnologias de Producao, Estrada do Pacco do Lumiar, 1649-038 Lisboa (Portugal); Nunes, D. [Associacao Euratom/IST, Departamento de Engenharia de Materiais, Instituto Superior Tecnico, Av. Rovisco Pais, 1049-001 Lisboa (Portugal); Carvalho, P. A.; Fernandes, H.; Silva, C. [Associacao Euratom/IST, Centro de Fusao Nuclear, Instituto Superior Tecnico, Av. Rovisco Pais, 1049-001 Lisboa (Portugal); Hanada, K. [National Institute of Advanced Industrial Science and Technology (AIST), 1-2-1 Namiki, Tsukuba, Ibaraki 305-8564 (Japan)

2008-04-07T23:59:59.000Z

199

Nuclear Materials Management and Safeguards System Working Group Charter  

National Nuclear Security Administration (NNSA)

DRAFT 2011 DRAFT 2011 DRAFT 2011 Nuclear Materials Management and Safeguards System Working Group Charter VERSION: 0 REVISION DATE: May 2011 Approver Name Title Signature Date DRAFT 2011 DRAFT 2011 NMMSS Working Group Charter PURPOSE The NMMSS Working Group (NWG) serves as an open forum for discussion of issues and concerns from the NMMSS User community. The Committee will provide an interface between NMMSS users, NMMSS sponsors and the NMMSS project staff. Activities may include: Identifying user needs Identifying deficiencies in reporting capabilities Recommending upgrades to software capabilities Recommending priorities for modifications Recommending enhancements to data Minimizing the reporting burden on the reporting community

200

Distributional properties of stochastic shortest paths for smuggled nuclear material  

SciTech Connect

The shortest path problem on a network with fixed weights is a well studied problem with applications to many diverse areas such as transportation and telecommunications. We are particularly interested in the scenario where a nuclear material smuggler tries to succesfully reach herlhis target by identifying the most likely path to the target. The identification of the path relies on reliabilities (weights) associated with each link and node in a multi-modal transportation network. In order to account for the adversary's uncertainty and to perform sensitivity analysis we introduce random reliabilities. We perform some controlled experiments on the grid and present the distributional properties of the resulting stochastic shortest paths.

Cuellar, Leticia [Los Alamos National Laboratory; Pan, Feng [Los Alamos National Laboratory; Roach, Fred [Los Alamos National Laboratory; Saeger, Kevin J [Los Alamos National Laboratory

2011-01-05T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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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201

Safety assessment of a robotic system handling nuclear material  

SciTech Connect

This paper outlines the use of a Failure Modes and Effects Analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, The Weigh and Leak Check System, is to replace a manual process at the Department of Energy facility at Pantex by which nuclear material is inspected for weight and leakage. Failure Modes and Effects Analyses were completed for the robotics process to ensure that safety goals for the system had been meet. These analyses showed that the risks to people and the internal and external environment were acceptable.

Atcitty, C.B.; Robinson, D.G.

1996-02-01T23:59:59.000Z

202

Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)  

SciTech Connect

In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet Americas nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in green technology.

Jesse Schreiber

2008-03-01T23:59:59.000Z

203

Nuclear car wash status report, August 2005  

SciTech Connect

A large majority of US imports arrive at seaports in maritime cargo containers. The number of containers arriving is nearly 10 million per year, each with a cargo of up to 30 tons of various materials. This provides a vulnerable entry point for the importation of a nuclear weapon or its components by a terrorist group. Passive radiation sensors are being deployed at portals to detect radioactive material and portable instruments are carried by port personnel to augment detection. Those instruments can detect the neutrons and g-rays produced by {sup 240}Pu that is normally present in weapons grade plutonium in cases where cargo overburden is not too great. However, {sup 235}U produces almost no neutron output in its normal radioactive decay and its principal {gamma}-radiation is at 186 keV and is readily attenuated by small amounts of wood or packing materials. Impurities such as {sup 232}U, often present in reactor irradiated material at the 100-200 ppt level, can provide a detectable signal through significant cargo overburden but the wide variations among samples of HEU make this an unreliable means of detecting SNM. High quality radiography may be useful in determining that the majority of containers are clearly free of SNM. However, some containers will lead to ambiguous results from radiography and passive radiation sensing. For these reasons active neutron interrogation is proposed as a means to produce fission and thus greatly amplify the radiation output of fissionable material to facilitate its reliable detection even when well shielded by large cargo overburden. Historically, the fission signature utilized as the unique identifying feature of fissionable materials is the detection of delayed neutrons. However, these neutrons have very low yield {approx} 0.017 per fission in {sup 235}U, and their low energy results in very poor penetration of hydrogenous materials such as fuels, water, wood, or agricultural products. That signature alone does not provide reliable detection in thick cargos. A new signature has been identified and has been developed within the current project for the detection of well shielded SNM. This SNM signature is based on high-energy {beta}-delayed {gamma}-radiation produced by fission products following neutron or photon induced fission. These {gamma}-rays are high enough in energy (E{sub {gamma}} > 3 MeV) to be readily distinguished from any natural background radioactivity since the latter does not extend above 2.6 MeV. Their abundance is nearly a decade greater than delayed neutrons and their short half-lives deliver nearly all of the signature radiation on time scales of one minute or less and thus facilitate rapid scanning. Finally, for this {gamma}-radiation in the 3-6 MeV range attenuation occurs only by Compton scattering and is in the range where minimum attenuation occurs in all materials. Even the thickest cargos of any material attenuate these {gamma}-rays by only a factor of 10-30X so that the signature is readily detected even with the most challenging shield materials. The goals of the current program are to detect significant quantities (much less than IAEA ''significant'' amounts) of well-shielded SNM, and to do so with detection probability P{sub d} {ge} 95% and with false alarm rates P{sub fp} {le} 0.001. It is the goal to meet these requirements in a scan that requires less than one minute to complete and does so without damage to the cargo or to people who may be hidden inside. We intend to meet these requirements even when the cargo overburden is up to {rho}L {le} 150 g/cm{sup 2} of any material ranging from fuels and agricultural products to steel and lead.

Prussin, S; Slaughter, D; Pruet, J; Descalle, M; Bernstein, A; Hall, J; Accatino, M; Alford, O; Asztalos, S; Church, J; Loshak, A; Madden, N; Manatt, D; Moore, T; Norman, E; Petersen, D

2005-07-29T23:59:59.000Z

204

SNM holdup assessment of Los Alamos exhaust ducts. Final report  

SciTech Connect

Fissile material holdup in glovebox and fume hood exhaust ducting has been quantified for all Los Alamos duct systems. Gamma-based, nondestructive measurements were used to quantify holdup. The measurements were performed during three measurement campaigns. The first campaign, Phase I, provided foot-by-foot, semiquantitative measurement data on all ducting. These data were used to identify ducting that required more accurate (quantitative) measurement. Of the 280 duct systems receiving Phase I measurements, 262 indicated less than 50 g of fissile holdup and 19 indicated fissile holdup of 50 or more grams. Seven duct systems were measured in a second campaign, called Series 1, Phase II. Holdup estimates on these ducts ranged from 421 g of {sup 235}U in a duct servicing a shut-down uranium-machining facility to 39 g of {sup 239}Pu in a duct servicing an active plutonium-processing facility. Measurements performed in the second campaign proved excessively laborious, so a third campaign was initiated that used more efficient instrumentation at some sacrifice in measurement quality. Holdup estimates for the 12 duct systems measured during this third campaign ranged from 70 g of {sup 235}U in a duct servicing analytical laboratories to 1 g of {sup 235}U and 1 g of {sup 239}Pu in a duct carrying exhaust air to a remote filter building. These quantitative holdup estimates support the conclusion made at the completion of the Phase I measurements that only ducts servicing shut-down uranium operations contain about 400 g of fissile holdup. No ventilation ducts at Los Alamos contain sufficient fissile material holdup to present a criticality safety concern.

Marshall, R.S.

1994-02-01T23:59:59.000Z

205

R&D for Better Nuclear Security: Radiation Detector Materials  

SciTech Connect

I am going to talk about the need for better materials for radiation detectors. I believe that government investment in this area can enable transformational technology change that could impact domestic nuclear security and also national nuclear security in some very positive and powerful ways. I'm not going to give you a lecture on how radiation detectors work, but I am going to tell you a bit about today's off-the-shelf technology and why it is not sufficient, what we need, and what security benefit you could get from improvements. I think we're at a critical point in time for some very impactful investments. In particular I'm going to focus on the use of gamma-ray radiation detectors at ports of entry. Not long before DHS was formed, Congress decreed that counter measures against the delivery of radiological and nuclear threats would be put in place at US ports of entry, under the authority of US Customs (later Customs and Border Protection in DHS). This included the screening of all cars and trucks passing through a port of entry. Existing off-the-shelf radiation detectors had to be selected for this purpose. Plans were made to make the most of the available technologies, but there are some inherent limitations of these detectors, plus the operational setting can bring out other limitations.

Kammeraad, J E

2009-04-02T23:59:59.000Z

206

Nuclear Resonance Fluorescence for Material Verification in Dismantlement  

SciTech Connect

Nuclear resonance fluorescence (NRF) is a well-established physical process that provides an isotope-specific signature that can be exploited for isotopic detection and characterization of samples. Pacific Northwest National Laboratory has been investigating possible applications of NRF for national security. Of the investigated applications, the verification of material in the dismantlement process is the most promising. Through a combination of benchmarking measurements and radiation transport modeling, we have shown that NRF techniques with existing bremsstrahlung photon sources and a modest detection system can be used to detect highly enriched uranium in the quantities and time limits relevant to the dismantlement process. Issues such as orientation, placement and material geometry do not significantly impact the sensitivity of the technique. We have also investigated how shielding of the uranium would be observed through non-NRF processes to enable the accurate assay of the material. This paper will discuss our findings on how NRF and photon-interrogation techniques may be applied to the material verification in the dismantlement process.

Warren, Glen A.; Detwiler, Rebecca S.

2011-10-01T23:59:59.000Z

207

Journal of Nuclear Materials 207 (1993) 116-122 North-Holland  

E-Print Network (OSTI)

Journal of Nuclear Materials 207 (1993) 116-122 North-Holland jomalof nuclear materials Impurity 90024, USA J.N. Brooks and A. Hassanein Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439, USA R.B. Turkot, Jr. Department of Nuclear Engineering, University of Illinois, 103 South Goodwin

Harilal, S. S.

208

S&TR | January/February 2007: Identifying the Source of Nuclear Materials  

NLE Websites -- All DOE Office Websites (Extended Search)

January/February 2007 January/February 2007 The Laboratory in the News Commentary by George H. Miller Titan Leads the Way in Laser-Matter Science Identifying the Source of Stolen Nuclear Materials Tiny Tubes Make the Flow Go Acidic Microbe Community Fosters the Unique Patents and Awards S&TR Staff Article title: Identifying the Source of Stolen Nuclear Materials; article blurb: Livermore scientists are analyzing interdicted illicit nuclear and radioactive materials for clues to the materials' origins and routes of transit. NUCLEAR forensics and attribution are becoming increasingly important tools in the fight against illegal smuggling and trafficking of radiological and nuclear materials. These include materials intended for industrial and medical use (radiological), nuclear materials such as those produced in the

209

Estimated and observed performance of a neutron SNM portal monitor for vehicles  

SciTech Connect

In July 1987, we completed our development of a neutron-detection- based vehicle SNM portal monitor with a conference paper presented at the annual meeting. The paper described the neutron vehicle portal (NVP), described source-response measurements made with it at Los Alamos, and gave our estimate of the monitor`s potential performance. Later, in December 1988, we had a chance to do a performance test with the monitor in a plant environment. This paper discusses how our original performance estimate should vary in different circumstances, and it uses the information to make a comparison between the monitor`s estimated and actual performance during the 1988 performance testing.

Fehlau, P.E.; Close, D.A.; Coop, K.L.; York, R.

1996-11-01T23:59:59.000Z

210

Nuclear Waste Storage in Gel-Derived Materials  

Science Journals Connector (OSTI)

For long life nuclear wastes (essentially actinides) research is in progress ... a process to prepare silica glass embedding the nuclear waste. Porous silica (gel) is used as a host matrix for nuclear waste. Neod...

T. Woignier; J. Reynes; J. Phalippou

2000-12-01T23:59:59.000Z

211

Advances in the Hopkinson bar testing of irradiated/non-irradiated nuclear materials and large specimens  

Science Journals Connector (OSTI)

...the twentieth century, research activity in the nuclear field of the Joint Research Centre (JRC) was concentrated on problems of nuclear reactor safety, especially...dynamic material testing programme for the high ductility...

2014-01-01T23:59:59.000Z

212

Journal of Nuclear Materials 191-194 (1992) 503-507 NorthHolland  

E-Print Network (OSTI)

Laboratory, Fusion Power Program, 9700 South Cass Avenue, Argonne, IL 60439, USA journal of nuclear materialsJournal of Nuclear Materials 191-194 (1992) 503-507 North·Holland Thermal response of substrate structural materials during a plasma disruption * Ahmed Hassanein and Dale L. Smith Argonne National

Harilal, S. S.

213

Journal of Nuclear Materials 191-194 (1992) 499-502 North-Holland  

E-Print Network (OSTI)

Journal of Nuclear Materials 191-194 (1992) 499-502 North-Holland journal of nuclear materials Analysis of sweeping heat loads on divertor plate materials * Ahmed Hassanein Argonne Nation.al Laboratory, Fusion Power Program, 9700 South Cass Anenue, Argonne, IL 60439, USA The heat flux on the divertor plate

Harilal, S. S.

214

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

Directives, Delegations, and Requirements

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

215

The Use of Smart Materials Technologies in Radiation Environment and Nuclear Industry  

E-Print Network (OSTI)

1 The Use of Smart Materials Technologies in Radiation Environment and Nuclear Industry Victor ABSTRACT Application of smart materials technology in nuclear industry offer new opportunities a unique challenge to the testing, qualification and use of smart materials. The present study assesses

Giurgiutiu, Victor

216

Neutron Detectors for Detection of Nuclear Materials at LANL...  

Office of Science (SC) Website

Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26Germantown Building 1000 Independence...

217

Radiation effects in nuclear materials: Role of nuclear and electronic energy losses and their synergy  

SciTech Connect

Ceramic oxides and carbides are promising matrices for the immobilization and/or transmutation of nuclear wastes, cladding materials for gas-cooled fission reactors and structural components for fusion reactors. For these applications there is a need of fundamental data concerning the behavior of nuclear ceramics upon irradiation. This article is focused on the presentation of a few remarkable examples regarding ion-beam modifications of nuclear ceramics with an emphasis on the mechanisms leading to damage creation and phase transformations. Results obtained by combining advanced techniques (Rutherford backscattering spectrometry and channeling, X-ray diffraction, transmission electron microscopy, Raman spectroscopy) concern irradiations in a broad energy range (from keV to GeV) with the aim of exploring both nuclear collision (Sn) and electronic excitation (Se) regimes. Finally, the daunting challenge of the demonstration of the existence of synergistic effects between Sn and Se is tackled by discussing the healing due to intense electronic energy deposition (SHIBIEC) and by reporting results recently obtained in dual-beam irradiation (DBI) experiments.

Thom, Lionel [Centre de Spectromtrie Nuclaire et de Spectromtrie de Masse, CNRS-IN2P3-Universit Paris-Sud; Debelle, Aurelien [Universite Paris Sud, Orsay, France; Garrido, Frederico [Universite Paris Sud, Orsay, France; Mylonas, Stamatis [Universite Paris Sud, Orsay, France; Dcamps, B. [Universite Paris Sud, Orsay, France; Bachelet, C. [Universite Paris Sud, Orsay, France; Sattonnay, G. [LEMHE/ICMMO, Universit Paris-Sud, Bt. Orsay, France; Moll, Sandra [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Pellegrino, S. [French Atomic Energy Commission (CEA); Miro, S. [French Atomic Energy Commission (CEA); Trocellier, P. [French Atomic Energy Commission (CEA); Serruys, Y. [French Atomic Energy Commission (CEA); Velisa, G. [French Atomic Energy Commission (CEA); Grygiel, C. [CNRS, France; Monnet, I. [CIMAP, CEA-CNRS-Universit de Caen, France; Toulemonde, Marcel [French Atomic Energy Commission (CEA), French National Centre for Scientific Research (CNRS)-ENSICAE; Simon, P. [CEMHTI, CNRS, France; Jagielski, Jacek [Institute for Electronic Materials Technology; Jozwik-Biala, Iwona [Institute for Electronic Materials Technology; Nowicki, Lech [Soltan Institute for Nuclear Studies, Swierk, Poland; Behar, M. [Instituto de Fisica, Universidade Federal do Rio Grande do Sul, Porto Alegre,; Weber, William J [ORNL; Zhang, Yanwen [ORNL; Backman, Marie [University of Tennessee, Knoxville (UTK); Nordlund, Kai [University of Helsinki; Djurabekova, Flyura [University of Helsinki

2013-01-01T23:59:59.000Z

218

E-Print Network 3.0 - active nuclear material Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

Powered by Explorit Topic List Advanced Search Sample search results for: active nuclear material Page: << < 1 2 3 4 5 > >> 1 Contact Info: Pavel Oblozinsky Summary: physics...

219

Signatures of special nuclear material: High-energy gamma rays followi ng fission  

E-Print Network (OSTI)

of Special Nuclear Material: High-Energy ? Rays Followingmaterials tested showed much longer decay times. These two features large numbers of high-energy

2003-01-01T23:59:59.000Z

220

97 percent of special nuclear material de-inventoried from LLNL | National  

National Nuclear Security Administration (NNSA)

97 percent of special nuclear material de-inventoried from LLNL | National 97 percent of special nuclear material de-inventoried from LLNL | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > 97 percent of special nuclear material de-inventoried ... 97 percent of special nuclear material de-inventoried from LLNL Posted By Office of Public Affairs

Note: This page contains sample records for the topic "nuclear material snm" 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

ARIES NDA Suite: Fully-integrated and automated nuclear material assay system for measurement of special nuclear materials  

SciTech Connect

The Advanced Retirement and Integrated Extraction System (ARIES) mission the demonstration of advanced technologies for the integrated dismantlement of surplus nuclear weapon components (pits) and the packaging of the recovered plutonium into long-term storage containers. The unclassified plutonium product is suitable for traditional international safeguards, as well as other potential inspection regimes. As indicated in the recent Secretary of Energy`s Record of Decision (ROD), this unclassified excess material is anticipated to be offered for international safeguards under the US Voluntary Offer (INFCIRC/288) performed by the International Atomic Energy Agency (TAEA). The ARIES nondestructive assay (NDA) suite offers state-of-the-art capabilities that provide highly accurate, precise material assay meeting IAEA bias defect measurement levels. Because of these levels of performance, the requirement of destructive analysis is largely removed. The unique combination of automation and high accuracy suggests the possibility of dual-use operator-owned IAEA authenticated instrumentation. Finally, the concept of continuous unattended monitoring for international safeguards applications with the ARIES NDA suite is intriguing and may encourage additional deployments of similar NDA systems internationally or elsewhere within the DOE complex.

Fearey, B.L.; Sampson, T.E.; Cremers, T.L.

1997-04-01T23:59:59.000Z

222

Test and evaluation of computerized nuclear material accounting methods. Final report  

SciTech Connect

In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

NONE

1995-12-31T23:59:59.000Z

223

Design of Nanosensors for Fissile Materials in Nuclear Waste Water  

Science Journals Connector (OSTI)

Uranium and plutonium ions and their complexes play an important role in nuclear fuel reprocessing, and their trace characterization is important in nuclear forensics. In this work, we perform ab initio density functional theory calculations of U and Pu ...

Narendra Kumar; Jorge M. Seminario

2013-10-16T23:59:59.000Z

224

Nuclear Materials Safeguards and Security Upgrade Project Completed...  

NLE Websites -- All DOE Office Websites (Extended Search)

Safeguards and Security Upgrade Project Completed Under Budget | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering...

225

Microsoft Word - Final Nuclear Materials Management and Safeguards System Users Guide 2 4-3-13.docx  

National Nuclear Security Administration (NNSA)

Nuclear Materials Management and Nuclear Materials Management and Safeguards Users Guide National Nuclear Security Administration Office of Nuclear Materials Integration Office of Nuclear Materials Integration Nuclear Materials Management and Safeguards System (NMMSS) Users Guide-Rev. 2.0 Prepared by: Department of Energy National Nuclear Security Administration Nuclear Materials Integration - NA-73 April 2013 Xavier Ascanio Office of Nuclear Materials Integration Nuclear Materials Management and 73 NMMSS User Guide 2.0 April 1, 2013 Revision History Date Revision Description October 2008 1.0 Initial release April 2013 2.0 New release NMMSS User Guide 2.0 i April 1, 2013 Table of Contents Section 1 Introduction ...................................................................................................................... 1-1

226

1Nuclear Materials Technology Division/Los Alamos National Laboratory Publications  

E-Print Network (OSTI)

, the United States had no easy way of recover- ing plutonium from its nuclear weapons with- out generating1Nuclear Materials Technology Division/Los Alamos National Laboratory 0 Publications Nuclear Fuels-Dehydride Recycle Process for Plutonium Recovery 4-5 Electrolytic Decontamination of Oralloy 6 Applied Weapons

227

Summary of "Materials Modeling and Simulations for Nuclear Fuels"  

NLE Websites -- All DOE Office Websites (Extended Search)

Summary of "Materials Modeling and Simulations for Nuclear Fuels" Summary of "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Workshop Summary Presentation during MMSNF Workshop in Chicago

228

A demonstration of variance and covariance calculations using MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator)  

SciTech Connect

Good decision-making in materials accounting requires a valid calculation of control limits and detection sensitivity for facilities handling special nuclear materials (SNM). A difficult aspect of this calculation is determining the appropriate variance and covariance values for the terms in the materials balance (MB) equation. Computer software such as MAVARIC (Materials Accounting VARIance Calculator) and PROFF (PROcessing and Fuel Facilities calculator) can efficiently select and combine variance terms. These programs determine the variance and covariance of an MB equation by first obtaining relations for the variance and covariance of each term in the MB equation through propagating instrument errors and then substituting the measured quantities and their uncertainties into these relations. MAVARIC is a custom spreadsheet used with the second release of LOTUS 1-2-3.** PROFF is a stand-alone menu-driven program requiring no commercial software. Programs such as MAVARIC and PROFF facilitate the complex calculations required to determine the detection sensitivity of an SNM facility. These programs can also be used to analyze materials accounting systems.

Barlich, G.L.; Nasseri, S.S.

1990-01-01T23:59:59.000Z

229

A Safeguards Design Strategy for Domestic Nuclear Materials Processing Facilities.  

E-Print Network (OSTI)

?? The outdated and oversized nuclear manufacturing complex within the United States requires its transformation into a smaller, safe, and secure enterprise. Health and safety (more)

Long, Jonathan

2010-01-01T23:59:59.000Z

230

Office of Weapons Material Protection | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

that gradually transfers responsibility for maintaining the security systems to Russia. Related Topics material protection MPC&A SLD second line of defense weapons material...

231

A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Busy Year Securing Vulnerable Nuclear Material and Making the A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer January 7, 2011 - 6:22pm Addthis John Schueler John Schueler Former New Media Specialist, Office of Public Affairs This holiday season was certainly a busy one for the National Nuclear Security Administration (NNSA). While many Americans were off completing last minute Christmas shopping and spending time with loved ones, the team at NNSA was working around the clock to secure over 50 kilograms of highly enriched uranium from three sites in the Ukraine. As part of President Obama's ambitious plan to secure all vulnerable nuclear material around the world in four years, NNSA assisted in repatriating the dangerous

232

EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4: Resumption of Transient Testing of Nuclear Fuels and 4: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho SUMMARY This Environmental Assessment (EA) evaluates U.S. Department of Energy (DOE) activities associated with its proposal to resume testing of nuclear fuels and materials under transient high-power test conditions at the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory. The State of Idaho and Shoshone-Bannock Tribes are cooperating agencies. PUBLIC COMMENT OPPORTUNITIES DOE invites the public to read and comment on a draft environmental assessment it has prepared for a proposal to resume transient testing of nuclear fuels and materials at either Idaho National Laboratory or Sandia

233

U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Works With Kazakhstan to Stop Nuclear and Radioactive Material Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling May 6, 2006 - 10:34am Addthis WASHINGTON, DC - As part of the overall U.S. strategy to prevent nuclear and dangerous radiological materials from falling into the hands of terrorists, the Department of Energy's National Nuclear Security Administration (NNSA) announced today that an agreement with the government of Kazakhstan had been signed to create a partnership under the Second Line of Defense program. U.S. Ambassador Ordway joined Kazakhstan Customs Control Committee Chairman Askar Shakirov in signing the accord. The agreement will pave the way for NNSA to work collaboratively with the Kazakhstan Customs Control Committee

234

Detecting special nuclear materials in containers using high-energy gamma rays emitted by fission products  

DOE Patents (OSTI)

A method and a system for detecting the presence of special nuclear materials in a container. The system and its method include irradiating the container with an energetic beam, so as to induce a fission in the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Norman, Eric B. (Oakland, CA); Prussin, Stanley G. (Kensington, CA)

2007-10-02T23:59:59.000Z

235

Human error contribution to nuclear materials-handling events  

E-Print Network (OSTI)

This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

Sutton, Bradley (Bradley Jordan)

2007-01-01T23:59:59.000Z

236

Neutron Detectors for Detection of Nuclear Materials at LANL| U.S. DOE  

Office of Science (SC) Website

Neutron Detectors for Detection of Neutron Detectors for Detection of Nuclear Materials at LANL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff Archives SBIR/STTR Applications of Nuclear Science and Technology Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information » Spinoff Archives Neutron Detectors for Detection of Nuclear Materials at LANL Print Text Size: A A A RSS Feeds FeedbackShare Page Application/instrumentation: Very Large Array Neutron Detector (VLAND); Development of large volume efficient neutron detectors for use in detection of small amounts (~ 1 gm)

237

First time nuclear material detection by one short-pulse-laser-driven  

NLE Websites -- All DOE Office Websites (Extended Search)

Articles » Articles » First time nuclear material detection by one short-pulse-laser-driven neutron source First time nuclear material detection by one short-pulse-laser-driven neutron source The results obtained are the first experimental demonstration of active interrogation of nuclear material by a short pulse laser driven neutron source. April 3, 2013 TRIDENT pulse The results obtained are the first experimental demonstration of active interrogation of nuclear material by a short pulse laser driven neutron source. Contact James Rickman Communications Specialist (505) 665-9203 Email A single shot interrogation of the depleted uranium sample, showed a clear signal from the delayed neutrons in the detector with uranium, compared with the background, and with the typical time behavior of delayed

238

Determination of boron in nuclear materials by isotope dilution technique. Part I  

Science Journals Connector (OSTI)

The application of the mass-spectrometric stable-isotope dilution technique for the determination of microgram and submicrogram quantities of boron in nuclear materials is described. An adequate...10B) is added t...

J. Marsel; D. Milivojevi?

1971-01-01T23:59:59.000Z

239

Detecting nuclear materials smuggling: using radiography to improve container inspection policies  

Science Journals Connector (OSTI)

This paper proposes a layered container inspection system for detecting illicit nuclear materials using radiography information. We argue that the current inspection system, relying heavily on the Automated Ta...

Gary M. Gaukler; Chenhua Li; Rory Cannaday

2011-07-01T23:59:59.000Z

240

Journal of Nuclear Materials 122 & 123 (1984) 1459-1465 North-Holland. Amsterdam  

E-Print Network (OSTI)

Journal of Nuclear Materials 122 & 123 (1984) 1459-1465 North-Holland. Amsterdam 1459 THERMAL Argonne National Laboratory, Fusion Power Program, 9700 South Cass Avenue, Argonne, Illinois 60439

Harilal, S. S.

Note: This page contains sample records for the topic "nuclear material snm" 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

A system for the detection of concealed nuclear weapons and fissile material aboard cargo cotainerships  

E-Print Network (OSTI)

A new approach to the detection of concealed nuclear weapons and fissile material aboard cargo containerships is proposed. The ship-based approach removes the constraints of current thinking by addressing the threat of ...

Gallagher, Shawn P., S.M. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

242

E-Print Network 3.0 - alamos nuclear materials Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Powered by Explorit Topic List Advanced Search Sample search results for: alamos nuclear materials Page: << < 1 2 3 4 5 > >> 1 Upper Los Alamos Canyon Project We are working...

243

SRS Completes Annual Examinations to Verify Safe Storage of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE))

AIKEN, S.C. The EM program at the Savannah River Site (SRS) recently completed an annual process in K Area that validates the sites ongoing commitment to maintaining the safety and security of nuclear materials stored there.

244

Journal of Nuclear Materials 205 (1993) 258-266 North-Holland  

E-Print Network (OSTI)

Journal of Nuclear Materials 205 (1993) 258-266 North-Holland Amorphization kinetics of Zr,Fe under, Argonne National Laboratory, Argonne, IL 60439, USA Previous investigations using 40Ar-ion bombardments alloys) of water-cooled nuclear reactors. For example, an irradia- tion-induced crystal

Motta, Arthur T.

245

Journal of Nuclear Materials 141-143 (1986) 221-225 North-Holland, Amsterdam  

E-Print Network (OSTI)

NationalLaboratory, Argonne, IL 60439-4837, USA H.M. ATTAYA, and G.L. KULCINSKI Nuclear EngineeringJournal of Nuclear Materials 141-143 (1986) 221-225 North-Holland, Amsterdam ION DEBRIS AND X-RAY ENERGY DEPOSITION AND RESPONSE OF FUSION REACTOR FIRST WALLS* A.M. HASSANEIN Fusion PowerProgram,Argonne

Harilal, S. S.

246

Journal of Nuclear Materials 195 (1992) 221-227 North-Holland  

E-Print Network (OSTI)

Journal of Nuclear Materials 195 (1992) 221-227 North-Holland Letter to the Editors Amorphization at Department of Nuclear Engineering, The Pennsyl- vania State University, 231 Sackett Building, University Park dispersive X-ray spectroscopy with a spot size of 6 nm. 3. Results It has been verified by TEM that under

Motta, Arthur T.

247

CONSTRUCTION OF WEB-ACCESSIBLE MATERIALS HANDBOOK FORGENERATION IV NUCLEAR REACTORS  

SciTech Connect

The development of a web-accessible materials handbook in support of the materials selection and structural design for the Generation IV nuclear reactors is being planned. Background of the reactor program is briefly introduced. Evolution of materials handbooks for nuclear reactors over years is reviewed in light of the trends brought forth by the rapid advancement in information technologies. The framework, major features, contents, and construction considerations of the web-accessible Gen IV Materials Handbook are discussed. Potential further developments and applications of the handbook are also elucidated.

Ren, Weiju [ORNL

2005-01-01T23:59:59.000Z

248

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

249

Audit Report on "The Department's Management of Nuclear Materials Provided to Domestic Licensees"  

SciTech Connect

The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

None

2009-02-01T23:59:59.000Z

250

Termination of Safeguards on ULWBR Material  

SciTech Connect

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 shippers 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

251

General Heat Transfer Characterization and Empirical Models of Material Storage Temperatures for the Los Alamos Nuclear Materials Storage Facility  

SciTech Connect

The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials. A fully passive cooling scheme, relying on the transfer of heat by conduction, free convection, and radiation has been proposed as a reliable means of maintaining material at acceptable storage temperatures. The storage concept involves placing radioactive materials, with a net heat-generation rate of 10 W to 20 W, inside a set of nested steel canisters. The canisters are, in placed in holding fixtures and positioned vertically within a steel storage pipe. Several hundred drywells are arranged in a linear array within a large bay and dissipate the waste heat to the surrounding air, thus creating a buoyancy driven airflow pattern that draws cool air into the storage facility and exhausts heated air through an outlet stack. In this study, an experimental apparatus was designed to investigate the thermal characteristics of simulated nuclear materials placed inside two nested steel canisters positioned vertically on an aluminum fixture plate and placed inside a section of steel pipe. The heat-generating nuclear materials were simulated with a solid aluminum cylinder containing .an embedded electrical resistance heater. Calibrated type T thermocouples (accurate to ~ O.1 C) were used to monitor temperatures at 20 different locations within the apparatus. The purposes of this study were to observe the heat dissipation characteristics of the proposed `canister/fixture plate storage configuration, to investigate how the storage system responds to changes in various parameters, and to develop and validate empirical correlations to predict material temperatures under various operating conditions

J. D. Bernardin; W. S. Gregory

1998-10-01T23:59:59.000Z

252

Fossil Energy [Corrosion and Mechanics of Materials] - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Fossil Energy Fossil Energy Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Fossil Energy Bookmark and Share Conceptual designs of advanced coal-fired combustion systems require furnaces and heat transfer surfaces that operate at much higher temperatures than those in current coal-fired power plants. The combination of elevated temperatures and hostile combustion environments necessitates the development and application of ceramic materials in these designs.

253

State-of-the-art review of materials properties of nuclear waste forms.  

SciTech Connect

The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability.

Mendel, J. E.; Nelson, R. D.; Turcotte, R. P.; Gray, W. J.; Merz, M. D.; Roberts, F. P.; Weber, W. J.; Westsik, Jr., J. H.; Clark, D. E.

1981-04-01T23:59:59.000Z

254

Management of nuclear materials in an R D environment at the Los Alamos National Laboratory  

SciTech Connect

Los Alamos National Laboratory is a multidisciplinary R D organization and, as such, its nuclear materials inventory is diverse. Accordingly, major inventories of isotopes such as Pu-238, Pu-239, Pu-242, U-235, Th, tritium, and deuterium, and lesser amounts of isotopes of Am, Cm, Np and exotic isotopes such as berkelium must be managed in accordance with Department of Energy Orders and Laboratory policies. Los Alamos also acts as a national resource for many one-of-a-kind materials which are supplied to universities, industry, and other government agencies within the US and throughout the world. Management of these materials requires effective interaction and communication with many nuclear materials custodians residing in over forty technical groups as well as effective interaction with numerous outside organizations. This paper discusses the role, philosophy, and organizational structure of Nuclear Materials Management at Los Alamos and also briefly presents results of two special nuclear materials management projects: 1- Revision of Item Description Codes for use in the Los Alamos nuclear material data base and 2- The recommendation of new economic discard limits for Pu-239. 2 refs., 1 fig.

Behrens, R.G.; Roth, S.B.; Jones, S.R.

1991-01-01T23:59:59.000Z

255

Light Water Reactors [Corrosion and Mechanics of Materials] - Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Light Water Reactors Light Water Reactors Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fatigue Testing of Carbon Steels and Low-Alloy Steels Environmentally Assisted Cracking of Ni-Base Alloys Irradiation-Induced Stress Corrosion Cracking of Austenitic Stainless Steels Steam Generator Tube Integrity Program Air Oxidation Kinetics for Zr-based Alloys Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Light Water Reactors Bookmark and Share To continue safe operation of current LWRs, the aging degradation of the

256

Fusion Energy [Corrosion and Mechanics of Materials] - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Fusion Energy Fusion Energy Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Fusion Energy Bookmark and Share Since 1995, Argonne has had primary responsibility for the development of new design rules regarding various components in a fusion reactor, particularly those subject to irradiation embrittlement. During 1998, Argonne issued the final draft of the structural design criteria for in-vessel components in the International Thermonuclear Reactor (ITER).

257

Nuclear Forensics  

NLE Websites -- All DOE Office Websites (Extended Search)

nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

258

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

SciTech Connect

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options for SFM disposition. A new method for the disposition of SFMs is described herein: the simultaneous conversion of SFMs, SNF, and other highly radioactive materials into high-level-waste (HLW) glass. The SFMs include plutonium, neptinium, americium, and {sup 233}U. The primary SFM is plutonium. The preferred SNF is degraded SNF, which may require processing before it can be accepted by a geological repository for disposal.

Forsberg, C.W.; Elam, K.R.

1995-01-31T23:59:59.000Z

259

Illicit trafficking of radiological & nuclear materials : modeling and analysis of trafficking trends and risks.  

SciTech Connect

Concerns over the illicit trafficking of radiological and nuclear materials were focused originally on the lack of security and accountability of such material throughout the former Soviet states. This is primarily attributed to the frequency of events that have occurred involving the theft and trafficking of critical material components that could be used to construct a Radiological Dispersal Device (RDD) or even a rudimentary nuclear device. However, with the continued expansion of nuclear technology and the deployment of a global nuclear fuel cycle these materials have become increasingly prevalent, affording a more diverse inventory of dangerous materials and dual-use items. To further complicate the matter, the list of nuclear consumers has grown to include: (1) Nation-states that have gone beyond the IAEA agreed framework and additional protocols concerning multiple nuclear fuel cycles and processes that reuse the fuel through reprocessing to exploit technologies previously confined to the more industrialized world; (2) Terrorist organizations seeking to acquire nuclear and radiological material due to the potential devastation and psychological effect of their use; (3) Organized crime, which has discovered a lucrative market in trafficking of illicit material to international actors and/or countries; and (4) Amateur smugglers trying to feed their families in a post-Soviet era. An initial look at trafficking trends of this type seems scattered and erratic, localized primarily to a select group of countries. This is not necessarily the case. The success with which other contraband has been smuggled throughout the world suggests that nuclear trafficking may be carried out with relative ease along the same routes by the same criminals or criminal organizations. Because of the inordinately high threat posed by terrorist or extremist groups acquiring the ingredients for unconventional weapons, it is necessary that illicit trafficking of these materials be better understood as to prepare for the sustained global development of the nuclear fuel cycle. Conversely, modeling and analyses of this activity must not be limited in their scope to loosely organized criminal smuggling, but address the problem as a commercial, industrial project for the covert development of nuclear technologies and unconventional weapon development.

York, David L.; Love, Tracia L.; Rochau, Gary Eugene

2005-01-01T23:59:59.000Z

260

Passive neutron techniques for the nondestructive assay of nuclear material  

E-Print Network (OSTI)

that the drums contained transuranic material. These results were based solely on the number of time-correlated neutron events. The gamma spectra for all three drums were inspected and no gamma ray lines corresponding to transuranic nuclides were found. Further...

Mapili, Gabriel

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation  

SciTech Connect

This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

2012-08-01T23:59:59.000Z

262

Some Possible Methods for Detection of Clandestin Production of Nuclear Materials  

SciTech Connect

When one considers the possibility of clandestine production of nuclear materials, one must consider the nature of the state. A Nuclear Weapon State (NWS) already has production facilities, and even though these might be safeguarded, the NWS could more easily hide the activities than could a Non-Nuclear Weapon State (NNWS). In this paper, some of the properties of production facilities are discussed in relation to how this would relate to vulnerability to detection. The observable and methods of detection are discussed, as well as the possibility that significant help by another country could totally eliminate one or more of the steps needed for a complete production cycle.

Marlow, Keith W.

1999-06-09T23:59:59.000Z

263

Nuclear-Fuel-Cycle Research Program: availability of geotoxic material  

SciTech Connect

This report represents an analog approach to the characterization of the environmental behavior of geotoxic waste materials (toxic material emplaced in the earth's crust) as drawn from literature on the Oklo natural fission reactors and uranium ore deposits relative to radioactive wastes, and hydrothermal metal ore deposits relative to stable toxic wastes. The natural analog data were examined in terms of mobility and immobility of selected radioactive or stable waste elements and are presented in matrix relationship with their prime geochemical variables. A numerical system of ranking those relationships for purposes of hazard-indexing is proposed. Geochemical parameters (especially oxidation/reduction potential) are apparently more potent mobilizers/immobilizers than geological or hydrological conditions in many, if not most, geologic environments for most radioactive waste elements. Heavy metal wastes, by analogy to hydrothermal ore systems and geothermal systems, are less clear in their behavior but similar geochemical patterns do apply. Depth relationships between geochemical variables and waste element behavior show some surprises. It is significantly indicated that for waste isolation, deeper is not necessarily better geochemically. Relatively shallow isolation in host rocks such as shale could offer maximum immobility. This paper provides a geochemical outline for examining analog models as well as a departure point for improved quantification of geological and geochemical indexing of toxic waste hazards.

Wachter, B.G.; Kresan, P.L.

1982-09-01T23:59:59.000Z

264

Managing nuclear materials from retired weapons: An overview of U.S. plans, programs and goals  

SciTech Connect

In September 1993, the Congressional Office of Technology Assessment (OTA) published a report entitled ``Dismantling the Bomb and Managing the Nuclear Materials``. That study evaluated the current activities as well as the future challenges inherent in retiring many thousands of nuclear weapons in the US and Russia; dismantling the warheads; and safely and securely disposing of the constituent materials.The warhead dismantlement process has been underway for a few years in both nations but long-range plans and policies are still in the early stages of development. At present both the plutonium and highly-enriched uranium removed from retired weapons is stored temporarily awaiting decisions about its ultimate fate.

Johnson, P.A. [Office of Technology Assessment, Washington, DC (United States)

1995-12-31T23:59:59.000Z

265

An adaptive simulation model for analysis of nuclear material shipping operations  

SciTech Connect

Los Alamos has developed an advanced simulation environment designed specifically for nuclear materials operations. This process-level simulation package, the Process Modeling System (ProMoS), is based on high-fidelity material balance criteria and contains intrinsic mechanisms for waste and recycle flows, contaminant estimation and tracking, and material-constrained operations. Recent development efforts have focused on coupling complex personnel interactions, personnel exposure calculations, and stochastic process-personnel performance criteria to the material-balance simulation. This combination of capabilities allows for more realistic simulation of nuclear material handling operations where complex personnel interactions are required. They have used ProMoS to assess fissile material shipping performance characteristics at the Los Alamos National Laboratory plutonium facility (TA-55). Nuclear material shipping operations are ubiquitous in the DOE complex and require the largest suite of varied personnel interacting in a well-timed manner to accomplish the task. They have developed a baseline simulation of the present operations and have estimated the operational impacts and requirement of the pit production mission at TA-55 as a result of the SSM-PEIS. Potential bottlenecks have been explored and mechanisms for increasing operational efficiency are identified.

Boerigter, S.T.; Sena, D.J.; Fasel, J.H.

1998-12-31T23:59:59.000Z

266

The History and Future of NDE in the Management of Nuclear Power Plant Materials Degradation  

SciTech Connect

The author has spent more than 25 years conducting engineering and research studies to quantify the performance of nondestructive evaluation (NDE) in nuclear power plant (NPP) applications and identifying improvements to codes and standards for NDE to manage materials degradation. This paper will review this fundamental NDE engineering/research work and then look to the future on how NDE can be optimized for proactively managing materials degradation in NPP components.

Doctor, Steven R.

2009-04-01T23:59:59.000Z

267

EIS-0220: Interim Management of Nuclear Materials at the Savannah River Site  

Energy.gov (U.S. Department of Energy (DOE))

This environmental impact statement assesses the potential environmental impacts of actions necessary to manage nuclear materials at the Savannah River Site (SRS) in Aiken, South Carolina, until decisions on their ultimate disposition are made and implemented. The Department of Energy has decided to initiate actions which will stabilize certain of the SRS materials that represent environment, safety and health vulnerabilities in their current storage condition or which may represent a vulnerability within the next 10 years.

268

Y-12 National Security Complex | Department of Energy  

Energy Savers (EERE)

weapons components, secure storage of special nuclear material (SNM), and various other nuclear weapons-related activities. Other activities include various aspects of testing...

269

March 10, 2005, Board letter forwarding Recommendation 2005-1, Nuclear Material Packaging  

NLE Websites -- All DOE Office Websites (Extended Search)

FACLLTIlEs FACLLTIlEs SAFETYBOARD John T. Conway, Chairman A.J. Eggenberger, Vice Chairman Joseph F. Bader John E. Mansfield R. Bruce Matthews 625 Indiana Avenue, NW, Suite 700, Wa5hington. D.C. 20004-2901 (202) 694-7000 March 10, 2005 The Honorable Samuel W. Bodman Secretary of Energy 1000 Independence Avenue, SW Washington, DC 20585-1000 Dear Secretary Bodman: On March 10,2005, the Defense Nuclear Facilities Safety Board (Board), in accordance with 42 U.S.C. 9 2286a(a)(5), unanimously approved Recommendation 2005- 1, Nuclear Material Packaging, which is enclosed for your consideration. This recommendation addresses issuance of a requirement that nuclear material packaging meet technically justified criteria for safe storage and handling outside of engineered contamination barriers.

270

1263Journal of Nuclear Materials 155-157 (1988) 1263-1267 North-Holland, Amsterdam  

E-Print Network (OSTI)

1263Journal of Nuclear Materials 155-157 (1988) 1263-1267 North-Holland, Amsterdam BINARY COLLISION&h-energy collision-cascade creation in SPINEL (MgA1204}. The study focuses on two aspects of cascade generation of applications in fusion reactors (e.g., wave- guides and dielectric windows). They must be used to insulate

Ghoniem, Nasr M.

271

Materials characterization capabilities at DOE Nuclear Weapons Laboratories and Production Plants  

SciTech Connect

The materials characterization and analytical chemistry capabilities at the 11 DOE Nuclear Weapons Laboratories or Production Plants have been surveyed and compared. In general, all laboratories have similar capabilities and equipment. Facilities or capabilities that are unique or that exist at only a few laboratories are described in detail.

Pyper, J.W.

1984-06-01T23:59:59.000Z

272

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors  

SciTech Connect

In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

Simos, N.

2011-05-01T23:59:59.000Z

273

Nuclear magnetic resonance of laser-polarized noble gases in molecules, materials and organisms  

SciTech Connect

Conventional nuclear magnetic resonance (NMR) spectroscopy and magnetic resonance imaging (MRI) are fundamentally challenged by the insensitivity that stems from the ordinarily low spin polarization achievable in even the strongest NMR magnets. However, by transferring angular momentum from laser light to electronic and nuclear spins, optical pumping methods can increase the nuclear spin polarization of noble gases by several orders of magnitude, thereby greatly enhancing their NMR sensitivity. This dissertation is primarily concerned with the principles and practice of optically pumped nuclear magnetic resonance (OPNMR). The enormous sensitivity enhancement afforded by optical pumping noble gases can be exploited to permit a variety of novel NMR experiments across many disciplines. Many such experiments are reviewed, including the void-space imaging of organisms and materials, NMR and MRI of living tissues, probing structure and dynamics of molecules in solution and on surfaces, and zero-field NMR and MRI.

Goodson, Boyd M.

1999-12-01T23:59:59.000Z

274

Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment, Health, Safety and Security  

Energy.gov (U.S. Department of Energy (DOE))

On December 15, Matt Moury, Associate Under Secretary, Office of Environment, Health, Safety and Security (EHSS DOE) and EHSS Office of Nuclear Safety staff met with the NRC Executive Director for Operations, the Deputy Executive Director for Operations, and the Director, Office of Nuclear Materials Safety and Safeguards to sign a nuclear safety information exchange agreement between NRC Office of Nuclear Materials Safety and Safeguards and the Office of Environment, Health, Safety and Security.

275

A Perspective on Coupled Multiscale Simulation and Validation in Nuclear Materials  

SciTech Connect

The field of nuclear materials encompasses numerous opportunities to address and ultimately solve longstanding industrial problems by improving the fundamental understanding of materials through the integration of experiments with multiscale modeling and high-performance simulation. A particularly noteworthy example is an ongoing study of axial power distortions in a nuclear reactor induced by corrosion deposits, known as CRUD (Chalk River unidentified deposits). We describe how progress is being made toward achieving scientific advances and technological solutions on two fronts. Specifically, the study of thermal conductivity of CRUD phases has augmented missing data as well as revealed new mechanisms. Additionally, the development of a multiscale simulation framework shows potential for the validation of a new capability to predict the power distribution of a reactor, in effect direct evidence of technological impact. The material- and system-level challenges identified in the study of CRUD are similar to other well-known vexing problems in nuclear materials, such as irradiation accelerated corrosion, stress corrosion cracking, and void swelling; they all involve connecting materials science fundamentals at the atomistic- and mesoscales to technology challenges at the macroscale.

M. P. Short; D. Gaston; C. R. Stanek; S. Yip

2014-01-01T23:59:59.000Z

276

Nuclear Materials  

E-Print Network (OSTI)

using some analytical expressions. Then, the SPICE model parameters are extracted using Silvaco. The

Gihan T. Sayah; Mohamed Abouelatta; Abdelhalim Zekry

277

INFCIRC/207 - Notification to the Agency of Exports and Imports of Nuclear Material  

National Nuclear Security Administration (NNSA)

INF INF INFCIRC/207 26 July 1974 International Atomic Energy Agency INFORMATION CIRCULAR GENERAL Distr. Original: ENGLISH and RUSSIAN NOTIFICATION TO THE AGENCY OF EXPORTS AND IMPORTS OF NUCLEAR MATERIAL On 11 July 1974 the Director General received letters dated 10 July from the Resident Representatives to the Agency of the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America informing him that in the interest of assisting the Agency in its safeguards activities, the Governments of these three Members had decided to provide it henceforth with information on exports and imports of nuclear material. In the light of the wish expressed at the end of these letters their text is reproduced below.

278

UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LlCENSE  

Office of Legacy Management (LM)

' ' ,' ' .:,: ' ,' ,,.. : .-: .: .A,.. :. .:,: ' .' :l:. ,:.:,. ,. ."i i..' ./. ' . : :, *:..: ,.a~ :.. ,::;: ;#j ,,. .,.' ' : 8:;) ,,> ,' UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LlCENSE pp.o-o\ 43 Licensee 1. Name spm%r ch+ti (hlqay 3. 2. Address i%si&t Building Kansas cay 5, ifissouri ~..--. 3. License No. .m4-329 I 4. Exp/rotion Date Sepikmber 30, I.962 -6. Special Nuclear:Material ~~~~SnrichedtoS~ I under this license ia the a-235 i.soto~p. one thoti (1ooo) kgs u-235 Contab$i in mani- etiched ta s$in ths U23.5 / isotope. -- 8. Authorized useFor i&e C' nwiC&. professing Of +ZXlXX enriohd IQ t0 s$-tifie u-235 isoi;ope bn, accordanoe 6th the procedures desczibed ii the, J.ic3x1m3~s ag@kations of Jme 22 andduly 28; 19%

279

Development of nuclear materials accounting for international safeguards: The past, the present, the future  

SciTech Connect

Nuclear materials accountancy was introduced as a primary safeguards measure in international safeguards from the inception of the EURATOM safeguards directorate in 1959 and IAEA safeguards in 1961 with the issuance of INFCIRC 26. As measurement technology evolved and safeguarded facilities increased in both number and size, measurement methodology requirements increased as reflected in INFCIRC 66 (Rev 2.) in 1968 and later in INFCIRC 153 in 1972. Early measurements relied heavily on chemical analysis, but in the 1960s it evolved more and more toward nondestructive assay. Future nuclear materials accountancy systems will increase in complexity, driven by larger and more complex facilities; more stringent health, safety, and environmental considerations; and unattended automation in facility operations. 15 refs.

Markin, J.T.; Augustson, R.H.; Eccleston, G.W.; Hakkila, E.A.

1991-01-01T23:59:59.000Z

280

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels  

SciTech Connect

Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

Hui Zhang; Raman P. Singh

2008-11-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Monte Carlo Modeling of Photon Interrogation Methods for Characterization of Special Nuclear Material  

SciTech Connect

This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using a Monte Carlo code system to simulate the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fissile materials. Time correlation functions between detectors were simulated for photon beam-on and photon beam-off operation. In the latter case, the correlation signal is obtained via delayed neutrons from photofission, which induce further fission chains in the nuclear material. An analysis methodology was demonstrated based on features selected from the simulated correlation functions and on the use of artificial neural networks. We show that the methodology can reliably differentiate between highly enriched uranium and plutonium. Furthermore, the mass of the material can be determined with a relative error of about 12%. Keywords: MCNP, MCNP-PoliMi, Artificial neural network, Correlation measurement, Photofission

Pozzi, Sara A [ORNL; Downar, Thomas J [ORNL; Padovani, Enrico [Nuclear Engineering Department Politecnico di Milano, Milan, Italy; Clarke, Shaun D [ORNL

2006-01-01T23:59:59.000Z

282

Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry  

SciTech Connect

The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility.

Foltman, A.; Newsom, D.; Lerner, K.

1988-01-01T23:59:59.000Z

283

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14  

SciTech Connect

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

1995-12-01T23:59:59.000Z

284

Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design  

SciTech Connect

Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program implementation as LANL moves forward into production and use of the SAVY-3000 will all be addressed. The SAVY-3000 is intended as a work horse package for the DOE complex as a vented storage container primarily for plutonium in solid form.

Stone, Timothy Amos [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

285

The Governance of Nuclear Technology  

SciTech Connect

Eisenhower's Atoms for Peace speech in 1953 is remembered for engaging the world, and the Soviet Union in particular, in a dialogue about arms control and the formulation of a nuclear regime in which national and international security concerns growing from this unprecedented emerging and frightening new weapons capability would be addressed while tapping the civilian promise of nuclear applications for the good of mankind. Out of it came a series of initiatives, leading fifteen years later to the NPT, intended to allow the growth and spread of the beneficial uses of nuclear know-how while constraining the incentives and capabilities for nuclear weapons. The last 50 years has seen a gradual spread in nations with nuclear weapons, other nations with nuclear knowledge and capabilities, and still others with nuclear weapon intentions. Still most nations of the world have forgone weapon development, most have signed and abided by the NPT, and some that have had programs or even weapons, have turned these capabilities off. Yet despite this experience, and despite a relatively successful record up to a few years ago, there is today a clear and generally recognized crisis in nuclear governance, a crisis that affects the future of all the cross-cutting civilian/security issues we have cited. The crux of this crisis is a lack of consensus among the major powers whose support of international efforts is necessary for effective governance of nuclear activities. The lack of consensus focuses on three challenges: what to do about non-compliance, what to do about non-adherence, and what to do about the possible leakage of nuclear materials and technologies to terrorist groups. Short of regaining consensus on the priority to be given to nuclear material and technology controls, it is unlikely that any international regime to control nuclear materials and technologies, let alone oversee a growth in the nuclear power sector, will be successful in the tough cases where it needs to be successful. Regaining that consensus on the other hand means alleviating some fundamental insecurity on the part of states, and weakening the hold that terrorist groups have on some state governments. This in turn requires that some fundamental issues be addressed, with recognition that these are part of a suite of complex and dynamic interactions. Among these issues are: How will states provide for their own security and other central interests while preventing further proliferation, protecting against the use of nuclear weapons, and yet allowing for the possible expansion of nuclear power?; How best can states with limited resources to fight terrorist activities and safeguard nuclear materials be assisted in securing their materials and technologies?; What is the future role of international inspections? Does the IAEA remain the right organization to carry out these tasks? If not, what are the desired characteristics of a successor agency and can there be agreement on one?; How confident can we be of nonproliferation as latent nuclear weapon capabilities spread? The policies to address these and other issues must explicitly deal with NPT members who do not observe their obligations; NPT non-members; illicit trade in SNM and weapon technologies and the possibility of a regional nuclear war.

Vergino, E S; May, M

2003-09-22T23:59:59.000Z

286

Business Ymwet Centlsaem: Enclosed is AEC Special Nuclear Material License Yo. SW-551, as  

Office of Legacy Management (LM)

c-ii 3-y c-ii 3-y !WL?DF!i 70.424 SW-551, 9s renewed AUG 9 196s cmhustian En&merin~, Inc. %.lelcar Division tYindter, Connecticut ,~ttentionr ?tr. 5. ff. Shfp,penbmg: Business Ymwet Centlsaem: Enclosed is AEC Special Nuclear Material License Yo. SW-551, as renewed. Very tTuly yours, fkmald A. Nusshauaer, Chief Saurce 4 Specfel Wcleer Yaterials Brmch Ofvision of Meterbls Licensing EnClOSUWl W W m , as renwed DISTRIBUTION: Ccaplianee, HQs 2 w/encl. H. j. McAlduff, OR00 w/encl. D. George, ?MM w/mcl. N. Dtilos, ML w/emCl, C. Luke, ML w/end. Br. RF w/encl. Div. RF w/o encl. UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LICENSE Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of Federal Regulations, Chapter 1, Part 70, "Special Nuclear Material Regulations," a license is hereby issued authorizing the licensee

287

Nuclear Waste Disposal and Strategies for Predicting Long-Term Performance of Material  

SciTech Connect

Ceramics have been an important part of the nuclear community for many years. On December 2, 1942, an historic event occurred under the West Stands of Stagg Field, at the University of Chicago. Man initiated his first self-sustaining nuclear chain reaction and controlled it. The impact of this event on civilization is considered by many as monumental and compared by some to other significant events in history, such as the invention of the steam engine and the manufacturing of the first automobile. Making this event possible and the successful operation of this first man-made nuclear reactor, was the use of forty tons of UO2. The use of natural or enriched UO2 is still used today as a nuclear fuel in many nuclear power plants operating world-wide. Other ceramic materials, such as 238Pu, are used for other important purposes, such as ceramic fuels for space exploration to provide electrical power to operate instruments on board spacecrafts. Radioisotopic Thermoelectric Generators (RTGs) are used to supply electrical power and consist of a nuclear heat source and converter to transform heat energy from radioactive decay into electrical power, thus providing reliable and relatively uniform power over the very long lifetime of a mission. These sources have been used in the Galileo spacecraft orbiting Jupiter and for scientific investigations of Saturn with the Cassini spacecraft. Still another very important series of applications using the unique properties of ceramics in the nuclear field, are as immobilization matrices for management of some of the most hazardous wastes known to man. For example, in long-term management of radioactive and hazardous wastes, glass matrices are currently in production immobilizing high-level radioactive materials, and cementious forms have also been produced to incorporate low level wastes. Also, as part of nuclear disarmament activities, assemblages of crystalline phases are being developed for immobilizing weapons grade plutonium, to not only produce environmentally friendly products, but also forms that are proliferation resistant. All of these waste forms as well as others, are designed to take advantage of the unique properties of the ceramic systems.

Wicks, G.G.

2001-03-28T23:59:59.000Z

288

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products  

DOE Patents (OSTI)

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Norman, Eric B. (Oakland, CA); Prussin, Stanley G. (Kensington, CA)

2009-01-27T23:59:59.000Z

289

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products  

DOE Patents (OSTI)

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Norman, Eric B. (Oakland, CA); Prussin, Stanley G. (Kensington, CA)

2009-01-06T23:59:59.000Z

290

Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products  

DOE Patents (OSTI)

A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

2009-05-05T23:59:59.000Z

291

Monitoring Thermal Fatigue Damage In Nuclear Power Plant Materials Using Acoustic Emission  

SciTech Connect

Proactive aging management of nuclear power plant passive components requires technologies to enable monitoring and accurate quantification of material condition at early stages of degradation (i.e., pre-macrocrack). Acoustic emission (AE) is well-suited to continuous monitoring of component degradation and is proposed as a method to monitor degradation during accelerated thermal fatigue tests. A key consideration is the ability to separate degradation responses from external sources such as water spray induced during thermal fatigue testing. Water spray provides a significant background of acoustic signals, which can overwhelm AE signals caused by degradation. Analysis of AE signal frequency and energy is proposed in this work as a means for separating degradation signals from background sources. Encouraging results were obtained by applying both frequency and energy filters to preliminary data. The analysis of signals filtered using frequency and energy provides signatures exhibiting several characteristics that are consistent with degradation accumulation in materials. Future work is planned to enable verification of the efficacy of AE for thermal fatigue crack initiation detection. While the emphasis has been placed on the use of AE for crack initiation detection during accelerated aging tests, this work also has implications with respect to the use of AE as a primary tool for early degradation monitoring in nuclear power plant materials. The development of NDE tools for characterization of aging in materials can also benefit from the use of a technology such as AE which can continuously monitor and detect crack initiation during accelerated aging tests.

Meyer, Ryan M.; Ramuhalli, Pradeep; Watson, Bruce E.; Pitman, Stan G.; Roosendaal, Timothy J.; Bond, Leonard J.

2012-04-26T23:59:59.000Z

292

Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels  

SciTech Connect

The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the centers investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradiation-induced defects and microstructures. The centers research thus includes modeling and measurement of thermal transport in oxide fuels with different levels of impurities, lattice disorder and irradiation-induced microstructure, as well as theoretical and experimental investigation of the evolution of disorder, stoichiometry and microstructure in nuclear fuel under irradiation. With the premise that thermal transport in irradiated UO2 is a phonon-mediated energy transport process in a crystalline material with defects and microstructure, a step-by-step approach will be utilized to understand the effects of types of defects and microstructures on the collective phonon dynamics in irradiated UO2. Our efforts under the thermal transport thrust involved both measurement of diffusive phonon transport (an approach that integrates over the entire phonon spectrum) and spectroscopic measurements of phonon attenuation/lifetime and phonon dispersion. Our distinct experimental efforts dovetail with our modeling effort involving atomistic simulation of phonon transport and prediction of lattice thermal conductivity using the Boltzmann transport framework.

Todd R. Allen, Director

2011-04-01T23:59:59.000Z

293

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

SciTech Connect

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

294

Compatibility of Space Nuclear Power Plant Materials in an Inert He/Xe Working Gas Containing Reactive Impurities  

SciTech Connect

A major materials selection and qualification issue identified in the Space Materials Plan is the potential for creating materials compatibility problems by combining dissimilar reactor core, Brayton Unit and other power conversion plant materials in a recirculating, inert He/Xe gas loop containing reactive impurity gases. Reported here are results of equilibrium thermochemical analyses that address the compatibility of space nuclear power plant (SNPP) materials in high temperature impure He gas environments. These studies provide early information regarding the constraints that exist for SNPP materials selection and provide guidance for establishing test objectives and environments for SNPP materials qualification testing.

MM Hall

2006-01-31T23:59:59.000Z

295

Radiation Resistance of Structural Materials of Nuclear Reactors on Irradiation with High-Energy Hydrogen and Helium Ions  

Science Journals Connector (OSTI)

Basic principles of determination of the radiation resistance of structural materials of nuclear reactors with implantation of high-energy hydrogen and helium atoms have been presented. ... them with hydrogen and...

F. F. Komarov; A. F. Komarov; Vl. V. Pil?ko

2013-11-01T23:59:59.000Z

296

Audit Report - The Department of Energy's Management of Surplus Nuclear Materials, OAS-L-13-04  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management Management of Surplus Nuclear Materials OAS-L-13-04 January 2013 MEMORANDUM FOR THE DIRECTOR INTEGRATION ADMINISTRATION FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION Management of Surplus Nuclear Materials BACKGROUND A primary mission of the Department of Energy design, build and test the Nation' Department's complex was devoted to the production and fabrication of n components. With the end of the C suspended or shutdown. Because Department did not make long term plans for storage or permanent disposition of material, including material that In 2005, the Department chartered

297

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue Universitys Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called Users Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. Users week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

298

Implementation of focused ion beam (FIB) system in characterization of nuclear fuels and materials  

SciTech Connect

Beginning in 2007, a program was established at the Idaho National Laboratory to update key capabilities enabling microstructural and micro-chemical characterization of highly irradiated and/or radiologically contaminated nuclear fuels and materials at scales that previously had not been achieved for these types of materials. Such materials typically cannot be contact handled and pose unique hazards to instrument operators, facilities, and associated personnel. One of the first instruments to be acquired was a Dual Beam focused ion beam (FIB)-scanning electron microscope (SEM) to support preparation of transmission electron microscopy and atom probe tomography samples. Over the ensuing years, techniques have been developed and operational experience gained that has enabled significant advancement in the ability to characterize a variety of fuel types including metallic, ceramic, and coated particle fuels, obtaining insights into in-reactor degradation phenomena not obtainable by any other means. The following article describes insights gained, challenges encountered, and provides examples of unique results obtained in adapting Dual Beam FIB technology to nuclear fuels characterization.

A. Aitkaliyeva; J. W. Madden; B. D. Miller; J I Cole; T A Hyde

2014-10-01T23:59:59.000Z

299

Cost-Sensitive Classification Methods for the Detection of Smuggled Nuclear Material in Cargo Containers  

E-Print Network (OSTI)

of the container, much like the radiation portal monitors currently in place [24]. For a localized source placed in the center of the cargo container, the near- est detector will be approximately 4 ft away and radiation may have to pass through a significant... with the cargo. This introduces a significant statistical variation to our measurement data, as will be shown in Ch. VI. 4 I.1.3 Current Detection Methods There are several detection systems currently in use to detect nuclear material ? fixed radiation portal...

Webster, Jennifer B

2013-07-09T23:59:59.000Z

300

Trafficking of nuclear materials from the former Soviet Union news abstracts  

SciTech Connect

This report was generated to provide a background for understanding the type and variety of smuggling incidents that have been reported. As discussed in the Site Prioritization report, smuggling cases provide insight into the activities of what has been called ''amateur smuggling'', that is, smugglers who do not belong to a professional smuggling gang. In many instances, the law enforcement officials giving the press release are not familiar with nuclear materials, and give incorrect identification. The other portions of the information, such as number of individuals involved, places, and modes of operation are likely to be more correct.

Erickson, S A; Lawson, T M

1999-08-31T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.  

SciTech Connect

A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron, hydroxyapatite, magnesium oxide, and others. As the contaminant moves through the reactive material, the contaminant is either sorbed by the reactive material or chemically reacts with the material to form a less harmful substance. Because of the high risk associated with failure of a geological repository for nuclear waste, most nations favor a near-field multibarrier engineered system using backfill materials to prevent release of radionuclides into the surrounding groundwater.

Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt)

2003-10-01T23:59:59.000Z

302

Fusion Nuclear Schience Facility-AT: A Material And Component Testing Device  

SciTech Connect

A Fusion Nuclear Science Facility (FNSF) is a necessary complement to ITER, especially in the area of materials and components testing, needed for DEMO design development. FNSF-AT, which takes advantage of advanced tokamak (AT) physics should have neutron wall loading of 1-2 MW/m2, continuous operation for periods of up to two weeks, a duty factor goal of 0.3 per year and an accumulated fluence of 3-6 MW-yr/m2 (~30-60 dpa) in ten years to enable the qualification of structural, blanket and functional materials, components and corresponding ancillary equipment necessary for the design and licensing of a DEMO. Base blankets with a ferritic steel structure and selected tritium blanket materials will be tested and used for the demonstration of tritium sufficiency. Additional test ports at the outboard mid-plane will be reserved for test blankets with advanced designs or exotic materials, and electricity production for integrated high fluence testing in a DT fusion spectrum. FNSF-AT will be designed using conservative implementations of all elements of AT physics to produce 150-300 MW fusion power with modest energy gain (Q<7) in a modest sized normal conducting coil device. It will demonstrate and help to select the DEMO plasma facing, structural, tritium breeding, functional materials and ancillary equipment including diagnostics. It will also demonstrate the necessary tritium fuel cycle, design and cooling of the first wall chamber and divertor components. It will contribute to the knowledge on material qualification, licensing, operational safety and remote maintenance necessary for DEMO design

Wong, C. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, Ron; Sawan, M.; Kurtz, Richard J.; Merrill, Brad

2012-07-01T23:59:59.000Z

303

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

SciTech Connect

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

304

Trial operation of material protection, control, and accountability systems at two active nuclear material handling sites within the All-Russian Institute of Experimental Physics (VNIIEF)  

SciTech Connect

This paper discusses Russian Federal Nuclear Center (RFNC)-VNIIEF activities in the area of nuclear material protection, control, and accounting (MPC and A) procedures enhancement. The goal of such activities is the development of an automated systems for MPC and A at two of the active VNIIEF research sites: a research (reactor) site and a nuclear material production facility. The activities for MPC and A system enhancement at both sites are performed in the framework of a VNIIEF-Los Alamos National Laboratory contract with participation from Sandia National Laboratories, Lawrence Livermore National Laboratory, Brookhaven National Laboratory, Oak Ridge National Laboratory, Pacific Northwest National Laboratory, and PANTEX Plant in accordance with Russian programs supported by MinAtom. The American specialists took part in searching for possible improvement of technical solutions, ordering equipment, and delivering and testing the equipment that was provided by the Americans.

Skripka, G.; Vatulin, V.; Yuferev, V. [VNIIEF, Sarov (Russian Federation)] [and others

1997-11-01T23:59:59.000Z

305

Progress toward mutual reciprocal inspections of fissile materials from dismantled nuclear weapons  

SciTech Connect

In March 1994, the United States and the Russian Federation announced their intention to conduct mutual reciprocal inspections (MRI) to confirm inventories of fissile materials from dismantled nuclear weapons. Subsequent interactions between the two countries have established the basis for an MRI regime, covering instrumentation, candidate sites for MRI, and protection of information deemed sensitive by the countries. This paper discusses progress made toward MRI, stressing measurement technologies and observables, as well as prospects for MRI implementation. An analysis is presented of observables that might be exploited to provide assurance that the material being measured could have come from a dismantled weapon rather than other sources. Instrumentation to exploit these observables will also be discussed, as will joint US/Russian efforts to demonstrate such instrumentation. Progress toward a so-called ``program of cooperation`` between the two countries in protecting each other`s sensitive information will be reviewed. All of these steps are essential components of an eventual comprehensive regime for controlling fissile materials from weapons.

Johnson, M.W. [Los Alamos National Lab., NM (United States); Gosnell, T.B. [Lawrence Livermore National Lab., CA (United States)

1995-08-01T23:59:59.000Z

306

Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition  

SciTech Connect

Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

2001-06-01T23:59:59.000Z

307

Virtual real-time inspection of nuclear material via VRML and secure web pages  

SciTech Connect

Sandia National Laboratories` Straight Line project is working to provide the right sensor information to the right user to enhance the safety, security, and international accountability of nuclear material. One of Straight Line`s efforts is to create a system to securely disseminate this data on the Internet`s World-Wide-Web. To make the user interface more intuitive, Sandia has generated a three dimensional VRML (virtual reality modeling language) interface for a secure web page. This paper will discuss the implementation of the Straight Line secure 3-D web page. A discussion of the ``pros and cons`` of a 3-D web page is also presented. The public VRML demonstration described in this paper can be found on the Internet at the following address: http://www.ca.sandia.gov/NMM/. A Netscape browser, version 3 is strongly recommended.

Nilsen, C.; Jortner, J.; Damico, J.; Friesen, J.; Schwegel, J.

1997-04-01T23:59:59.000Z

308

FY05 LDRD Final Report Sensor Fusion for Regional Monitoring of Nuclear Materials with Ubiquitous Detection  

SciTech Connect

The detection of the unconventional delivery of a nuclear weapon or the illicit transport of fissile materials is one of the most crucial, and difficult, challenges facing us today in national security. A wide array of radiation detectors are now being deployed domestically and internationally to address this problem. This initial deployment will be followed by radiation detection systems, composed of intelligent, networked devices intended to supplement the choke-point perimeter systems with more comprehensive broad-area, or regional coverage. Cataloging and fusing the data from these new detection systems will clearly be one of the most significant challenges in radiation-based security systems. We present here our results from our first 6 months of effort on this project. We anticipate the work will continue as part of the Predictive Knowledge System Strategic Initiative.

Labov, S E; Craig, W W

2006-02-15T23:59:59.000Z

309

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network  

SciTech Connect

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-10-28T23:59:59.000Z

310

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network  

SciTech Connect

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

311

Novel Problems Associated with Accounting and Control of Nuclear Material from Decontamination and Decommissioning and in Waste  

SciTech Connect

Abstract The reduction in nuclear arms and the production facilities that supported the weapons programs have produced some unique problems for nuclear material control and accountability (MC&A). Many of these problems are not limited to the weapons complex, but have the potential to appear in many legacy facilities as they undergo dismantlement and disposal. Closing facilities find that what was previously defined as product has become a waste stream bringing regulatory, human, and technological conflict. The sometimes unique compositions of these materials produce both storage and measurement problems. The nuclear material accounting and control programs have had to become very adaptive and preemptive to ensure control and protection is maintained. This paper examines some of the challenges to Safeguards generated by deinventory, decontamination decommissioning, dismantlement, demolition, and waste site remediation from predictable sources and some from unpredictable sources. 1.0 Introduction The United States is eliminating many facilities that support the nuclear weapons program. With the changing political conditions around the world and changes in military capabilities, the decreased emphasis on nuclear weapons has eliminated the need for many of the aging facilities. Additionally, the recovery of plutonium from dismantled weapons and reuse of components has eliminated the need to produce more plutonium for the near future. Because the nuclear weapons program and commercial applications generally do not mix in the United States, the facilities in the DOE complex that no longer have a weapon mission are being deinventoried, decontaminated, decommissioned, and dismantled/demolished. The materials from these activities are then disposed of in various ways but usually in select waste burial sites. Additionally, the waste in many historical burial sites associated with the weapons complex are being recovered, repackaged if necessary, and disposed of in either geological sites or low-level waste sites. The type of waste from the decontamination and decommissioning (D&D) activities varies from uncontaminated construction materials to nuclear weapon components. This variety of forms, types, and composition of nuclear material presents many challenges to MC&A. It requires the creative application of regulations, but current regulations are adequate to ensure the security and control of the nuclear material. This paper examines some of the approaches used to meet regulatory requirements and problems that occurred during D&D. Experiences are drawn for the Hanford site and elsewhere in the DOE complex.

Schlegel, Steven C.

2007-07-10T23:59:59.000Z

312

Selection of candidate canister materials for high-level nuclear waste containment in a tuff repository  

SciTech Connect

A repository located at Yucca Mountain at the Nevada Test Site is a potential site for permanent geological disposal of high-level nuclear waste. The repository can be located in a horizon in welded tuff, a volcanic rock, which is above the static water level at this site. The environmental conditions in this unsaturated zone are expected to be air and water vapor dominated for much of the containment period. Type 304L stainless steel is the reference material for fabricating canisters to contain the solid high-level wastes. Alternative stainless alloys are considered because of possible susceptibility of 304L to localized and stress forms of corrosion. For the reprocessed glass wastes, the canisters serve as the recipient for pouring the glass with the result that a sensitized microstructure may develop because of the times at elevated temperatures. Corrosion testing of the reference and alternative materials has begun in tuff-conditioned water and steam environments. 21 references, 8 figures, 8 tables.

McCright, R.D.; Weiss, H.; Juhas, M.C.; Logan, R.W.

1983-11-01T23:59:59.000Z

313

International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings  

SciTech Connect

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

Not Available

1984-06-01T23:59:59.000Z

314

Amended Record of Decision for the Interim Management of Nuclear Materials (DOE/EIS-0220) (1/26/01)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

88 88 Federal Register / Vol. 66, No. 18 / Friday, January 26, 2001 / Notices 1 A ''pit'' is a nuclear weapon component. 2 A physical blend of uranium oxide and plutonium oxide. DEPARTMENT OF ENERGY Interim Management of Nuclear Materials AGENCY: Department of Energy ACTION: Amended record of decision. SUMMARY: On December 12, 1995, the U.S. Department of Energy (DOE) issued a Record of Decision (ROD) and Notice of Preferred Alternatives, 60 FR 65300 (December 19, 1995), for the final environmental impact statement, Interim Management of Nuclear Materials (IMNM EIS) (DOE/EIS-0220, October 20, 1995), at the Savannah River Site (SRS), Aiken, South Carolina. As part of its decision, DOE decided to construct a new facility, the Actinide Packaging and Storage Facility (APSF), to prepare, package, and store

315

Fundamental Processes of Coupled Radiation Damage and Mechanical Behavior in Nuclear Fuel Materials for High Temperature Reactors  

SciTech Connect

The objective of this work has been to elucidate the relationship among microstructure, radiation damage and mechanical properties for nuclear fuel materials. As representative nuclear materials, we have taken an hcp metal (Mg as a generic metal, and Ti alloys for fast reactors) and UO2 (representing fuel). The degradation of the thermo-mechanical behavior of nuclear fuels under irradiation, both the fissionable material itself and its cladding, is a longstanding issue of critical importance to the nuclear industry. There are experimental indications that nanocrystalline metals and ceramics may be more resistant to radiation damage than their coarse-grained counterparts. The objective of this project look at the effect of microstructure on radiation damage and mechanical behavior in these materials. The approach to be taken was state-of-the-art, large-scale atomic-level simulation. This systematic simulation program of the effects of irradiation on the structure and mechanical properties of polycrystalline Ti and UO2 identified radiation damage mechanisms. Moreover, it will provided important insights into behavior that can be expected in nanocrystalline microstructures and, by extension, nanocomposites. The fundamental insights from this work can be expected to help in the design microstructures that are less susceptible to radiation damage and thermomechanical degradation.

Simon Phillpot; James Tulenko

2011-09-08T23:59:59.000Z

316

Workshop materials from the 2nd international training course on physical protection of nuclear facilities and materials, Module 13  

SciTech Connect

This course is intended for representatives of countries where nuclear power is being developed and whose responsibilities include the preparation of regulation and the design and evaluation of physical protection systems. This is the second of two volumes; the first volume is SAND-79-1090. (DLC)

Martin, F. P. [ed.

1980-04-01T23:59:59.000Z

317

LYNX: An unattended sensor system for detection of gamma-ray and neutron emissions from special nuclear materials  

SciTech Connect

This manuscript profiles an unattended and fully autonomous detection system sensitive to gamma-ray and neutron emissions from special nuclear material. The LYNX design specifically targets applications that require radiation detection capabilities but possess little or no infrastructure. In these settings, users need the capability to deploy sensors for extended periods of time that analyze whatever signal-starved data can be captured, since little or no control may be exerted over measurement conditions. The fundamental sensing elements of the LYNX system are traditional NaI(Tl) and 3He detectors. The new developments reported here center on two themes: low-power electronics and computationally simple analysis algorithms capable of discriminating gamma-ray signatures indicative of special nuclear materials from those of naturally occurring radioactive material. Incorporating tripwire-detection algorithms based on gamma-ray spectral signatures into a low-power electronics package significantly improves performance in environments where sensors encounter nuisance sources.

Runkle, Robert C.; Myjak, Mitchell J.; Kiff, Scott D.; Sidor, Daniel E.; Morris, Scott J.; Rohrer, John S.; Jarman, Kenneth D.; Pfund, David M.; Todd, Lindsay C.; Bowler, Ryan S.; Mullen, Crystal A.

2009-01-21T23:59:59.000Z

318

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980  

SciTech Connect

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

Not Available

1980-06-25T23:59:59.000Z

319

Nuclear materials control and accountability (NMC and A) auditors in the 90's  

SciTech Connect

The increase in emphasis on the adequacy of the NMC and A internal control systems requires that management define what type of training and experience is needed by NMC and A Internal Audit Program. At Martin Marietta Energy Systems, inc. (the prime contractor for the Department of Energy at Oak Ridge, Tenn.), the Central NMC and A Manager has developed a comprehensive set of NMC and A Internal Audit policies that defines performance standards, methods of conducting audits, mechanisms for ensuring appropriate independence for NMC and A auditors, structure for standardized audit reports and working papers, and a section that addresses the development of training plans for individual NMC and A auditors. The training requirements reflect the unique combination of skills necessary to be an effective NMC and A Internal Auditor- a combination of the operational auditing skills of a Certified Internal Auditor, the accounting auditing capabilities of a Certified Public Accountant, and the specific technical knowledge base associated with nuclear materials. This paper presents a mechanism for identifying an individual training program for NMC and A auditors that considers the above requirements and the individual's long-range career goals.

Barham, M.A.; Abbott, R.R. (Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States))

1991-01-01T23:59:59.000Z

320

High Temperature Materials for Nuclear Fast Fission and Fusion Reactors and Advanced Fossil Power Plants  

Science Journals Connector (OSTI)

Development of materials plays a crucial role in the economic feasibility of fast nuclear fission and fusion power plant. In order to meet this objective, one of the methods is to extend the fuel burnup and decreasing doubling time. The burnup is largely limited by the void swelling and creep resistances of the fuel cladding and wrapping materials. India's 500 \\{MWe\\} Prototype Fast Breeder Reactor (PFBR) is in advanced stage of construction. The major structural materials chosen for PFBR with MOX fuel are alloy D9 as fuel clad and wrapper material, 316LN austenitic stainless steel for reactor components and piping and modified 9Cr-1Mo steel for steam generator. In order to improve the burnup further, titanium, phosphorous and silicon contents in alloy D9 have been optimized for better swelling and creep resistances to develop modified version of alloy D9 as IFAC-1. Creep resistance of inherently void swelling resistance 9Cr-ferritic steel has been improved with the dispersion of nano-size yttria to develop oxide dispersion strengthened (ODS) steel clad tube with long- term creep strength, similar to D9, for increasing the fuel burnup. Development of modified 9Cr-1Mo steel clad tube and 9Cr-1Mo steel wrapper for future metallic fuel reactors being developed for reducing the doubling time are in progress. Extensive studies on resistance of this new generation core materials to void swelling are also under progress along with material development. Improved versions of 316LN stainless steel with nitrogen content of about 0.14 wt.% having higher creep strength to increase the life of fast reactor and modified 9Cr-1Mo steel with reduced nitrogen content and controlled addition of boron to improve type IV cracking resistance for steam generator are other developments. India's participation in ITER programme necessitates the development of India-specific RAFM steel for Test Blanket Module (TBM). A comprehensive research programme is being carried out to develop India-specific 9Cr-W-Ta RAFM steel with the optimization of tungsten and tantalum contents for better combination of strength and toughness. Based of the extensive mechanical tests including impact, tensile, creep and fatigue on four heats of RAFM steels having tungsten in the range 1 2 wt. % and tantalum in the range 0.06 -.014 wt., the RAFM steel having 1.4 wt. % tungsten with 0.06 wt. % tantalum is found to possess better combination of strength and toughness. This steel is considered as India-specific RAFM steel and TBM is being manufactured by this RAFM steel. To limit the emission of green house gases, a research and development programme has been initiated to develop advanced ultra super critical fossil fuel fired thermal power plants working at temperature of around 973 K and pressure of 300 bar. High temperature creep strength super 304H austenitic steel and Inconel 617 superalloy tubes are indigenously developed for this purpose.

T. Jayakumar; M.D. Mathew; K. Laha

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Analysis and section of processes for the disposition of excess fissile material from nuclear weapon dismantlement in the United States  

SciTech Connect

The end of the cold war and the acceleration of nuclear disarmament efforts by the United States (US) and Russia are generating large quantities of surplus fissile nuclear materials that are no longer needed for military purposes. The safe and secure disposition of this surplus material to prevent theft or reuse in weapons has become a high priority for the US Department of Energy (USDOE). Many options exist for storage and disposition (use or disposal) of these surplus materials. The criteria, which have been developed from the basis for a preliminary ``screening`` of options, to eliminate from further consideration those options that do not meet minimal requirements. Factors, or attributes, contained in the screening and selection criteria include: (1) resistance to theft and diversion by unauthorized parties, (2) resistance to retrieval, extraction, and reuse by the host nation, (3) technical viability, (4) environmental, safety, and health impacts, (5) cost effectiveness, (6) timeliness, (7) fostering of progress and cooperation with Russia and others, (8) public and institutional acceptance, and (9) additional benefits. The evaluation of environmental impacts, in accordance with the US National Environmental Policy Ac (NEPA) process, is an integral part of the overall evaluation process. Because of the variety of physical and chemical forms of the nuclear material inventory, and because of the large number of possible disposition technologies and final forms, several hundred possible pathways to disposition have been defined and have undergone a systematic selection process. Also, because nuclear material disposition will have far ranging impacts, extensive public, in the form of public and stakeholder, input was integral to the selection process.

Myers, B.R.; Armantrout, G.A. [Lawrence Livermore National Lab., CA (United States); Erickson, R. [Los Alamos National Lab., NM (United States)

1995-02-01T23:59:59.000Z

322

NUCLEAR MATERIALTRANSACTION REPORT | Department of Energy  

Energy Savers (EERE)

NUCLEAR MATERIALTRANSACTION REPORT NUCLEAR MATERIALTRANSACTION REPORT Form used to support nuclear materials accountability and control. NUCLEAR MATERIALTRANSACTION REPORT More...

323

NUCLEAR REACTORS.  

E-Print Network (OSTI)

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

324

E-Print Network 3.0 - alternate nuclear material Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Program Summary: of electricity from nuclear power plants is far less than any of the alternative energy technologies now... Power Plants, EGRN 630 Characterization of...

325

The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging  

SciTech Connect

This dissertation presents a novel method for removing scattering effects from Nuclear Materials Identification System (NMIS) imaging. The NMIS uses fast neutron radiography to generate images of the internal structure of objects non-intrusively. If the correct attenuation through the object is measured, the positions and macroscopic cross-sections of features inside the object can be determined. The cross sections can then be used to identify the materials and a 3D map of the interior of the object can be reconstructed. Unfortunately, the measured attenuation values are always too low because scattered neutrons contribute to the unattenuated neutron signal. Previous efforts to remove the scatter from NMIS imaging have focused on minimizing the fraction of scattered neutrons which are misidentified as directly transmitted by electronically collimating and time tagging the source neutrons. The parameterized scatter removal algorithm (PSRA) approaches the problem from an entirely new direction by using Monte Carlo simulations to estimate the point scatter functions (PScFs) produced by neutrons scattering in the object. PScFs have been used to remove scattering successfully in other applications, but only with simple 2D detector models. This work represents the first time PScFs have ever been applied to an imaging detector geometry as complicated as the NMIS. By fitting the PScFs using a Gaussian function, they can be parameterized and the proper scatter for a given problem can be removed without the need for rerunning the simulations each time. In order to model the PScFs, an entirely new method for simulating NMIS measurements was developed for this work. The development of the new models and the codes required to simulate them are presented in detail. The PSRA was used on several simulated and experimental measurements and chi-squared goodness of fit tests were used to compare the corrected values to the ideal values that would be expected with no scattering. Using the PSRA resulted in an improvement of the chi-squared test by a factor of 60 or more when applied to simple homogeneous objects.

Grogan, Brandon R [ORNL

2010-03-01T23:59:59.000Z

326

THE DEVELOPMENT OF A PARAMETERIZED SCATTER REMOVAL ALGORITHM FOR NUCLEAR MATERIALS IDENTIFICATION SYSTEM IMAGING  

SciTech Connect

This report presents a novel method for removing scattering effects from Nuclear Materials Identification System (NMIS) imaging. The NMIS uses fast neutron radiography to generate images of the internal structure of objects nonintrusively. If the correct attenuation through the object is measured, the positions and macroscopic cross sections of features inside the object can be determined. The cross sections can then be used to identify the materials, and a 3D map of the interior of the object can be reconstructed. Unfortunately, the measured attenuation values are always too low because scattered neutrons contribute to the unattenuated neutron signal. Previous efforts to remove the scatter from NMIS imaging have focused on minimizing the fraction of scattered neutrons that are misidentified as directly transmitted by electronically collimating and time tagging the source neutrons. The parameterized scatter removal algorithm (PSRA) approaches the problem from an entirely new direction by using Monte Carlo simulations to estimate the point scatter functions (PScFs) produced by neutrons scattering in the object. PScFs have been used to remove scattering successfully in other applications, but only with simple 2D detector models. This work represents the first time PScFs have ever been applied to an imaging detector geometry as complicated as the NMIS. By fitting the PScFs using a Gaussian function, they can be parameterized, and the proper scatter for a given problem can be removed without the need for rerunning the simulations each time. In order to model the PScFs, an entirely new method for simulating NMIS measurements was developed for this work. The development of the new models and the codes required to simulate them are presented in detail. The PSRA was used on several simulated and experimental measurements, and chi-squared goodness of fit tests were used to compare the corrected values to the ideal values that would be expected with no scattering. Using the PSRA resulted in an improvement of the chi-squared test by a factor of 60 or more when applied to simple homogeneous objects.

Grogan, Brandon R [ORNL

2010-05-01T23:59:59.000Z

327

Leak-Path Factor Analysis for the Nuclear Materials Storage Facility  

SciTech Connect

Leak-path factors (LPFs) were calculated for the Nuclear Materials Storage Facility (NMSF) located in the Plutonium Facility, Building 41 at the Los Alamos National Laboratory Technical Area 55. In the unlikely event of an accidental fire powerful enough to fail a container holding actinides, the subsequent release of oxides, modeled as PuO{sub 2} aerosols, from the facility and into the surrounding environment was predicted. A 1-h nondestructive assay (NDA) laboratory fire accident was simulated with the MELCOR severe accident analysis code. Fire-driven air movement along with wind-driven air infiltration transported a portion of these actinides from the building. This fraction is referred to as the leak-path factor. The potential effect of smoke aerosol on the transport of the actinides was investigated to verify the validity of neglecting the smoke as conservative. The input model for the NMSF consisted of a system of control volumes, flow pathways, and surfaces sufficient to model the thermal-hydraulic conditions within the facility and the aerosol transport data necessary to simulate the transport of PuO{sub 2} particles. The thermal-hydraulic, heat-transfer, and aerosol-transport models are solved simultaneously with data being exchanged between models. A MELCOR input model was designed such that it would reproduce the salient features of the fire per the corresponding CFAST calculation. Air infiltration into and out of the facility would be affected strongly by wind-driven differential pressures across the building. Therefore, differential pressures were applied to each side of the building according to guidance found in the ASHRAE handbook using a standard-velocity head equation with a leading multiplier to account for the orientation of the wind with the building. The model for the transport of aerosols considered all applicable transport processes, but the deposition within the building clearly was dominated by gravitational settling.

Shaffer, C.; Leonard, M.

1999-06-13T23:59:59.000Z

328

Commercial nuclear fuel from U.S. and Russian surplus defense inventories: Materials, policies, and market effects  

SciTech Connect

Nuclear materials declared by the US and Russian governments as surplus to defense programs are being converted into fuel for commercial nuclear reactors. This report presents the results of an analysis estimating the market effects that would likely result from current plans to commercialize surplus defense inventories. The analysis focuses on two key issues: (1) the extent by which traditional sources of supply, such as production from uranium mines and enrichment plants, would be displaced by the commercialization of surplus defense inventories or, conversely, would be required in the event of disruptions to planned commercialization, and (2) the future price of uranium considering the potential availability of surplus defense inventories. Finally, the report provides an estimate of the savings in uranium procurement costs that could be realized by US nuclear power generating companies with access to competitively priced uranium supplied from surplus defense inventories.

NONE

1998-05-01T23:59:59.000Z

329

Title 10, Part 710 - Criteria and Procedures for Determining Eligibility for Access to Classified Matter or Special Nuclear Material  

NLE Websites -- All DOE Office Websites (Extended Search)

e-CFR Data is current as of April 7, 2008 e-CFR Data is current as of April 7, 2008 Title 10: Energy PART 710-CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO CLASSIFIED MATTER OR SPECIAL NUCLEAR MATERIAL Subpart A-General Criteria and Procedures for Determining Eligibility for Access to Classified Matter or Special Nuclear Material Source: 59 FR 35185, July 8, 1994, unless otherwise noted. General Provisions § 710.1 Purpose. (a) This subpart establishes the criteria, procedures, and methods for resolving questions concerning the eligibility of individuals who are employed by, or applicants for employment with, Department of Energy (DOE) contractors, agents, and access permittees, individuals who are DOE employees or applicants for DOE employment, and other persons designated by the Secretary of Energy, for access to Restricted Data

330

Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979  

SciTech Connect

The results of work performed from July 1, 1979 through September 30, 1979 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

Not Available

1980-03-07T23:59:59.000Z

331

The Ural Electrochemical Integrated Plant Process for Managing Equipment Intended for Nuclear Material Protection, Control and Accounting System Upgrades  

SciTech Connect

Since 1996, the Ural Electrochemical Integrated Plant (UEIP) located in the town of Novouralsk, Russia, (previously known as Sverdlovsk-44) and the United States Department of Energy (U.S. DOE) have been cooperating under the Nuclear Material Protection, Control and Accounting (MPC&A) Program. Because UEIP is involved in the processing of highly enriched uranium (HEU) into low enriched uranium (LEU), and there are highly enriched nuclear materials on its territory, the main goal of the MPC&A cooperation is to upgrade those systems that ensure secure storage, processing and transportation of nuclear materials at the plant. UEIP has completed key upgrades (equipment procurement and installation) aimed at improving MPC&A systems through significant investments made by both the U.S. DOE and UEIP. These joint cooperative efforts resulted in bringing MPC&A systems into compliance with current regulations, which led to nuclear material (NM) theft risk reduction and prevention from other unlawful actions with respect to them. Upon the U.S. MPC&A project teams suggestion, UEIP has developed an equipment inventory control process to track all the property provided through the MPC&A Program. The UEIP process and system for managing equipment provides many benefits including: greater ease and efficiency in determining the quantities, location, maintenance and repair schedule for equipment; greater assurance that MPC&A equipment is in continued satisfactory operation; and improved control in the development of a site sustainability program. While emphasizing UEIPs equipment inventory control processes, this paper will present process requirements and a methodology that may have practical and helpful applications at other sites.

Yuldashev, Rashid; Nosov, Andrei; Carroll, Michael F.; Garrett, Albert G.; Dabbs, Richard D.; Ku, Esther M.

2008-10-01T23:59:59.000Z

332

NNSAs Management of the $245 million Nuclear Materials Safeguards and Security Upgrades Project Phase II at Los Alamos National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSA's Management of the $245 NNSA's Management of the $245 Million Nuclear Materials Safeguards and Security Upgrades Project Phase II DOE/IG-0901 January 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 January 2, 2014 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Special Report on "NNSA's Management of the $245 million Nuclear Materials Safeguards and Security Upgrades Project Phase II at Los Alamos National Laboratory" BACKGROUND The National Nuclear Security Administration's Los Alamos National Laboratory (LANL) is responsible for the protection and control of a significant portion of the Nation's special nuclear

333

Test and valuation of portal monitors of nuclear material with the use of plastic scintillators and hand-held radiation detectors. Final report  

SciTech Connect

This report is the final part of work fulfilled under the contract with LANL in the cooperative program of American and Russian nuclear laboratories, aimed at strengthening the system of protection, control, and accountability of nuclear materials. Purpose of this work was to test portal and handheld monitors made by TSA Co. (USA) in order to upgrade the control of unauthorized passout of nuclear and radioactive materials from controlled territory and evaluation of possible application at Russian nuclear facility. Results of tests of PM-700SP pedestrian portal monitors and PRM-470A handheld monitors are given.

Savin, N.I. [Moskovskij Fiziko-Tekhnicheskij Inst., Moscow (Russian Federation)

1995-12-31T23:59:59.000Z

334

All-laser-driven, MeV-energy X-ray source for detection of SNM Sudeep Banerjee, Nathan Powers, Vidya Ramanathan, Nathaniel Cunningham, Nate Chandler-Smith, Shouyuan  

E-Print Network (OSTI)

All-laser-driven, MeV-energy X-ray source for detection of SNM Sudeep Banerjee, Nathan Powers, MI 48109. A quasi-monoenergetic MeV x-ray source based on laser-driven electron acceleration per laser shot. Characterization of such a high-flux high energy x-ray beam is in progress. Quasi

Umstadter, Donald

335

Materials  

NLE Websites -- All DOE Office Websites (Extended Search)

2 MAG LAB REPORTS Volume 18 No. 1 CONDENSED MATTER SCIENCE Technique development, graphene, magnetism & magnetic materials, topological insulators, quantum fl uids & solids,...

336

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging systema system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

337

THE ROLE OF STRUCTURAL MATERIALS IN THE VULNERABILITY OF NUCLEAR POWER PLANTS  

Science Journals Connector (OSTI)

The nuclear power plants (NPPs) world-wide are generally very robustly designed and constructed, capable to stand very extreme conditions. Small design differences from this point of view can be found among th...

LUIGI DEBARBERIS; KAISA SIMOLA

2006-01-01T23:59:59.000Z

338

Nuclear-quadrupole optical hole burning in the stoichiometric material EuP5O14  

Science Journals Connector (OSTI)

Hole burning, which is attributed to optical pumping of nuclear-quadrupole levels, has been observed in the stoichiometric rare-earth compound, EuP5O14. The long...

Macfarlane, R M; Genack, A Z; Weitz, D A; Shelby, R M

1980-01-01T23:59:59.000Z

339

Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.  

SciTech Connect

We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

2013-09-01T23:59:59.000Z

340

Status of materials handbooks for particle accelerator and nuclear reactor applications  

SciTech Connect

In support of research and development for accelerator applications, a materials handbook was developed in August of 1998 funded by the Accelerator Production of Tritium Project. This handbook, presently called Advanced Fuel Cycle Initiative (AFCI) Materials Handbook, Materials Data for Particle Accelerator Applications, has just issued Revision 5 and contains detailed information showing the effects of irradiation on many properties for a wide variety of materials. Development of a web-accessible materials database for Generation IV Reactor Programs has been ongoing for about three years. This handbook provides a single authoritative source for qualified materials data applicable to all Generation IV reactor concepts. A beta version of this Gen IV Materials Handbook has been completed and is presently under evaluation.

Maloy, Stuart [Los Alamos National Laboratory (LANL); Rogers, Berylene [Los Alamos National Laboratory (LANL); Ren, Weiju [ORNL; Philip, Rittenhouse [Consultant

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

US/Russian cooperative efforts in nuclear material protection, control, and accounting at the Siberian Chemical Combine  

SciTech Connect

The Siberian Chemical Combine (SKhK) is the largest multifunction nuclear production facility in the Russian nuclear complex. Until recently, it produced and processed special nuclear material for the Russian Defense Ministry. SKhK and its US partners in the Department of Energy (DOE) US/Russian Materials Protection, Control, and Accountability (MPC and A) Program are nearing completion of the initial MPC and A upgrades at the six SKhK plant sites that were begun three years ago. Comprehensive enhancements to the physical protection and access control systems are progressing on a site-wide basis while a comprehensive MC and A system is being implemented at the Radiochemical Plant site. SKhK now produces thermal and electrical power, enriches uranium for commercial reactor fuel, reprocesses irradiated fuel, converts high-enriched uranium metal into high-enriched oxide for blending into reactor-grade, low-enriched uranium, and manufactures civilian products. The authors review the progress to date and outline plans for continuing the work in 1999.

Goloskokov, I.; Yarygin, A.; Petrushev, V. [Siberian Chemical Combine, Seversk (Russian Federation); Morgado, R.E. [Los Alamos National Lab., NM (United States)] [and others

1998-12-31T23:59:59.000Z

342

Irradiation Effect on the Interface of the Composites Used as the Insulation Materials in the Nuclear Fusion Reactor  

Science Journals Connector (OSTI)

Abstract In ITER (International Thermonuclear Experimental Reactor), the insulation materials containing polymeric matrix are the most radiation-sensitive among the materials constituting the superconducting magnet in the nuclear fusion reactor. Insulation materials are fabricated by impregnating the polymeric material into the stacks of alternating layers of polyimide films and glass cloth. There are a lot of studies about irradiation property of each constituent material, whereas few studies are reported about the irradiation effect on the resin -glass cloth and the resin polyimide film boundary. In this study, we focused on the degradation of the resin-glass cloth boundary. The influence of the surface treatment and the weaving density of the glass cloth on the boundary degradation was evaluated by the mechanical properties before and after irradiation. The composite material specimens were prepared using the glass cloth with different surface treatment, and with different weaving density. The inter laminar shear strength (ILSS) test was conducted to examine the influence of the boundary on the radiation effect. In addition, the fracture mechanism were evaluated by optical micro-scope. Based on the results, it was indicated that the weaving density of the glass cloth is small influence on the irradiation effect and the radiation resistance was improved by the surface treatment.

M. Hayashi; Y. Nakata; F. Mishima; Y. Akiyama; S. Nishijima

2014-01-01T23:59:59.000Z

343

Feasibility Study of a Portable Coupled 3He Detector with LaBr3 Gamma Scintillator for Field Identification and Quantification of Nuclear Material  

E-Print Network (OSTI)

In recent years, there have been several research endeavors to increase the ability to identify and quantify special nuclear material in field measurements. These have included both gamma spectroscopy and neutron coincidence systems...

Strohmeyer, Daniel C.

2010-07-14T23:59:59.000Z

344

ELSEVIER Journal of Nuclear Materials 244 (1997) 295-304 The formation of bubbles in Zr alloys under Kr ion irradiation  

E-Print Network (OSTI)

ELSEVIER Journal of Nuclear Materials 244 (1997) 295-304 The formation of bubbles in Zr alloys under Kr ion irradiation L. Pagano Jr. a, A.T. Motta a,,, R.C. Birtcher b a Department of Nuclear,ision, Argonne National Laborato~', Argonne, IL 60439, USA Received 24 May 1996; accepted 26 November 1996

Motta, Arthur T.

345

Nuclear forward scattering vs. conventional Mossbauer studies of atomically tailored Eu-based materials.  

SciTech Connect

With the decrease in size of devices, rapid characterization of nano-devices is an inevitable necessity. It is shown that Moessbauer spectroscopy using synchrotron radiation from the advanced photon source provides such a tool of investigation. Results are presented and compared for conventional Moessbauer and Nuclear Forward Scattering for {sup 151}Eu-doped magnesium sulfide as an example, especially at low concentrations.

Konjhodzic, A.; Adamczyk, A.; Hasan, Z.; Alp, E. E.; Sturhahn, W.; Zhao, J.; Carroll, J. J.; Vagizov, F.; Univ. of Philadelphia; Youngstown State Univ.

2006-01-01T23:59:59.000Z

346

Inquiry into the De-Inventory of Special Nuclear Material at Lawrence Livermore National Laboratory, OAS-L-12-11  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Inquiry into the De-Inventory of Special Nuclear Material at Lawrence Livermore National Laboratory OAS-L-12-11 September 2012 Department of Energy Washington, DC 20585 September 21, 2012 MEMORANDUM FOR THE MANAGER, LIVERMORE SITE OFFICE FROM: David Sedillo Director, Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Special Report on "Inquiry into the De-Inventory of Special Nuclear Material at Lawrence Livermore National Laboratory" BACKGROUND The Lawrence Livermore National Laboratory (Livermore) is a Department of Energy facility managed and operated by Lawrence Livermore National Security, LLC (LLNS), for the Department's National Nuclear Security Administration (NNSA). Livermore's mission is to

347

Materials  

NLE Websites -- All DOE Office Websites (Extended Search)

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

348

Implementation Plan: Jasper Management Prestart Review (Surrogate Material Experiments)  

SciTech Connect

Able Site is located 24 km northwest of Mercury on the Nevada Test Site. The Nevada Test Site is approximately 105 km northwest of Las Vegas, NV. Major facilities at Able Site include Buildings 5100,5180, and 5191. Significant external interfaces for the JASPER site include the electrical system, wastewater system, communications systems, and water supply system, which provides both potable and fire-protection water. Support services, which are provided on the Nevada Test Site, include medical, emergency response (NTS Fire Department), radiation protection, industrial hygiene, and waste management. Although JASPER will ultimately be used for actinide research, the start-up process requires system demonstration using surrogates in place of the actinide targets. LLNL Nevada Experiments and Operations (N) Program has established a Management Prestart Review (MPR) team to determine the readiness of the JASPER personnel and facilities to initiate surrogate-material experiments. A second MPR will be conducted before actinide experiments are executed. This document addresses implementation requirements for only the first MPR. This first review coincides with the completion of authorization-basis documents and physical subsystems, which have undergone appropriate formal engineering design reviews. This MPR will affirm the quality of those reviews, their findings/resolutions, and will look most closely at systems integration requirements and demonstrations that will have undergone technical acceptance reviews before this formal MPR action. Closure of MPR findings will finalize requirements for a DOE/NV Real Estate/Operations Permit (REOP) for surrogate-material experiments. Upon completion of that experiment series and the establishment of capabilities for incorporating special nuclear material (SNM) into future experiments, the team will convene again as part of the process of authorizing those activities. A summary of the review schedule is provided.

Cooper, W.E.

2000-09-29T23:59:59.000Z

349

Energy loss of nuclear fragments in partially ionized materials of high atomic number  

Science Journals Connector (OSTI)

Methods used for the computation of the stopping power of high-atomic-number media to light and heavy nuclear fragments in un-ionized and completely ionized states are reasonably well developed. This is not the case for partially ionized states. We propose a method that bridges these two extremes and discuss applications of the method to ? particles and fission fragments in uranium at extreme temperatures and densities.

R. A. Lewis; G. A. Smith; W. S. Toothacker

1991-07-01T23:59:59.000Z

350

Standard specification for boron-Based neutron absorbing material systems for use in nuclear spent fuel storage racks  

E-Print Network (OSTI)

1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system. 1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials. 1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 0.2 % by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used. 1.4 The materials systems described herein shall be functional that is always be capable to maintain a B10 areal density such that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 depending on the design specification for the service...

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

351

GKTC ACTIVITIES TO PROVIDE NUCLEAR MATERIAL PHYSICAL PROTECTION, CONTROL AND ACCOUNTING TRAINING FOR 2011-2012  

SciTech Connect

The GKTC was created at the Kyiv Institute of Nuclear Research as a result of collaborative efforts between the United States and Ukraine. The GKTC has been designated by the Ukrainian Government to provide the MPC&A training and methodological assistance to nuclear facilities and nuclear specialists. In 2010 the GKTC has conducted the planned assessment of training needs of Ukrainian MPC&A specialists. The objective of this work is to acquire the detailed information about the number of MPC&A specialists and guard personnel, who in the coming years should receive the further advanced training. As a result of the performed training needs evaluation the GKTC has determined that in the coming years a number of new training courses need to be developed. Some training courses are already in the process of development. Also taking into account the specific of activity on the guarding of nuclear facilities, GKTC has begun to develop the specialized training courses for the guarding unit personnel. The evaluation of needs of training of Ukrainian specialists on the physical protection shows that without the technical base of learning is not possible to satisfy the needs of Ukrainian facilities, in particular, the need for further training of specialists who maintains physical protection technical means, provides vulnerability assessment and testing of technical means. To increase the training effectiveness and create the basis for specialized training courses holding the GKTC is now working on the construction of an Interior (non-classified) Physical Protection Training Site. The objective of this site is to simulate the actual conditions of the nuclear facility PP system including the complex of engineering and technical means that will help the GKTC training course participants to consolidate the knowledge and gain the practical skills in the work with PP system engineering and technical means for more effective performance of their official duties. This paper briefly describes the practical efforts applied to the provision of physical protection specialists advanced training in Ukraine and real results on the way to implement such efforts in 2011-2012.

Romanova, Olena; Gavrilyuk, Victor I.; Kirischuk, Volodymyr; Gavrilyuk-Burakova, Anna; Diakov, Oleksii; Drapey, Sergiy; Proskurin, Dmitry; Dickman, Deborah A.; Ferguson, Ken

2011-10-01T23:59:59.000Z

352

Roadmapping - A Tool for Resolving Science and Technology Issues Related to Processing, Packaging, and Shipping Nuclear Materials and Waste  

SciTech Connect

Roadmapping is an effective methodology to identify and link technology development and deployment efforts to a program's or project's needs and requirements. Roadmapping focuses on needed technical support to the baselines (and to alternatives to the baselines) where the probability of success is low (high uncertainty) and the consequences of failure are relatively high (high programmatic risk, higher cost, longer schedule, or higher ES&H risk). The roadmap identifies where emphasis is needed, i.e., areas where investments are large, the return on investment is high, or the timing is crucial. The development of a roadmap typically involves problem definition (current state versus the desired state) and major steps (functions) needed to reach the desired state. For Nuclear Materials (NM), the functions could include processing, packaging, storage, shipping, and/or final disposition of the material. Each function is examined to determine what technical development would be needed to make the function perform as desired. This requires a good understanding of the current state of technology and technology development and validation activities to ensure the viability of each step. In NM disposition projects, timing is crucial! Technology must be deployed within the project window to be of value. Roadmaps set the stage to keep the technology development and deployment focused on project milestones and ensure that the technologies are sufficiently mature when needed to mitigate project risk and meet project commitments. A recent roadmapping activity involved a 'cross-program' effort, which included NM programs, to address an area of significant concern to the Department of Energy (DOE) related to gas generation issues, particularly hydrogen. The roadmap that was developed defined major gas generation issues within the DOE complex and research that has been and is being conducted to address gas generation concerns. The roadmap also provided the basis for sharing ''lessons learned'' from R&D efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues. The gas generation roadmap identified pathways that have significant risk, indicating where more emphasis should be placed on contingency planning. Roadmapping further identified many opportunities for sharing of information and collaboration. Roadmapping will continue to be useful in keeping focused on the efforts necessary to mitigate the risk in the disposition pathways and to respond to the specific needs of the sites. Other areas within NM programs, including transportation and disposition of orphan and other nuclear materials, are prime candidates for additional roadmapping to assure achievement of timely and cost effective solutions for the processing, packaging, shipping, and/or final disposition of nuclear materials.

Luke, Dale Elden; Dixon, Brent Wayne; Murphy, James Anthony

2002-06-01T23:59:59.000Z

353

Plan of Action: JASPER Management Prestart Review (Surrogate Material Experiments)  

SciTech Connect

The Lawrence Livermore National Laboratory (LLNL) Joint Actinide Shock Physics Experimental Research (JASPER) Facility is being developed at the Nevada Test Site (NTS) to conduct shock physics experiments on special nuclear material and other actinide materials. JASPER will use a two-stage, light-gas gun to shoot projectiles at actinide targets. Projectile velocities will range from 1 to 8 km/s, inducing pressures in the target material up to 6 Mbar. The JASPER gas gun has been designed to match the critical dimensions of the two-stage, light-gas gun in Building 341 of LLNL. The goal in copying the LLNL gun design is to take advantage of the extensive ballistics database that exists and to minimize the effort spent on gun characterization in the initial facility start-up. A siting study conducted by an inter-Laboratory team identified Able Site in Area 27 of the NTS as the best location for the JASPER gas gun. Able Site consists of three major buildings that had previously been used to support the nuclear test program. In April 1999, Able Site was decommissioned as a Nuclear Explosive Assembly Facility and turned back to the DOE for other uses. Construction and facility modifications at Able Site to support the JASPER project started in April 1999 and were completed in September 1999. The gas gun and the secondary confinement chamber (SCC) were installed in early 2000. During the year, all facility and operational systems were brought on line. Initial system integration demonstrations were completed in September 2000. The facility is anticipated to be operational by August 2001, and the expected life cycle for the facility is 10 years. LLNL Nevada Experiments and Operations (N) Program has established a Management Prestart Review (MPR) team to determine the readiness of the JASPER personnel and facilities to initiate surrogate-material experiments. The review coincides with the completion of authorization-basis documents and physical subsystems, which have undergone appropriate formal engineering design reviews. This MPR will affirm the quality of those reviews, their findings/resolutions, and will look most closely at systems integration requirements and demonstrations that will have undergone technical acceptance reviews before the formal MPR action. Closure of MPR findings will finalize requirements for a DOE/NV Real Estate/Operations Permit (REOP) for surrogate-material experiments. Upon completion of that experiment series and the establishment of capabilities for incorporating SNM into future experiments, the team will convene again as part of the process of authorizing those activities.

Cooper, W.E.

2000-09-29T23:59:59.000Z

354

Plan of Action: JASPER Management Prestart Review (Surrogate Material Experiment)  

SciTech Connect

The Lawrence Livermore National Laboratory (LLNL) Joint Actinide Shock Physics Experimental Research (JASPER) Facility is being developed at the Nevada Test Site (NTS) to conduct shock physics experiments on special nuclear material and other actinide materials. JASPER will use a two-stage, light-gas gun to shoot projectiles at actinide targets. Projectile velocities will range from 1 to 8 km/s, inducing pressures in the target material up to 6 Mbar. The JASPER gas gun has been designed to match the critical dimensions of the two-stage, light-gas gun in Building 341 of LLNL. The goal in copying the LLNL gun design is to take advantage of the extensive ballistics database that exists and to minimize the effort spent on gun characterization in the initial facility start-up. A siting study conducted by an inter-Laboratory team identified Able Site in Area 27 of the NTS as the best location for the JASPER gas gun. Able Site consists of three major buildings that had previously been used to support the nuclear test program. In April 1999, Able Site was decommissioned as a Nuclear Explosive Assembly Facility and turned back to the DOE for other uses. Construction and facility modifications at Able Site to support the JASPER project started in April 1999 and were completed in September 1999. The gas gun and the secondary confinement chamber (SCC) were installed in early 2000. During the year, all facility and operational systems were brought on line. Initial system integration demonstrations were completed in September 2000. The facility is anticipated to be operational by August 2001, and the expected life cycle for the facility is 10 years. LLNL Nevada Experiments and Operations (N) Program has established a Management Prestart Review (MPR) team to determine the readiness of the JASPER personnel and facilities to initiate surrogate-material experiments. The review coincides with the completion of authorization-basis documents and physical subsystems, which have undergone appropriate formal engineering design reviews. This MPR will affirm the quality of those reviews, their findings/resolutions, and will look most closely at systems integration requirements and demonstrations that will have undergone technical acceptance reviews before the formal MPR action. Closure of MPR findings will finalize requirements for a DOE/NV Real Estate/Operations Permit (REOP) for surrogate-material experiments. Upon completion of that experiment series and the establishment of capabilities for incorporating SNM into future experiments, the team will convene again as part of the process of authorizing those activities.

Cooper, W E

2000-12-05T23:59:59.000Z

355

Characterization of depleted uranium oxides fabricated using different processing methods  

Science Journals Connector (OSTI)

Identifying both physical and chemical characteristics of Special Nuclear Material (SNM) production processes is the corner stone of nuclear forensics. Typically, processing markers are based on measuring an inte...

E. P. Hastings; C. Lewis; J. FitzPatrick

2008-05-01T23:59:59.000Z

356

Ultra-low field nuclear magnetic resonance and magnetic resonance imaging to discriminate and identify materials  

DOE Patents (OSTI)

An ultra-low magnetic field NMR system can non-invasively examine containers. Database matching techniques can then identify hazardous materials within the containers. Ultra-low field NMR systems are ideal for this purpose because they do not require large powerful magnets and because they can examine materials enclosed in conductive shells such as lead shells. The NMR examination technique can be combined with ultra-low field NMR imaging, where an NMR image is obtained and analyzed to identify target volumes. Spatial sensitivity encoding can also be used to identify target volumes. After the target volumes are identified the NMR measurement technique can be used to identify their contents.

Kraus, Robert H. (Los Alamos, NM); Matlashov, Andrei N. (Los Alamos, NM); Espy, Michelle A. (Los Alamos, NM); Volegov, Petr L. (Los Alamos, NM)

2010-03-30T23:59:59.000Z

357

Ultra-low field nuclear magnetic resonance and magnetic resonance imaging to discriminate and identify materials  

DOE Patents (OSTI)

Method comprising obtaining an NMR measurement from a sample wherein an ultra-low field NMR system probes the sample and produces the NMR measurement and wherein a sampling temperature, prepolarizing field, and measurement field are known; detecting the NMR measurement by means of inductive coils; analyzing the NMR measurement to obtain at least one measurement feature wherein the measurement feature comprises T1, T2, T1.rho., or the frequency dependence thereof; and, searching for the at least one measurement feature within a database comprising NMR reference data for at least one material to determine if the sample comprises a material of interest.

Matlashov, Andrei Nikolaevich; Urbaitis, Algis V.; Savukov, Igor Mykhaylovich; Espy, Michelle A.; Volegov, Petr Lvovich; Kraus, Jr., Robert Henry

2013-03-05T23:59:59.000Z

358

Development of Nanostructured Materials with Improved Radiation Tolerance for Advanced Nuclear Systems  

SciTech Connect

This project will explore the fundamental mechanisms through which interfaces in nanolayered structures and grain boundaries of bulk nanomaterials are able to attract and rapidly eliminate point defects and unwanted foreign species. Candidate materials that will be studied include both nanostructured multilayer composites synthesized by magnetron sputtering and structural bulk nanomaterials produced by severed plastic deformation, equal channel angular extrusion.

Zinghang Zhang; K. Ted Hartwig

2009-08-12T23:59:59.000Z

359

Qualitative and Quantitative Assessment of Nuclear Materials Contained in High-Activity Waste Arising from the Operations at the 'SHELTER' Facility  

SciTech Connect

As a result of the nuclear accident at the Chernobyl NPP in 1986, the explosion dispeesed nuclear materials contained in the nuclear fuel of the reactor core over the destroyed facilities at Unit No. 4 and over the territory immediately adjacent to the destroyed unit. The debris was buried under the Cascade Wall. Nuclear materials at the SHELTER can be characterized as spent nuclear fuel, fresh fuel assemblies (including fuel assemblies with damaged geometry and integrity, and individual fuel elements), core fragments of the Chernobyl NPP Unit No. 4, finely-dispersed fuel (powder/dust), uranium and plutonium compounds in water solutions, and lava-like nuclear fuel-containing masses. The new safe confinement (NSC) is a facility designed to enclose the Chernobyl NPP Unit No. 4 destroyed by the accident. Construction of the NSC involves excavating operations, which are continuously monitored including for the level of radiation. The findings of such monitoring at the SHELTER site will allow us to characterize the recovered radioactive waste. When a process material categorized as high activity waste (HAW) is detected the following HLW management operations should be involved: HLW collection; HLW fragmentation (if appropriate); loading HAW into the primary package KT-0.2; loading the primary package filled with HAW into the transportation cask KTZV-0.2; and storing the cask in temporary storage facilities for high-level solid waste. The CDAS system is a system of 3He tubes for neutron coincidence counting, and is designed to measure the percentage ratio of specific nuclear materials in a 200-liter drum containing nuclear material intermixed with a matrix. The CDAS consists of panels with helium counter tubes and a polyethylene moderator. The panels are configured to allow one to position a waste-containing drum and a drum manipulator. The system operates on the add a source basis using a small Cf-252 source to identify irregularities in the matrix during an assay. The platform with the source is placed under the measurement chamber. The platform with the source material is moved under the measurement chamber. The design allows one to move the platform with the source in and out, thus moving the drum. The CDAS system and radioactive waste containers have been built. For each drum filled with waste two individual measurements (passive/active) will be made. This paper briefly describes the work carried out to assess qualitatively and quantitatively the nuclear materials contained in high-level waste at the SHELTER facility. These efforts substantially increased nuclear safety and security at the facility.

Cherkas, Dmytro

2011-10-01T23:59:59.000Z

360

Creep rupture behavior of candidate materials for nuclear process heat applications  

SciTech Connect

Creep and stress rupture properties are determined for the candidate materials to be used in hightemperature gas-cooled reactor (HTGR) components. The materials and test methods are briefly described based on experimental results of test durations of about20000 h. The medium creep strengths of the alloys Inconel-617, Hastelloy-X, Nimonic-86, Hastelloy-S, Manaurite-36X, IN-519, and Incoloy-800H are compared showing that Inconel-617 has the best creep rupture properties in the temperature range above 800/sup 0/C. The rupture time of welded joints is in the lower range of the scatterband of the parent metal. The properties determined in different simulated HTGR atmospheres are within the scatterband of the properties obtained in air. Extrapolation methods are discussed and a modified minimum commitment method is favored.

Schubert, F.; te Heesen, E.; Bruch, U.; Cook, R.; Diehl, H.; Ennis, P.J.; Jakobeit, W.; Penkalla, H.J.; Ullrich, G.

1984-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Evaluation of Mechanical Properties of Nuclear Materials Using Non-Destructive Ball Indentation Technique  

SciTech Connect

Integrity of structural components depends on the deformation and fracture behavior of materials. For evaluating the material condition in-service, it is generally not feasible or practical or advisable to cut samples from operating structures. Non-destructive testing (NDT) techniques are required to evaluate the mechanical properties. Although several NDT techniques such as ultrasound, magnetic strength, Barkhausen noise, microhardness etc., are employed for estimating the mechanical property degradation, these methodologies are generally empirical and indirect. Automated Ball Indentation (ABI) is a non-destructive testing technique for direct measurement of mechanical and fracture properties of metallic engineering materials. Because of the small area over which the test is carried out, it is possible to determine point to point variations in the mechanical and fracture properties, such as those that exist in weldments. Although ABI technique is non-intrusive, it is a state-of-the-art mechanical test that measures directly the current/local deformation behavior of the material. In this paper, we present results from studies on the application of ABI technique to determine tensile and fracture properties of ferritic steels, an austenitic stainless steel, a nickel base superalloy and Zircaloy in different thermo-mechanical conditions. The effects of aging and cold work on these properties were determined from the ABI tests. Gradients in mechanical properties of ferritic steel welds, particularly in the narrow heat-affected zone, were clearly established. ABI technique was found to be useful in determining the anisotropy in the tensile properties of Zircaloy cladding tubes. The technique has potential as a non-destructive method for assessing structural integrity of aged components. (authors)

Mathew, M.D. [Indira Gandhi Center for Atomic Research, Kalpakkam, Tamil Nadu, 603102 (India); Linga Murty, K. [North Carolina State University, Nuclear Engineering Department, Raleigh, NC 27695-7909 (United States)

2002-07-01T23:59:59.000Z

362

August 17, 2005, Department letter forwarding the Department's implementation plan in response to the Board's recommendation 2005-1, Nuclear Material Packaging  

NLE Websites -- All DOE Office Websites (Extended Search)

August 17,2005 August 17,2005 The Honorable A . J. Eggenberger Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, D.C. 20004 - 2901 Dear Mr. Chairman: We are pleased to forward the enclosed Implementation Plan (Plan) for the Defense Nuclear Facilities Safety Board's (Board) Recommendation 2005-1, Nuclear Material Packaging. This Plan provides the Department's approach to ensure safe storage and handling of nuclear material at our sites. We appreciate the support provided by the Board and its staff during the development of this Plan. We will keep you informed of our progress in completing the Plan. I have assigned Mr. Richard M. Stark as the responsible manager for ensuring the Plan's successful completion. You may contact Mr. Stark at (301) 903-4407 to answer any

363

Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association  

SciTech Connect

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

Starodubtsev, G.S.; Prishchepov, A.I.; Zatorsky, Y.M.; James, L.T. [and others

1997-11-01T23:59:59.000Z

364

Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association  

SciTech Connect

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC and A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC and A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC and A systems at two plants that are operated by Mayak and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

Prishchepov, A.I.; Starodubtsev, G.S.; Zatorsky, Y.M. [Mayak Production Association, Ozersk City (Russian Federation); James, L.T. [Sandia National Labs., Albuquerque, NM (United States); Ehinger, M.H. [Oak Ridge National Lab., TN (United States); Manatt, D.R. [Lawrence Livermore National Lab., CA (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Lundgren, R.A. [Pacific Northwest National Lab., Richland, WA (United States); Suda, S.C. [Brookhaven National Lab., Upton, NY (United States)

1998-08-01T23:59:59.000Z

365

Cooperation Between the Russia Federation and the United States to Enhance the Existing Nuclear-Material Protection, Control, and Accounting Systems at Mayak Production Association  

SciTech Connect

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by lylINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at two of the plants operated by Mayak that work with proliferation-sensitive nuclear materials.

Cahalane, P.T.; Ehinger, M.H.; James, L.T.; Jarrett, J.H.; Lundgren, R.A.; Manatt, D.R.; Niederauer, G.F.; Olivos, J.D.; Prishchepov, A.I.; Starodubtsev, G.S.; Suda, S.C.; Tittemore, G.W.; Zatorsky, Y.M.

1999-07-19T23:59:59.000Z

366

Cooperative efforts to improve nuclear materials accounting, control and physical protection at the National Science Center, Kharkov Institute of Physics and Technology  

SciTech Connect

The US Department of Energy (DOE) and the Ukrainian Government are engaged in a program of cooperation to enhance the nonproliferation of nuclear weapons by developing a strong national system of nuclear material protection, control, and accounting (MPC and A). This paper describes the capabilities and work of the Kharkov Institute of Physics and Technology (KIPT) and cooperative efforts to improve MPC and A at this facility. It describes how these cooperative efforts grew out of Ukraine`s decision to become a non-nuclear weapon state and the shortcomings in MPC and A that developed at KIPT after the disintegration of the former Soviet Union. It also envisions expanded future cooperation in other areas of nuclear materials management.

Zelensky, V.F.; Mikhailov, V.A. [Kharkov Inst. of Physics and Technology (Ukraine). National Science Center

1996-12-31T23:59:59.000Z

367

Advanced Nuclear Energy Projects Solicitation | Department of...  

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

Advanced Nuclear Energy Projects Solicitation Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION Solicitation...

368

Draft Advanced Nuclear Energy Projects Solicitation | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Draft Advanced Nuclear Energy Projects Solicitation Draft Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS DRAFT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION...

369

PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations  

SciTech Connect

This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs.

Bander, T.J.

1982-11-01T23:59:59.000Z

370

Development of a system for academic training of the personnel engaged in nuclear material protection, control and accounting in Russia  

Science Journals Connector (OSTI)

The main attention in the present paper is focused on discussing the educational problems in the area of nuclear materials physical protection, control and accountability (MPC&A) in Russia. Currently, only the Master of Science Graduate Program has been completely developed for students training. This is taking place at Moscow Engineering Physics Institute (State University, MEPhI), where the sixth generation of Masters has graduated in May 2004. The MPC&A Engineer Degree Program, currently under development at MEPhI, is considered in the paper. This paper discusses specific features of the Engineer Degree training required by the Russian educational legislation and the Russian quality control system as applied to the training process. The paper summarises the main joint actions undertaken during the past three years by MEPhI in collaboration with the US Department of Energy and US National Laboratories for developing the MPC&A Engineer Degree Program in Russia.

Boris N. Onykiy; Eduard F. Kryuchkov

2005-01-01T23:59:59.000Z

371

Approach to IAEA verification of the nuclear-material balance at the Portsmouth Gas Centrifuge Enrichment Plant (GCEP)  

SciTech Connect

This paper describes a potential approach by which the International Atomic Energy Agency (IAEA) might verify the nuclear-material balance at the Portsmouth Gas Centrifuge Enrichment Plant (GCEP), should that plant be placed under IAEA safeguards. The strategy makes use of the attributes and variables measurement verification approach, whereby the IAEA would perform independent measurements on a randomly selected subset of the items comprising the U-235 flows and inventories at the plant. In addition, the MUF-D statistic is used as the test statistics for the detection of diversion. The paper includes descriptions of the potential verification activities, as well as calculations of (a) attributes and variables sample sizes for the various strata, (b) standard deviations of the relevant test statistics, and (c) the sensitivity for detection of diversion which the IAEA might achieve by this verification strategy at GCEP.

Gordon, D.M.; Sanborn, J.B.; Younkin, J.M.; DeVito, V.J.

1982-01-01T23:59:59.000Z

372

Characterization of proton exchange membrane materials for fuel cells by solid state nuclear magnetic resonance  

SciTech Connect

Solid-state nuclear magnetic resonance (NMR) has been used to explore the nanometer-scale structure of Nafion, the widely used fuel cell membrane, and its composites. We have shown that solid-state NMR can characterize chemical structure and composition, domain size and morphology, internuclear distances, molecular dynamics, etc. The newly-developed water channel model of Nafion has been confirmed, and important characteristic length-scales established. Nafion-based organic and inorganic composites with special properties have also been characterized and their structures elucidated. The morphology of Nafion varies with hydration level, and is reflected in the changes in surface-to-volume (S/V) ratio of the polymer obtained by small-angle X-ray scattering (SAXS). The S/V ratios of different Nafion models have been evaluated numerically. It has been found that only the water channel model gives the measured S/V ratios in the normal hydration range of a working fuel cell, while dispersed water molecules and polymer ribbons account for the structures at low and high hydration levels, respectively.

Kong, Zueqian

2010-03-15T23:59:59.000Z

373

Active Detection and Imaging of Nuclear Materials with High-Brightness Gamma Rays  

SciTech Connect

A Compton scattering {gamma}-ray source, capable of producing photons with energies ranging from 0.1 MeV to 0.9 MeV has been commissioned and characterized, and then used to perform nuclear resonance fluorescence (NRF) experiments. The performances of the two laser systems (one for electron production, one for scattering), the electron photoinjector, and the linear accelerator are also detailed, and {gamma}-ray results are presented. The key source parameters are the size (0.01 mm{sup 2}), horizontal and vertical divergence (6 x 10 mrad{sup 2}), duration (10 ps), spectrum and intensity (10{sup 5} photons/shot). These parameters are summarized by the peak brightness, 1.5 x 10{sup 15} photons/mm{sup 2}/mrad{sup 2}/s/0.1% bandwidth, measured at 478 keV. Additional measurements of the flux as a function of the timing difference between the drive laser pulse and the relativistic photo-electron bunch, {gamma}-ray beam profile, and background evaluations are presented. These results are systematically compared to theoretical models and computer simulations. NRF measurements performed on {sup 7}Li in LiH demonstrate the potential of Compton scattering photon sources to accurately detect isotopes in situ.

Barty, C J; Gibson, D J; Albert, F; Anderson, S G; Anderson, G G; Betts, S M; Berry, R D; Fisher, S E; Hagmann, C A; Johnson, M S; Messerly, M J; Phan, H H; Semenov, V A; Shverdin, M Y; Tremaine, A M; Hartemann, F V; Siders, C W; McNabb, D P

2009-02-26T23:59:59.000Z

374

Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository  

SciTech Connect

This paper reviews the state-of-the-art understanding of the degradation processes by the Yucca Mountain Project (YMP) with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the first 10,000-years after repository closure. This paper provides an overview of the degradation of the waste packages and drip shields in the repository after permanent closure of the facility. The degradation modes discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking, and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on the degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, and galvanic coupling to less noble metals are considered. It is concluded that the materials and design adopted will provide sufficient safety margins for at least 10,000-years after repository closure.

K.G. Mon; F. Hua

2005-04-12T23:59:59.000Z

375

Report on Follow-up Inspection of the Double Funding of Security for Special Nuclear Material at Richland Operations, IG-0378  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 1 INFORMATION: Report on "Follow-up Inspection of the Double Funding of Security for Special Nuclear Material at the Richland Operations Office" The Secretary BACKGROUND: On June 3, 1993, the Deputy Assistant Inspector General for Inspections issued a Letter Report to the Department's Acting Chief Financial Officer which stated that during Fiscal Year 1993 the Department had requested and received $60 million, double the funding needed, for the safeguard and security of special nuclear material at the Richland Operations Office. In response to that Report, the Acting Chief Financial Officer took control of the funds and placed them into a management reserve account. A follow-up inspection was initiated to:

376

Apparatus for supporting contactors used in extracting nuclear materials from liquids  

DOE Patents (OSTI)

Apparatus is provided for supporting one or more contactor stages used to remove radioactive materials from aqueous solutions. The contactor stages include a housing having an internal rotor, a motor secured to the top of the housing for rotating the rotor, and a drain in the bottom of the housing. The support apparatus includes two or more vertical members each secured to a ground support that is horizontal and perpendicular to the frame member, and a horizontally disposed frame member. The frame member may be any suitable shape, but is preferably a rectangular tube having substantially flat, spaced top and bottom surfaces separated by substantially vertical side surfaces. The top and bottom surfaces each have an opening through which the contactor housing is secured so that the motor is above the frame and the drain is below the frame during use.

Leonard, Ralph A. (River Forest, IL); Frank, Robert C. (Crestwood, IL)

1991-01-01T23:59:59.000Z

377

Advanced nuclear fuel  

SciTech Connect

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-14T23:59:59.000Z

378

Advanced nuclear fuel  

ScienceCinema (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-15T23:59:59.000Z

379

Potential hazards and artifacts of ferromagnetic and nonferromagnetic surgical and dental materials and devices in nuclear magnetic resonance imaging  

SciTech Connect

The risks to patients with metal surgical implants who are undergoing nuclear magnetic resonance (NMR) imaging and the artifacts caused by such implants were studied. Twenty-one aneurysm and other hemostatic clips and a variety of other materials (e.g., dental amalgam, 14 karat gold) were used. Longitudinal forces and torques were found to be exerted upon 16 of the 21 clips. With five aneurysm clips, forces and torques sufficient to produce risk of hemorrhage from dislocation of the clip from the vessel or aneurysm, or cerebral injury by clip displacement without dislodgement were identified. The induced ferromagnetism was shown to be related to the composition of the alloys from which the clips were manufactured. Clips with 10-14% nickel are evidently without sufficient induced ferromagnetism to cause hazard. The extent of NMR imaging artifacts was greater for materials with measurable ferromagnetic properties, but metals without measurable ferromagnetism in our tests also resulted in significant artifacts. Dental amalgam and 14 karat gold produced no imaging artifacts, but stainless steels in dentures and orthodontic braces produced extensive artifacts in the facial region.

New, P.F.J. (Massachusetts General Hospital, Boston, MA); Rosen, B.R.; Brady, T.J.; Buonanno, F.S.; Kistler, J.P.; Burt, C.T.; Hinshaw, W.S.; Newhouse, J.H.; Pohost, G.M.; Taveras, J.M.

1983-04-01T23:59:59.000Z

380

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1980-June 30, 1980  

SciTech Connect

Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850 and 950/sup 0/C. The initiation of air creep-rupture testing in the intensive screening test program is discussed. In addition, the status of the data management system is described.

Not Available

1980-11-14T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268  

SciTech Connect

Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike [Cabrera Services (United States); Matthews, Brian [Nuclear Safety Associates (United States)

2012-07-01T23:59:59.000Z

382

Summary of a joint US-Japan study of potential approaches to reduce the attractiveness of various nuclear materials for use in a nuclear explosive device by a terrorist group  

SciTech Connect

This paper summarizes the results of a joint US-Japan study to establish a mutual understanding, through scientific-based study, of potential approaches to reduce the attractiveness of various nuclear materials for use in a terrorist nuclear explosive device (NED). 4 approaches that can reduce materials attractiveness with a very high degree of effectiveness are: -) diluting HEU with natural or depleted U to an enrichment of less than 10% U-235; -) storing Pu in nuclear fuel that is not man portable and with a dose rate greater or equal to 10 Gy/h at 1 m; -) storing Pu or HEU in heavy items, i.e. not transportable, provided the removal of the Pu or HEU from the item requires a purification/processing capability; and -) converting Pu and HEU to very dilute forms (such as wastes) that, without any security barriers, would require very long acquisition times to acquire a Category I quantity of Pu or of HEU. 2 approaches that can reduce materials attractiveness with a high degree of effectiveness are: -) converting HEU-fueled research reactors into LEU-fueled research reactors or dilute HEU with natural or depleted U to an enrichment of less than 20% U-235; -) converting U/Al reactor fuel into U/Si reactor fuel. Other approaches have been assessed as moderately or totally inefficient to reduce the attractiveness of nuclear materials.

Bathke, C.G. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM (United States); Inoue, N.; Kuno, Y.; Mihara, T.; Sagara, H. [Japan Atomic Energy Agency, 4-49 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1184 (Japan); Ebbinghaus, B.B. [Lawrence Livermore National Laboratory, P.O. Box L-168, Livermore, CA 94551 (United States); Murphy, J.; Dalton, D. [National Nuclear Security Administration, Department of Energy, 1000 Independence Ave, SW, Washington, DC 20585 (United States); Nagayama, Y. [Ministry of Education, Culture, Sports, Science and Technology, 3-2-2 Kasumigaseki, Chiyoda-ku, Tokyo 100-8959 (Japan)

2013-07-01T23:59:59.000Z

383

INMM 55th Annual Meeting, July 2024, 2014, Atlanta Marriott Marquis, Atlanta, Georgia, USA Transport Security for Nuclear and Other Radioactive Materials --A DOE Training Course  

E-Print Network (OSTI)

Laboratory. The course was developed by Argonne for the U.S. Department of Energy Packaging Certification of Energy, Washington, D.C. 20585 ABSTRACT In early December of 2013, a weeklong training course on security Transport Security for Nuclear and Other Radioactive Materials -- A DOE Training Course Ronald B. Pope, Yung

Kemner, Ken

384

Sensors & Materials | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Sensors and Materials Argonne uses its materials and engineering expertise to develop, test, and deploy sensors and materials to detect nuclear and radiological materials, chemical...

385

USING TECHNOLOGY TO SUPPORT PROACTIVE MANAGEMENT OF MATERIALS DEGRADATION FOR THE U.S. NUCLEAR REGULATORY COMMISSION  

SciTech Connect

The majority of the U.S. reactor fleet is applying for license renewal to extend the operating life from the current 40 years to 60 years, and there is now active interest in extending the operating life to beyond 60 years. Many plants are also applying for increases in power rating and both of these changes increases the need for an improved understanding of materials degradation. Many materials degrade over time and much is known about the degradation of materials under normal environmental conditions; however, less is known about the characteristics of materials degradation when the environment is subject to higher than normal radiological conditions over extended periods of time. Significant efforts are being made by industrial, academic and regulatory groups worldwide to identify, classify and mitigate potential problems arising from degradation of components in this context. From a regulatory perspective, the U.S. Nuclear Regulatory Commission (USNRC) is very interested in being able to identify ways to insure their licensees proactively manage the identification of materials degradation and the mitigation of its effects. To date, the USNRC has consolidated generic programs for mitigating aging issues in the two volume Generic Aging Lessons Learned (GALL) Report (NUREG-1801) [1][2], and have encouraged applicants for license renewal to use these programs where applicable in their plant when applying for renew of their reactors license. The USNRC has also published a comprehensive report entitled Expert Panel Report on Proactive Materials Degradation (NUREG/CR-6923) [3] that inventories the types of degradation mechanisms that could exist in each component of a Light Water Reactor (LWR) and each degradation mechanism is assessed regarding how much is known about mitigating its effects. Since the number of plant designs and materials used varies greatly within the U.S. fleet, there are many variations to implementing aging management programs (AMPs), requiring significant dialogs between the Licensee and the USNRC. These discussions are part of the licensing basis and as such are documented with up to multi-hundred page responses that are loosely coupled through the USNRC Agency-wide Document Access and Management System (ADAMS), which serves as an electronic records repository for the USNRC . These discussions have supported revisions to the GALL, including the revision that is being prepared as this paper is being written. The USNRC has sought the help of the Pacific Northwest National Laboratory to improve the staffs ability to navigate the significant numbers of documents that are generated in this process and to provide a forum for regulators, licensees and researchers to share knowledge in the efforts to improve the cyclic process for defining, applying, validating and re-defining AMPs. Work to date in this area is publicly accessible and this paper will describe that work and outline a potential path forward. The presenter will also demonstrate the capabilities of the PMMD information tools (http://pmmd.pnl.gov).

Taylor, W Boyd; Knobbs, Katherine J.; Carpenter, C. E. (Gene) [Gene; Malik, Shah

2010-07-19T23:59:59.000Z

386

SRS K-AREA MATERIAL STORAGE - EXPANDING CAPABILITIES  

SciTech Connect

In support of the Department of Energys continued plans to de-inventory and reduce the footprint of Cold War era weapons material production sites, the K-Area Material Storage (KAMS) facility, located in the K-Area Complex (KAC) at the Savannah River Site reservation, has expanded since its startup authorization in 2000 to accommodate DOEs material consolidation mission. During the facilitys growth and expansion, KAMS will have expanded its authorization capability of material types and storage containers to allow up to 8200 total shipping containers once the current expansion effort completes in 2014. Recognizing the need to safely and cost effectively manage other surplus material across the DOE Complex, KAC is constantly evaluating the storage of different material types within K area. When modifying storage areas in KAC, the Documented Safety Analysis (DSA) must undergo extensive calculations and reviews; however, without an extensive and proven security posture the possibility for expansion would not be possible. The KAC maintains the strictest adherence to safety and security requirements for all the SNM it handles. Disciplined Conduct of Operations and Conduct of Projects are demonstrated throughout this historical overview highlighting various improvements in capability, capacity, demonstrated cost effectiveness and utilization of the KAC as the DOE Center of Excellence for safe and secure storage of surplus SNM.

Koenig, R.

2013-07-02T23:59:59.000Z

387

Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff  

SciTech Connect

This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

Van Konynenburg, R.A. [Lawrence Livermore National Lab., CA (USA); Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S. [CDA/INCRA Joint Advisory Group, Greenwich, CT (USA)

1990-06-01T23:59:59.000Z

388

Supporting Organizations | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Educational Outreach Publications and Reports News and Awards Supporting Organizations Nuclear Science Engineering Fusion & Materials for Nuclear Systems Nuclear Science Home |...

389

Nuclear Fuels  

Science Journals Connector (OSTI)

The core of a nuclear reactor is composed of a controlled critical configuration of a fissile material, which in strict a sense is the fuel. This fissile material is contained in a matrix, normally a ceramic c...

Rudy J. M. Konings; Thierry Wiss

2011-01-01T23:59:59.000Z

390

NNSA: Working To Prevent Nuclear Terrorism | National Nuclear...  

National Nuclear Security Administration (NNSA)

secure weapons-grade nuclear material at the Mayak Production Association in Ozersk, Russia. Completed MPC&A upgrades to 15 nuclear material buildings outside of Russia. Returned...

391

Nuclear Fuel Cycle & Vulnerabilities  

SciTech Connect

The objective of safeguards 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. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

Boyer, Brian D. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

392

Directionally Sensitive Neutron Detector For Homeland Security Applications  

E-Print Network (OSTI)

Radiation Portal Monitor SNM Special Nuclear Material US United States vii TABLE OF CONTENTS Page ABSTRACT ................................................................................................................. iii ACKNOWLEDGEMENTS... of Existing Radiation Portal Monitors............................ 7 II.B. Previous Work in the Field of Directionally Sensitive Detectors ...... 11 III THEORY...

Spence, Grant

2012-02-14T23:59:59.000Z

393

Breaking the Tension: Development and Investigation of a Centrifugal Tensioned Metastable Fluid Detector System  

E-Print Network (OSTI)

Fluid Mechanics CTMFD Centrifugal Tensioned Metastable Fluid Detector HEU Highly Enriched Uranium IR Infrared LED Light Emitting Diode P Pressure PWM Pulse Width Modulation r Radius R Gas Constant SNM Special Nuclear Material T Temperature...

Solom, Matthew 1985-

2012-12-10T23:59:59.000Z

394

Standard guide for establishing surveillance test program for boron-based neutron absorbing material systems for use in nuclear spent fuel storage racks  

E-Print Network (OSTI)

1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear spent fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the presence of sufficient neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear spent fuel. 1.2 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

395

Gamma/neutron time-correlation for special nuclear material characterization %3CU%2B2013%3E active stimulation of highly enriched uranium.  

SciTech Connect

A series of simulations and experiments were undertaken to explore and evaluate the potential for a novel new technique for fissile material detection and characterization, the timecorrelated pulse-height (TCPH) method, to be used concurrent with active stimulation of potential nuclear materials. In previous work TCPH has been established as a highly sensitive method for the detection and characterization of configurations of fissile material containing Plutonium in passive measurements. By actively stimulating fission with the introduction of an external radiation source, we have shown that TCPH is also an effective method of detecting and characterizing configurations of fissile material containing Highly Enriched Uranium (HEU). The TCPH method is shown to be robust in the presence of the proper choice of external radiation source. An evaluation of potential interrogation sources is presented.

Marleau, Peter; Nowack, Aaron B.; Clarke, Shaun D. [University of Michigan; Monterial, Mateusz [University of Michigan; Paff, Marc [University of Michigan; Pozzi, Sara A. [University of Michigan

2013-09-01T23:59:59.000Z

396

Regulatory Guide 5.29, Revision 2, "Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants".  

National Nuclear Security Administration (NNSA)

U.S. NUCLEAR REGULATORY COMMISSION June 2013 U.S. NUCLEAR REGULATORY COMMISSION June 2013 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH Written suggestions regarding this guide or development of new guides may be submitted through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory guide is also available through the NRC's Agencywide Documents Access and Management System (ADAMS) at

397

Relativistic mean-field models and nuclear matter constraints  

SciTech Connect

This work presents a preliminary study of 147 relativistic mean-field (RMF) hadronic models used in the literature, regarding their behavior in the nuclear matter regime. We analyze here different kinds of such models, namely: (i) linear models, (ii) nonlinear {sigma}{sup 3}+{sigma}{sup 4} models, (iii) {sigma}{sup 3}+{sigma}{sup 4}+{omega}{sup 4} models, (iv) models containing mixing terms in the fields {sigma} and {omega}, (v) density dependent models, and (vi) point-coupling ones. In the finite range models, the attractive (repulsive) interaction is described in the Lagrangian density by the {sigma} ({omega}) field. The isospin dependence of the interaction is modeled by the {rho} meson field. We submit these sets of RMF models to eleven macroscopic (experimental and empirical) constraints, used in a recent study in which 240 Skyrme parametrizations were analyzed. Such constraints cover a wide range of properties related to symmetric nuclear matter (SNM), pure neutron matter (PNM), and both SNM and PNM.

Dutra, M.; Lourenco, O.; Carlson, B. V. [Departamento de Fisica, Instituto Tecnologico de Aeronautica-CTA, 12228-900, Sao Jose dos Campos, SP (Brazil); Delfino, A. [Instituto de Fisica, Universidade Federal Fluminense, 24210-150, Boa Viagem, Niteroi, RJ (Brazil); Menezes, D. P.; Avancini, S. S. [Departamento de Fisica, CFM, Universidade Federal de Santa Catarina, CP. 476, CEP 88.040-900, Florianopolis, SC (Brazil); Stone, J. R. [Oxford Physics, University of Oxford, OX1 3PU Oxford (United Kingdom) and Department of Physics and Astronomy, University of Tennessee, Knoxville, Tennessee 37996 (United States); Providencia, C. [Centro de Fisica Computacional, Department of Physics, University of Coimbra, P-3004-516 Coimbra (Portugal); Typel, S. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Theorie, Planckstrasse 1,D-64291 Darmstadt (Germany)

2013-05-06T23:59:59.000Z

398

Destruction of Plutonium and Other Nuclear Waste Materials Using the Accelerator-Driven Transmutation of Waste Concept  

Science Journals Connector (OSTI)

Each large nuclear power plant produces about 300 kilograms of ... about 120 kilograms of long-lived fission product wastes per year, with major constituents in terms ... humans either directly or by clandestine ...

F. Venneri

1997-01-01T23:59:59.000Z

399

554 Journal of Nuclear Materials II I & 112 (1982) 554-559 North-Holland Publishing Company  

E-Print Network (OSTI)

.M. HASSANEIN, G.L. KULCINSKI and W.G. WOLFER Fusion Engineering Program, Nuclear Engineering Department that stays solid. The detailed time history of the temperature distribution is accurately computed by solving

Harilal, S. S.

400

Neutron Energy Response and Background of Electrochemically Etched Nuclear Track Detectors: Study of Various CR-39 Materials  

Science Journals Connector (OSTI)

......Radiation Protection Dosimetry Article Neutron Energy Response and Background of Electrochemically Etched Nuclear Track Detectors: Study of Various CR-39...experiments. Results are presented for the energy dependence of the response of the various......

M. Luszik-Bhadra; W.G. Alberts; E. Piesch

1990-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor  

Science Journals Connector (OSTI)

The basic results are given of an experimental investigation of the interaction oxide corium melt containing unoxidized zirconium with the sacrificial material of the device for localization of the core melt o...

V. G. Asmolov; A. A. Sulatskii; S. V. Beshta; V. S. Granovskii

2007-02-01T23:59:59.000Z

402

Creating a Comprehensive, Efficient, and Sustainable Nuclear Regulatory Structure: A Process Report from the U.S. Department of Energy's Material Protection, Control and Accounting Program  

SciTech Connect

With the congressionally mandated January 1, 2013 deadline for the U.S. Department of Energys (DOE) Nuclear Material Protection, Control and Accounting (MPC&A) program to complete its transition of MPC&A responsibility to the Russian Federation, National Nuclear Security Administration (NNSA) management directed its MPC&A program managers and team leaders to demonstrate that work in ongoing programs would lead to successful and timely achievement of these milestones. In the spirit of planning for successful project completion, the NNSA review of the Russian regulatory development process confirmed the critical importance of an effective regulatory system to a sustainable nuclear protection regime and called for an analysis of the existing Russian regulatory structure and the identification of a plan to ensure a complete MPC&A regulatory foundation. This paper describes the systematic process used by DOEs MPC&A Regulatory Development Project (RDP) to develop an effective and sustainable MPC&A regulatory structure in the Russian Federation. This nuclear regulatory system will address all non-military Category I and II nuclear materials at State Corporation for Atomic Energy Rosatom, the Federal Service for Ecological, Technological, and Nuclear Oversight (Rostechnadzor), the Federal Agency for Marine and River Transport (FAMRT, within the Ministry of Transportation), and the Ministry of Industry and Trade (Minpromtorg). The approach to ensuring a complete and comprehensive nuclear regulatory structure includes five sequential steps. The approach was adopted from DOEs project management guidelines and was adapted to the regulatory development task by the RDP. The five steps in the Regulatory Development Process are: 1) Define MPC&A Structural Elements; 2) Analyze the existing regulatory documents using the identified Structural Elements; 3) Validate the analysis with Russian colleagues and define the list of documents to be developed; 4) Prioritize and schedule the development of documents; 5) Identify and develop processes to measure effectiveness of regulations. Utilizing this process is resulting in an effective regulatory process that is understood and is being adopted by the four RF organizations. It is anticipated that the current regulatory development process will continue after U.S. support ends. Utilization of the systematic methodology will ensure regulatory development is based on required MPC&A structural elements and will support the continued maintenance and development of an effective regulatory base.

Wright, Troy L.; O'Brien, Patricia E.; Hazel, Michael J.; Tuttle, John D.; Cunningham, Mitchel E.; Schlegel, Steven C.

2010-08-11T23:59:59.000Z

403

Development of a portable neutron coincidence counter for field measurements of nuclear materials using the advanced multiplicity capabilities of MCNPX 2.5.F and the neutron coincidence point model  

E-Print Network (OSTI)

given material. In an effort to identify unknown nuclear samples in field inspections, the Portable Neutron Coincidence Counter (PNCC) has been developed. This detector makes use of the coincident neutrons being emitted from a bulk sample. An in...

Thornton, Angela Lynn

2009-05-15T23:59:59.000Z

404

Development of a portable neutron coincidence counter for field measurements of nuclear materials using the advanced multiplicity capabilities of MCNPX 2.5.F and the neutron coincidence point model  

E-Print Network (OSTI)

given material. In an effort to identify unknown nuclear samples in field inspections, the Portable Neutron Coincidence Counter (PNCC) has been developed. This detector makes use of the coincident neutrons being emitted from a bulk sample. An in...

Thornton, Angela Lynn

2008-10-10T23:59:59.000Z

405

a._-__k!BEUEVIER Journal of Nuclear Materials 233-237 (1996) 713-717 Lifetime evaluation of plasma-facing materials during a tokamak  

E-Print Network (OSTI)

as a critical obstacle to reliable and successful operation of a tokamak reactor. Two separate mechanisms lead, Russian Federation Abstract Erosion losses of plasma-facing materials in a tokamak reactor during major. In this analysis, magnetic field diffusion in the vapor, two-dimen- sional effects of vapor expansion, and lateral

Harilal, S. S.

406

An Assessment of the Current Day Impact of Various Materials Associated with the U.S. Nuclear Test Program in the Marshall Island  

SciTech Connect

Different stable elements, and some natural and man-made radionuclides, were used as tracers or associated in other ways with nuclear devices that were detonated at Bikini and Enewetak Atolls as part of the U.S. nuclear testing program from 1946 through 1958. The question has been raised whether any of these materials dispersed by the explosions could be of sufficient concentration in either the marine environment or on the coral islands to be of a health concern to people living, or planning to live, on the atolls. This report addresses that concern. An inventory of the materials involved during the test period was prepared and provided to us by the Office of Defense Programs (DP) of the United States Department of Energy (DOE). The materials that the DOE and the Republic of the Marshall Islands (RMI) ask to be evaluated are--sulfur, arsenic, yttrium, tantalum, gold, rhodium, indium, tungsten, thallium, thorium-230,232 ({sup 230,232}Th), uranium-233,238 ({sup 233,238}U), polonium-210 ({sup 210}Po), curium-232 ({sup 232}Cu), and americium-241 ({sup 241}Am). The stable elements were used primarily as tracers for determining neutron energy and flux, and for other diagnostic purposes in the larger yield, multistage devices. It is reasonable to assume that these materials would be distributed in a similar manner as the fission products subsequent to detonation. A large inventory of fission product and uranium data was available for assessment. Detailed calculations show only a very small fraction of the fission products produced during the entire test series remain at the test site atolls. Consequently, based on the information provided, we conclude that the concentration of these materials in the atoll environment pose no adverse health effects to humans.

Robison, W L; Noshkin, V E; Hamilton, T F; Conrado, C L; Bogen, K T

2001-05-01T23:59:59.000Z

407

ELSEVIER Journal of Nuclear Materials 212-215 (1994) 845-848 Postirradiation fiber debonding and pull-out  

E-Print Network (OSTI)

The toughness of ceramic matrix composites is contributed by crack bridging, matrix crack deflection, fiber by investigating the mechanisms of energy dissipation during composite failure. In addition to matrix toughness and pull-out in Sic-Sic composites * A. El-Azab, N.M. Ghoniem Mechanic, Aerospace and Nuclear En~~e~g ~epa

Ghoniem, Nasr M.

408

An Accelerated Aging Analysis Method Based on Local Data for Components and Materials in Nuclear Power Plants  

Science Journals Connector (OSTI)

In nuclear power plants, accelerated aging of certain components can lead to reduction of their service life, which has potential impact on the safety and economics of the whole plant. In order to effectively manage the accelerated aging of critical ... Keywords: accelerated aging, life estimation, accelerating factor, performance degradation data

Zeng Yuyun; Liu Jingquan; Huang Weigang

2013-07-01T23:59:59.000Z

409

Thermal and flow analysis of the Fluor Daniel, Inc., Nuclear Material Storage Facility renovation design (initial 30% effort of Title 1)  

SciTech Connect

The computational fluid dynamics code CFX4.2 was used to evaluate steady-state thermal-hydraulic conditions in the Fluor Daniel, Inc., Nuclear Material Storage Facility renovation design (initial 30% of Title 1). Thirteen facility cases were evaluated with varying temperature dependence, drywell-array heat-source magnitude and distribution, location of the inlet tower, and no-flow curtains in the drywell-array vault. Four cases of a detailed model of the inlet-tower top fixture were evaluated to show the effect of the canopy-cruciform fixture design on the air pressure and flow distributions.

Steinke, R.G.; Mueller, C.; Knight, T.D.

1998-03-01T23:59:59.000Z

410

Nuclear Medicine  

Science Journals Connector (OSTI)

Nuclear medicine is the branch of medicine that is concerned with the use of in the diagnosis, management, and treatment of disease. It usually uses small amounts of radioactive materials or , substances th...

2008-01-01T23:59:59.000Z

411

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

412

Office of the Assistant General Counsel for Civilian Nuclear...  

Energy Savers (EERE)

(HLW) and Spent Nuclear Fuel (SNF) Management of Nuclear Materials and Non-HLW Nuclear Fuel Cycle Energy Research and Development Non-Proliferation Nuclear Regulatory Commission...

413

DOE-STD-1071-94; DOE Standard Guideline to Good Practices for Material Receipt, Inspection, Handling, Storage, Retrieval, and Issuance at DOE Nuclear Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

71-94 71-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR MATERIAL RECEIPT, INSPECTION, HANDLING, STORAGE, RETRIEVAL, AND ISSUANCE AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (615) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE94014949 DOE-STD-1071-94 FOREWORD The Guideline to Good Practices for Material Receipt, Inspection, Handling, Storage,

414

6 Nuclear Fuel Designs  

NLE Websites -- All DOE Office Websites (Extended Search)

Message from the Director Message from the Director 2 Nuclear Power & Researrh Reactors 3 Discovery of Promethium 4 Nuclear Isotopes 4 Nuclear Medicine 5 Nuclear Fuel Processes & Software 6 Nuclear Fuel Designs 6 Nuclear Safety 7 Nuclear Desalination 7 Nuclear Nonproliferation 8 Neutron Scattering 9 Semiconductors & Superconductors 10 lon-Implanted Joints 10 Environmental Impact Analyses 11 Environmental Quality 12 Space Exploration 12 Graphite & Carbon Products 13 Advanced Materials: Alloys 14 Advanced Materials: Ceramics 15 Biological Systems 16 Biological Systems 17 Computational Biology 18 Biomedical Technologies 19 Intelligent Machines 20 Health Physics & Radiation Dosimetry 21 Radiation Shielding 21 Information Centers 22 Energy Efficiency: Cooling & Heating

415

Nuclear and Non-Ionizing Energy-loss of Electrons with Low and Relativistic Energies in Materials and Space Environment  

E-Print Network (OSTI)

The treatment of the electron-nucleus interaction based on the Mott differential cross section was extended to account for effects due to screened Coulomb potentials, finite sizes and finite rest masses of nuclei for electrons above 200 keV and up to ultra high energies. This treatment allows one to determine both the total and differential cross sections, thus, subsequently to calculate the resulting nuclear and non-ionizing stopping powers. Above a few hundreds of MeV, neglecting the effect due to finite rest masses of recoil nuclei the stopping power and NIEL result to be largely underestimated; while, above a few tens of MeV the finite size of the nuclear target prevents a further large increase of stopping powers which approach almost constant values.

Boschini, M J; Gervasi, M; Giani, S; Grandi, D; Ivanchenko, V; Nieminem, P; Pensotti, S; Rancoita, P G; Tacconi, M

2011-01-01T23:59:59.000Z

416

Nuclear and Non-Ionizing Energy-loss of Electrons with Low and Relativistic Energies in Materials and Space Environment  

E-Print Network (OSTI)

The treatment of the electron-nucleus interaction based on the Mott differential cross section was extended to account for effects due to screened Coulomb potentials, finite sizes and finite rest masses of nuclei for electrons above 200 keV and up to ultra high energies. This treatment allows one to determine both the total and differential cross sections, thus, subsequently to calculate the resulting nuclear and non-ionizing stopping powers. Above a few hundreds of MeV, neglecting the effect due to finite rest masses of recoil nuclei the stopping power and NIEL result to be largely underestimated; while, above a few tens of MeV the finite size of the nuclear target prevents a further large increase of stopping powers which approach almost constant values.

M. J. Boschini; C. Consolandi; M. Gervasi; S. Giani; D. Grandi; V. Ivanchenko; P. Nieminem; S. Pensotti; P. G. Rancoita; M. Tacconi

2011-12-06T23:59:59.000Z

417

Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 3, Site team reports  

SciTech Connect

A self assessment was conducted of those Hanford facilities that are utilized to store Reactor Irradiated Nuclear Material, (RINM). The objective of the assessment is to identify the Hanford inventories of RINM and the ES & H concerns associated with such storage. The assessment was performed as proscribed by the Project Plan issued by the DOE Spent Fuel Working Group. The Project Plan is the plan of execution intended to complete the Secretary`s request for information relevant to the inventories and vulnerabilities of DOE storage of spent nuclear fuel. The Hanford RINM inventory, the facilities involved and the nature of the fuel stored are summarized. This table succinctly reveals the variety of the Hanford facilities involved, the variety of the types of RINM involved, and the wide range of the quantities of material involved in Hanford`s RINM storage circumstances. ES & H concerns are defined as those circumstances that have the potential, now or in the future, to lead to a criticality event, to a worker radiation exposure event, to an environmental release event, or to public announcements of such circumstances and the sensationalized reporting of the inherent risks.

Not Available

1993-11-01T23:59:59.000Z

418

Standard test method for analysis of isotopic composition of uranium in nuclear-grade fuel material by quadrupole inductively coupled plasma-mass spectrometry  

E-Print Network (OSTI)

1.1 This test method is applicable to the determination of the isotopic composition of uranium (U) in nuclear-grade fuel material. The following isotopic weight percentages are determined using a quadrupole inductively coupled plasma-mass spectrometer (Q-ICP-MS): 233U, 234U, 235U, 236U, and 238U. The analysis can be performed on various material matrices after acid dissolution and sample dilution into water or dilute nitric (HNO3) acid. These materials include: fuel product, uranium oxide, uranium oxide alloys, uranyl nitrate (UNH) crystals, and solutions. The sample preparation discussed in this test method focuses on fuel product material but may be used for uranium oxide or a uranium oxide alloy. Other preparation techniques may be used and some references are given. Purification of the uranium by anion-exchange extraction is not required for this test method, as it is required by other test methods such as radiochemistry and thermal ionization mass spectroscopy (TIMS). This test method is also described i...

American Society for Testing and Materials. Philadelphia

2000-01-01T23:59:59.000Z

419

PARTNERSHIP FOR THE DEVELOPMENT OF NEXT GENERATION SIMULATION TOOLS TO EVALUATE CEMENTITIOUS BARRIERS AND MATERIALS USED IN NUCLEAR APPLICATION - 8388  

SciTech Connect

The US DOE has initiated a multidisciplinary cross cutting project to develop a reasonable and credible set of tools to predict the structural, hydraulic and chemical performance of cement barriers used in nuclear applications over extended time frames (e.g., > 100 years for operating facilities and > 1000 years for waste management). A partnership that combines DOE, NRC, academia, private sector, and international expertise has been formed to accomplish the project objectives by integrating existing information and realizing advancements where necessary. The set of simulation tools and data developed under this project will be used to evaluate and predict the behavior of cementitious barriers used in near surface engineered waste disposal systems, e.g., waste forms, containment structures, entombments and environmental remediation, including decontamination and decommissioning (D&D) activities. The simulation tools will also support analysis of structural concrete components of nuclear facilities (spent fuel pools, dry spent fuel storage units, and recycling facilities, e.g., fuel fabrication, separations processes). Simulation parameters will be obtained from prior literature and will be experimentally measured under this project, as necessary, to demonstrate application of the simulation tools for three prototype applications (waste form in concrete vault, high level waste tank grouting, and spent fuel pool). Test methods and data needs to support use of the simulation tools for future applications will be defined. This is a national issue that affects all waste disposal sites that use cementitious waste forms and structures, decontamination and decommissioning activities, service life determination of existing structures, and design of future public and private nuclear facilities. The problem is difficult because it requires projecting conditions and responses over extremely long times. Current performance assessment analyses show that engineered barriers are typically the primary control to prevent the release of radionuclides from nuclear facilities into the environment. In the absence of an adequate predictive tool, assessments cannot fully incorporate the effectiveness of the concrete barriers, and the inventory of radionuclides (especially the long-lived radionuclides) that may be safely disposed of in shallow land disposal and the predicted service life of operating nuclear facilities. This project is 5 year effort focused on reducing uncertainties associated with current methodologies for assessing cementitious barrier performance and increasing the consistency and transparency of the assessment process. The results of this project will enable improved risk-informed, performance-based decision making, and supports several of the strategic initiatives in the DOE-EM Engineering & Technology Roadmap.

Langton, C; Richard Dimenna, R

2008-01-29T23:59:59.000Z

420

Implementing New Methods of Laser Marking of Items in the Nuclear Material Control and Accountability System at SSC RF-IPPE: An Automated Laser Marking System  

SciTech Connect

For over ten years SSC RF-IPPE, together with the US DOE National Laboratories, has been working on implementing automated control and accountability methods for nuclear materials and other items. Initial efforts to use adhesive bar codes or ones printed (painted) onto metal revealed that these methods were inconvenient and lacked durability under operational conditions. For NM disk applications in critical stands, there is the additional requirement that labels not affect the neutron characteristics of the critical assembly. This is particularly true for the many stainless-steel clad disks containing highly enriched uranium (HEU) and plutonium that are used at SSC RF-IPPE for modeling nuclear power reactors. In search of an alternate method for labeling these disks, we tested several technological options, including laser marking and two-dimensional codes. As a result, the method of laser coloring was chosen in combination with Data Matrix ECC200 symbology. To implement laser marking procedures for the HEU disks and meet all the nuclear material (NM) handling standards and rules, IPPE staff, with U.S. technical and financial support, implemented an automated laser marking system; there are also specially developed procedures for NM movements during laser marking. For the laser marking station, a Zenith 10F system by Telesis Technologies (10 watt Ytterbium Fiber Laser and Merlin software) is used. The presentation includes a flowchart for the automated system and a list of specially developed procedures with comments. Among other things, approaches are discussed for human-factor considerations. To date, markings have been applied to numerous steel-clad HEU disks, and the work continues. In the future this method is expected to be applied to other MC&A items.

Regoushevsky, V I; Tambovtsev, S D; Dvukhsherstnov, V G; Efimenko, V F; Ilyantsev, A I; Russ III, G P

2009-05-18T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material snm" 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

Nuclear Forensics | More Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Materials Science and Engineering Materials Science and Engineering Advanced Materials Clean Energy Materials Theory and Simulation Neutron Science Nuclear Forensics Nuclear Science Supercomputing Theory, Modeling and Simulation More Science Home | Science & Discovery | More Science | Materials Science and Engineering | Nuclear Forensics SHARE Nuclear Forensics image Tools, techniques, and expertise in nuclear fuel cycle research gained over seven decades help ORNL scientists control and track nuclear bomb-grade materials to be sure they don't fall into the wrong hands. Among the leading-edge technologies used by researchers are high-resolution techniques that allow analysis of radiation detector data in stunning detail. Researchers are also developing aerosol sampling systems to collect

422

Special Report: OAS-L-12-11 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

L-12-11 L-12-11 Special Report: OAS-L-12-11 September 21, 2012 Inquiry into the De-Inventory of Special Nuclear Material at Lawrence Livermore National Laboratory In January 2012, the Office of Inspector General received allegations that Lawrence Livermore National Laboratory (Livermore) had (1) failed to follow the Department of Energy's Record of Decision requirements for removing special nuclear material (SNM) and as such had violated Public Law 109-364; (2) attempted to maintain SNM beyond 2012 by establishing unique testing capabilities that were used to perform physical work using SNM on the W78 Life Extension Program (LEP) that required only a "paper study;" (3) misappropriated Government funds to reestablish test capabilities following a flood in 2006; and, (4) incurred excessive security costs for SNM. We

423

Nuclear Systems Technology | Nuclear Science | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Fuel Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments & Analysis Used Nuclear Fuel Storage, Transportation, and Disposal Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Nuclear Systems Technology SHARE Nuclear Systems Technology Nuclear Systems Technology Image 2 ORNL has had historic involvement in a broad set of nuclear research areas: irradiated materials and isotopes R&D, fission and fusion reactors development, neutron scattering, fuel enrichment, used fuel recycling and disposal, etc. The skills and knowledge required to succeed in these research areas often cultivated core areas of expertise in which ORNL is

424

Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, October 1, 1979-December 31, 1979  

SciTech Connect

This report presents the results of work performed from October 1, 1979 through December 31, 1979. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described. This includes: screening creep results, weight gain and post-exposure mechanical properties for materials thermally exposed at 750/sup 0/ and 850/sup 0/C (1382/sup 0/ and 1562/sup 0/F). In addition, the status of the data management system is described.

Not Available

1980-04-18T23:59:59.000Z

425

Materials | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

today New high-tech materials are the key to breakthroughs in biology, the environment, nuclear energy, transportation and national security. Argonne continues to make...

426

Antineutrino Detection for Nuclear Monitoring  

E-Print Network (OSTI)

covertly acquire these special nuclear materials from: Assembled weapons Raw uranium ore Enriched uranium antineutrino monitoring infrastructure will help avert the spread of covert nuclear reactors and weaponsAntineutrino Detection for Nuclear Monitoring Draft #12;Graphic courtesy Lawrence Livermore

Mcdonough, William F.

427

US-Russian collaboration for enhancing nuclear materials protection, control, and accounting at the Elektrostal uranium fuel-fabrication plant  

SciTech Connect

In September 1993, an implementing agreement was signed that authorized collaborative projects to enhance Russian national materials control and accounting, physical protection, and regulatory activities, with US assistance funded by the Nunn-Lugar Act. At the first US-Russian technical working group meeting in Moscow in February 1994, it was decided to identify a model facility where materials protection, control, and accounting (MPC and A) and regulatory projects could be carried out using proven technologies and approaches. The low-enriched uranium (LEU or RBMK and VVER) fuel-fabrication process at Elektrostal was selected, and collaborative work began in June 1994. Based on many factors, including initial successes at Elektrostal, the Russians expanded the cooperation by proposing five additional sites for MPC and A development: the Elektrostal medium-enriched uranium (MEU or BN) fuel-fabrication process and additional facilities at Podolsk, Dmitrovgrad, Obninsk, and Mayak. Since that time, multilaboratory teams have been formed to develop and implement MPC and A upgrades at the additional sites, and much new work is underway. This paper summarizes the current status of MPC and A enhancement projects in the LEU fuel-fabrication process and discusses the status of work that addresses similar enhancements in the MEU (BN) fuel processes at Elektrostal, under the recently expanded US-Russian MPC and A cooperation.

Smith, H. [Los Alamos National Lab., NM (United States); Allentuck, J. [Brookhaven National Lab., Upton, NY (United States); Barham, M. [Oak Ridge National Lab., TN (United States); Bishop, M. [Sandia National Labs., Albuquerque, NM (United States); Wentz, D. [Lawrence Livermore National Lab., CA (United States); Steele, B.; Bricker, K. [Pacific Northwest National Lab., Richland, WA (United States); Cherry, R. [USDOE, Washington, DC (United States); Snegosky, T. [Dept. of Defense, Washington, DC (United States). Defense Nuclear Agency

1996-09-01T23:59:59.000Z

428

Nuclear Power Plants  

Science Journals Connector (OSTI)

A third issue related to the production, use and transportation of nuclear materials is the safety issue associated with ... an act of war or an act of terrorism. While the containment buildings of typical nuclear

Efstathios E. (Stathis) Michaelides

2012-01-01T23:59:59.000Z

429

Physics in nuclear safeguards  

Science Journals Connector (OSTI)

International agreements demand that rigorous control procedures are applied to nuclear material. Containment and surveillance techniques are used to monitor the security aspects of dealing with the material whilst accountancy provides quantitative information. The author shows that the methods used to control nuclear material can be conveniently broken down into these two parts

B.W. Hooton

1984-01-01T23:59:59.000Z

430

Faculty and Instructional Staff in the UW-Madison Department of Materials Science & Engineering  

E-Print Network (OSTI)

& Engineering Materials for nuclear energy system, fission reactors, nuclear fuels, energy policy, sustainability of nuclear energy. Mark A Eriksson Professor, Physics and Materials Science & Engineering

Wisconsin at Madison, University of

431

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

U in a mixture of depleted uranium and lead as a surrogateamounts of Pb and depleted uranium (DU). These targets actedprevious experiment, the depleted uranium in the target was

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

432

Portal monitoring technology control process  

SciTech Connect

Portal monitors are an important part of the material protection, control, and accounting (MPC and A) programs in Russia and the US. Although portal monitors are only a part of an integrated MPC and A system, they are an effective means of controlling the unauthorized movement of special nuclear material (SNM). Russian technical experts have gained experience in the use of SNM portal monitors from US experts ad this has allowed them to use the monitors more effectively. Several Russian institutes and companies are designing and manufacturing SNM portal monitors in Russia. Interactions between Russian and US experts have resulted in improvements to the instruments. SNM portal monitor technology has been effectively transferred from the US to Russia and should be a permanent part of the Russian MPC and A Program. Progress in the implementation of the monitors and improvements to how they are used are discussed.

York, R.L.

1998-12-31T23:59:59.000Z

433

Coated ceramic breeder materials  

DOE Patents (OSTI)

A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.

Tam, Shiu-Wing (Downers Grove, IL); Johnson, Carl E. (Elk Grove, IL)

1987-01-01T23:59:59.000Z

434

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

435

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

436

Review of the International Atomic Energy Agency International database on reactor pressure vessel materials and US Nuclear Regulatory Commission/Oak Ridge National Laboratory embrittlement data base  

SciTech Connect

The International Atomic Energy Agency (IAEA) has supported neutron radiation effects information exchange through meetings and conferences since the mid-1960s. Through an International Working Group on Reliability of Reactor Pressure Components, information exchange and research activities were fostered through the Coordinated Research Program (CRP) sponsored by the IAEA. The final CRP meeting was held in November 1993, where it was recommended that the IAEA coordinate the development of an International Database on Reactor Pressure Vessel Material (IDRPVM) as the first step in generating an International Database on Aging Management. The purpose of this study was to provide special technical assistance to the NRC in monitoring and evaluating the IAEA activities in developing the IAEA IDRPVM, and to compare the IDRPVM with the Nuclear Regulatory Commission (NRC) - Oak Ridge National Laboratory (ORNL) Power Reactor Embrittlement Data Base (PR-EDB) and provide recommendations for improving the PR-EDB. A first test version of the IDRPVM was distributed at the First Meeting of Liaison Officers to the IAEA IDRPVM, in November 1996. No power reactor surveillance data were included in this version; the testing data were mainly from CRP Phase III data. Therefore, because of insufficient data and a lack of power reactor surveillance data received from the IAEA IDRPVM, the comparison is made based only on the structure of the IDRPVM. In general, the IDRPVM and the EDB have very similar data structure and data format. One anticipates that because the IDRPVM data will be collected from so many different sources, quality assurance of the data will be a difficult task. The consistency of experimental test results will be an important issue. A very wide spectrum of material characteristics of RPV steels and irradiation environments exists among the various countries. Hence the development of embrittlement prediction models will be a formidable task. 4 refs., 2 figs., 4 tabs.

Wang, J.A.; Kam, F.B.K.

1998-02-01T23:59:59.000Z

437

Environmental consequences of postulate plutonium releases from Atomics International's Nuclear Materials Development Facility (NMDF), Santa Susana, California, as a result of severe natural phenomena  

SciTech Connect

Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases caused by severe natural phenomena at the Atomics International's Nuclear Materials Development Facility (NMDF), in the Santa Susana site, California. The severe natural phenomena considered are earthquakes, tornadoes, and high straight-line winds. Plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year committed dose equivalents are given for the maximum-exposed individual and the population within a 50-mile radius of the plant. The maximum plutonium deposition values likely to occur offsite are also given. The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited offsite following the earthquake, and the 150-mph and 170-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium in the general environment of 0.2 ..mu..Ci/m/sup 2/. The deposition values following the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline.

Jamison, J.D.; Watson, E.C.

1982-02-01T23:59:59.000Z

438

SRS Completes Annual Examinations to Verify Safe Storage of Nuclear...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Completes Annual Examinations to Verify Safe Storage of Nuclear Materials SRS Completes Annual Examinations to Verify Safe Storage of Nuclear Materials July 29, 2014 - 12:00pm...