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Note: This page contains sample records for the topic "nuclear operations related" 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.


1

EIS-0373: Proposed Consolidation of Nuclear Operations Related...  

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

373: Proposed Consolidation of Nuclear Operations Related to the Production of Radioisotope Power Systems EIS-0373: Proposed Consolidation of Nuclear Operations Related to the...

2

EIS-0373: Proposed Consolidation of Nuclear Operations Related to the  

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

373: Proposed Consolidation of Nuclear Operations Related to 373: Proposed Consolidation of Nuclear Operations Related to the Production of Radioisotope Power Systems EIS-0373: Proposed Consolidation of Nuclear Operations Related to the Production of Radioisotope Power Systems Summary NOTE: EIS-0373 has been cancelled. This EIS evaluates the environmental impacts of consolidating nuclear activities related to production of radioisotope power systems (RPS) for space and national security missions at a single DOE site: the preferred alternative is the Materials and Fuels Complex at Idaho National Laboratory. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download January 9, 2013 EIS-0373: Notice of Cancellation of an Environmental Impact Statement Proposed Consolidation of Nuclear Operations Related to the Production of

3

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: neutron flux, cur- rent noise, vibration diagnostics: Swedish Nuclear Power Inspectorate SE- 10658 Stockholm, Sweden. NUCLEAR TECHNOLOGY VOL. 131 AUG. 2000 239 by the Swedish Nuclear Power Inspectorate, contract 14.5-980942-98242. REFERENCES 1. A. M. WEINBERG and H. C

Pázsit, Imre

4

Recommended electromagnetic operating envelopes for safety-related I and C systems in nuclear power plants: Draft report for comment  

Science Conference Proceedings (OSTI)

This document presents recommendations for electromagnetic operating envelopes to augment test criteria and test methods addressing electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges that are applicable to safety-related instrumentation and control (I and C) systems in nuclear power plants. The Oak Ridge National Laboratory (ORNL) was engaged by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to assist in developing the technical basis for regulatory guidance on EMI/RFI immunity and power surge withstand capability (SWC). Previous research has provided recommendations on electromagnetic compatibility (EMC) design and installation practices, endorsement of EMI/RFI immunity and SWC test criteria and test methods, and determination of ambient electromagnetic conditions at nuclear power plants. The present research involves development of recommended electromagnetic envelopes that are applicable to nuclear power plant locations where safety-related I and C systems either are or may be installed. These recommended envelopes establish both emissions criteria and the levels of radiated and conducted interference that I and C systems should be able to withstand without upset or malfunction. The EMI/RFI operating envelopes are derived from conditions in comparable military environments and are confirmed by comparison with the nuclear power plant electromagnetic environment based on measured plant emissions profiles. Detailed information on specific power surge conditions in nuclear power plants is not available, so industrial guidance on representative surge characteristics for susceptibility testing is adopted. An engineering assessment of the power surge environment in nuclear power plants leads to the recommendation of operating envelopes based on location categories and exposure levels defined in IEEE Std C62.41-1991, IEEE Recommended Practice on Surge Voltages in Low-Voltage AC Power Circuits.

Ewing, P.D.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1997-12-01T23:59:59.000Z

5

Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants  

SciTech Connect

Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures.

Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

1995-05-01T23:59:59.000Z

6

Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology  

SciTech Connect

The US Department of Energy (DOE), under the US government`s International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

Kohut, P.; Epel, L.G.; Tutu, N.K. [and others

1998-08-01T23:59:59.000Z

7

Operations | National Nuclear Security Administration  

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

| National Nuclear Security Administration | 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 Operations Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations Operations NNSA's Emergency Response Operations program acts as the headquarters command and control, functioning as the coordinating focal point for all

8

Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

| National Nuclear Security Administration | 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 Operations Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations Operations NNSA's Emergency Response Operations program acts as the headquarters command and control, functioning as the coordinating focal point for all

9

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed--has been benchmarked against measurements.30 At the Ringhals nuclear power plant, this measurement is car a measurement performed at the PWR Unit 4 of the Ring hals Nuclear Power Plant was available to us

Demazière, Christophe

10

NUCLEAR PLANT OPERATIONS AND  

E-Print Network (OSTI)

reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed reactivity effects--has been benchmarked against measurements.30 At the Ringhals nuclear power plant a measurement performed at the PWR Unit 4 of the Ring- hals Nuclear Power Plant was available to us

Demazière, Christophe

11

NIST: Methane Symmetry Operations - Nuclear spin functions  

Science Conference Proceedings (OSTI)

Methane Symmetry Operations. 9. Symmetry Properties of Laboratory-Fixed Nuclear Spin Functions, Nuclear Spin Statistics, and Parities. ...

12

NNSA Streamlines Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

NNSA Timeline > NNSA Streamlines Operations NNSA Streamlines Operations December 20, 2002 Washington, DC NNSA Streamlines Operations The National Nuclear Security Administration...

13

Nuclear reactor characteristics and operational history  

Gasoline and Diesel Fuel Update (EIA)

1. Capacity and Generation, Table 3. Characteristics and Operational History 1. Capacity and Generation, Table 3. Characteristics and Operational History Table 2. U.S. Nuclear Reactor Ownership Data PDF XLS Plant/Reactor Name Generator ID Utility Name - Operator Owner Name % Owned Arkansas Nuclear One 1 Entergy Arkansas Inc Entergy Arkansas Inc 100 Arkansas Nuclear One 2 Entergy Arkansas Inc Entergy Arkansas Inc 100 Beaver Valley 1 FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Generation Corp 100 Beaver Valley 2 FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Generation Corp 100 Braidwood Generation Station 1 Exelon Nuclear Exelon Nuclear 100 Braidwood Generation Station 2 Exelon Nuclear Exelon Nuclear 100 Browns Ferry 1 Tennessee Valley Authority Tennessee Valley Authority 100

14

PROJECTIZING AN OPERATING NUCLEAR FACILITY  

SciTech Connect

This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully accomplish deactivation. This concept had to allow for continued operations in FB Line until 2005, while providing distinct task-oriented teams for deactivation of the FCC. Facility workers, always the most knowledgeable about any facility, were integral parts of the project team. The team defined the scope, developed a bottoms-up estimate, reorganized personnel to designated project teams, and developed a baseline schedule with about 12,000 activities. Training was implemented to prepare the facility workers to use project management tools and concepts, which were to execute the project, coordinate activities and track progress. The project budget was estimated at $579 million. The team completed F Canyon and FB Line deactivation in August 2006, four months ahead of schedule and under budget.

Adams, N

2007-07-08T23:59:59.000Z

15

Infrastructure and Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Operations | National Nuclear Security Administration Operations | 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 Infrastructure and Operations Home > About Us > Our Operations > Infrastructure and Operations Infrastructure and Operations NNSA's missions require a secure production and laboratory infrastructure meeting immediate and long term needs. The Associate Administrator for

16

Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

17

Conditional Probabilities, Relative Operating Characteristics, and Relative Operating Levels  

Science Conference Proceedings (OSTI)

The relative operating characteristic (ROC) curve is a highly flexible method for representing the quality of dichotomous, categorical, continuous, and probabilistic forecasts. The method is based on ratios that measure the proportions of events ...

Simon J. Mason; Nicholas E. Graham

1999-10-01T23:59:59.000Z

18

Emergency Operations Training Academy | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Operations Training Academy | National Nuclear Security Operations Training Academy | 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 Emergency Operations Training Academy Home > About Us > Our Programs > Emergency Response > Training > Emergency Operations Training Academy Emergency Operations Training Academy Rotating image showing pictures of Classroom, Online and Hands on trainings

19

Nuclear Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

20

Operating strategy generators for nuclear reactors  

Science Conference Proceedings (OSTI)

Operating strategy generators, i.e., the software intended for increasing the efficiency of work of nuclear power plant operators, are discussed. The possibilities provided by the domestic and foreign operating-strategy generators are analyzed.

Solovyev, D. A., E-mail: and@est.mephi.ru; Semenov, A. A.; Shchukin, N. V. [National Research Nuclear University MEPhI (Russian Federation)

2011-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

METHOD OF OPERATING NUCLEAR REACTORS  

DOE Patents (OSTI)

A method is presented for obtaining enhanced utilization of natural uranium in heavy water moderated nuclear reactors by charging the reactor with an equal number of fuel elements formed of natural uranium and of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction. The reactor is operated until the rate of burnup of plutonium equals its rate of production, the fuel elements are processed to recover plutonium, the depleted uranium is discarded, and the remaining uranium is formed into fuel elements. These fuel elements are charged into a reactor along with an equal number of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction, and reuse of the uranium is continued as aforesaid until it wlll no longer support a chain reaction when combined with an equal quantity of natural uranium.

Untermyer, S.

1958-10-14T23:59:59.000Z

22

Related Resources - Nuclear Data Program, Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

23

Nuclear Facility Operations | Department of Energy  

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

Idaho Operations Office oversees these contract activities in accordance with DOE directives. INL is a multi-program laboratory In addition to enabling the Office of Nuclear...

24

Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12  

Science Conference Proceedings (OSTI)

Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

Tam, P.S.

1993-10-01T23:59:59.000Z

25

Nuclear reactor characteristics and operational history  

U.S. Energy Information Administration (EIA) Indexed Site

Nuclear > U.S. reactor operation status tables Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: November 2012 See also: Table 2. Ownership Data, Table 3. Characteristics and Operational History Table 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor PDF XLS Plant/Reactor Name Generator ID State Type 2009 Summer Capacity Net MW(e)1 2010 Annual Generation Net MWh2 Capacity Factor Percent3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas Nuclear One 2 AR PWR 993 8,415,588 97 Beaver Valley 1 PA PWR 892 7,119,413 91 Beaver Valley 2 PA PWR 885 7,874,151 102 Braidwood Generation Station 1 IL PWR 1,178 9,196,689 89

26

Nuclear reactor characteristics and operational history  

Gasoline and Diesel Fuel Update (EIA)

Nuclear > U.S. reactor operation status tables Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: November 2012 See also: Table 1. Capacity and Generation, Table 2. Ownership Data Table 3. Nuclear Reactor Characteristics and Operational History PDF XLS Plant Name Generator ID Type Reactor Supplier and Model Construction Start Grid Connection Original Expiration Date License Renewal Application License Renewal Issued Extended Expiration Arkansas Nuclear One 1 PWR Babcock&Wilcox, Lower Loop 10/1/1968 8/17/1974 5/20/2014 2/1/2000 6/20/2001 5/20/2034 Arkansas Nuclear One 2 PWR Combustion Eng. 7/1/1971 12/26/1978 7/17/2018 10/15/2003 6/30/2005 7/17/2038

27

Nuclear Facility Operations | Department of Energy  

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

Facility Operations Facility Operations Nuclear Facility Operations INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and national security needs. The Idaho Operations Office oversees these contract activities in accordance with DOE directives. INL is a multi-program laboratory In addition to enabling the Office of Nuclear Energy to develop space power systems and advanced fuel cycle and reactor technologies, INL facilities are used by the National Nuclear Security Administration and other DOE offices, together with other Federal agencies such as the Department of

28

Nuclear data and related services  

SciTech Connect

National Nuclear Data Center (NNDC) maintains a number of data bases containing bibliographic information and evaluated as well as experimental nuclear properties. An evaluated computer file maintained by the NNDC, called the Evaluated Nuclear Structure Data File (ENSDF), contains nuclear structure information for all known nuclides. The ENSDF is the source for the journal ''Nuclear Data Sheets'' which is produced and edited by NNDC. The Evaluated Nuclear Data File (ENDF), on the other hand is designed for storage and retrieval of such evaluated nuclear data as are used in neutronic, photonic, and decay heat calculations in a large variety of applications. Some of the publications from these data bases are the Nuclear Wallet Cards, Radioactivity Handbook, and books on neutron cross sections and resonance parameters. In addition, the NNDC maintains three bibliographic files: NSR - for nuclear structure and decay data related references, CINDA - a bibliographic file for neutron induced reactions, and CPBIB - for charged particle reactions. Selected retrievals from evaluated data and bibliographic files are possible on-line or on request from NNDC. 6 refs., 1 fig.

Tuli, J.K.

1985-01-01T23:59:59.000Z

29

Nuclear Power - Deployment, Operation and Sustainability  

E-Print Network (OSTI)

We are fortunate to live in incredibly exciting and incredibly challenging time. Energy demands due to economic growth and increasing population must be satisfied in a sustainable manner assuring inherent safety, efficiency and no or minimized environmental impact. These considerations are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. At the same time, catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, design requirements and facilitated growing interests in advanced nuclear energy systems. This book is one in a series of books on nuclear power published by InTech. It consists of six major sections housing twenty chapters on topics from the key subject areas pertinent to successful development, deployment and operation of nuclear power systems worldwide. The book targets everyone as its potential readership groups - students, researchers and practitioners - who are interested to learn about nuclear power.

Tsvetkov, Pavel

2011-09-01T23:59:59.000Z

30

EPA Notice of Availability of the Draft Environmental Impact Statement for the Proposed Consolidation of Nuclear Operations Related to Production of Radioisotope Related to Production of Radioisotope Power Systems (DOE/EIS-0373D) (07/01/05)  

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

32 32 Federal Register / Vol. 70, No. 126 / Friday, July 1, 2005 / Notices Severity and Resistance to Control, Amador Ranger District, Eldorado National Forest, Amado County, CA,Wait Period Ends: 08/01/2005, Contact: Patricia Ferrell 530-642- 5146. EIS No. 20050264, Draft EIS, NPS, ID, Minidoka Internment National Monument (Former Minidoka Relocation Center) , General Management Plan, Implementation, Jerome County, ID, Comment Period Ends: 09/19/2005, Contact: Neil King 208-837-4793. EIS No. 20050265, Final EIS, NPS, AZ, Chiricahua National Monument Fire Management Plan (FMP), Implementation, AZ, Wait Period Ends: 08/01/2005, Contact: Alan Whalon 520-824-3560. EIS No. 20050266, Draft EIS, DOE, 00, Proposed Consolidation of Nuclear Operations Related to Production of

31

Hazard Analysis Reports for Nuclear Explosive Operations  

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

NA-STD-3016-2006 NA-STD-3016-2006 May 2006 DOE LIMITED STANDARD HAZARD ANALYSIS REPORTS FOR NUCLEAR EXPLOSIVE OPERATIONS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-NA-STD-3016-2006 iii FORWARD This Department of Energy (DOE)/National Nuclear Security Administration (NNSA) technical standard is approved for use by the Assistant Deputy Administrator for Military Application and Stockpile Operations (NA-12), and is available for use to prepare Nuclear Explosive Operation (NEO) Hazard Analysis Reports (HARs) as required by 10 CFR 830, "Nuclear Safety Management." This Standard is

32

Nuclear Power - Operation, Safety and Environment  

E-Print Network (OSTI)

Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. At the same time, catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, design requirements and facilitated growing interests in advanced nuclear energy systems, next generation nuclear reactors, which are inherently capable to withstand natural disasters and avoid catastrophic consequences without any environmental impact. This book is one in a series of books on nuclear power published by InTech. Under the single-volume cover, we put together such topics as operation, safety, environment and radiation effects. The book is not offering a comprehensive coverage of the material in each area. Instead, selected themes are highlighted by authors of individual chapters representing contemporary interests worldwide. With all diversity of topics in 16 chapters, the integrated system analysis approach of nuclear power operation, safety and environment is the common thread. The goal of the book is to bring nuclear power to our readers as one of the promising energy sources that has a unique potential to meet energy demands with minimized environmental impact, near-zero carbon footprint, and competitive economics via robust potential applications. The book targets everyone as its potential readership groups - students, researchers and practitioners - who are interested to learn about nuclear power.

Tsvetkov, Pavel

2011-09-01T23:59:59.000Z

33

Operating experience feedback report-reliability of safety-related steam turbine-driven standby pumps used in US commerical nuclear power plants  

SciTech Connect

Pump failure experience is collected by two primary means: (1) Licensee Event Reports, and (2) Nuclear Plant Reliability Data System failure reports. Certain safety-related turbine-driven standby pumps were identified by these data systems as experiencing significant ongoing repetitive failures of their turbine drivers, resulting in low reliability of the pump units. The root causes of identified failures were determined, and actions to preclude these repetitive failures were identified. 5 refs., 1 tab.

Boardman, J.R. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-01-01T23:59:59.000Z

34

Digital computer operation of a nuclear reactor  

DOE Patents (OSTI)

A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

Colley, R.W.

1982-06-29T23:59:59.000Z

35

Digital computer operation of a nuclear reactor  

DOE Patents (OSTI)

A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

Colley, Robert W. (Richland, WA)

1984-01-01T23:59:59.000Z

36

Nuclear Power - System Simulations and Operation  

E-Print Network (OSTI)

At the onset of the 21st century, we are searching for reliable and sustainable energy sources that have a potential to support growing economies developing at accelerated growth rates, technology advances improving quality of life and becoming available to larger and larger populations. The quest for robust sustainable energy supplies meeting the above constraints leads us to the nuclear power technology. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. Catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, requirements and facilitated growing interests in designs, which can withstand natural disasters and avoid catastrophic consequences. This book is one in a series of books on nuclear power published by InTech. It consists of ten chapters on system simulations and operational aspects. Our book does not aim at a complete coverage or a broad range. Instead, the included chapters shine light at existing challenges, solutions and approaches. Authors hope to share ideas and findings so that new ideas and directions can potentially be developed focusing on operational characteristics of nuclear power plants. The consistent thread throughout all chapters is the system-thinking approach synthesizing provided information and ideas. The book targets everyone with interests in system simulations and nuclear power operational aspects as its potential readership groups - students, researchers and practitioners.

Tsvetkov, Pavel

2011-09-01T23:59:59.000Z

37

Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15  

Science Conference Proceedings (OSTI)

This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.

Tam, P.S.

1995-06-01T23:59:59.000Z

38

Nuclear Fuel Assembly and Related Methods for Spent Nuclear ...  

Nuclear Fuel Assembly and Related Methods for Spent Nuclear Fuel Reprocessing and Management Note: The technology described above is an early stage ...

39

US nuclear power plant operating cost and experience summaries  

Science Conference Proceedings (OSTI)

NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

Kohn, W.E.; Reid, R.L.; White, V.S.

1998-02-01T23:59:59.000Z

40

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

India and Pakistans unstable peace: Why nuclear South Asiaincludes nuclear powers such as France, Pakistan, and theChina, and Pakistan, may suffer relative losses when nuclear

Kroenig, Matthew

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Executive Director for Operations UPDATE OF ISSUES RELATED TO NUCLEAR POWER REACTOR FINANCIAL QUALIFICATIONS IN RESPONSE TO RESTRUCTURING OF THE ELECTRIC UTILITY INDUSTRY  

E-Print Network (OSTI)

To provide the Commission with an update of electric utility deregulation and restructuring issues regarding the financial qualifications of power reactor licensees to operate their facilities safely. BACKGROUND: On October 24, 1997, the staff sent to the Commission SECY-97-253, "Policy Options for Nuclear Power Reactor Financial Qualifications in Response to Restructuring of the Electric Utility Industry. " In that paper, the staff discussed three options for the Commission's consideration regarding possible approaches that the NRC could use in assessing the financial qualifications of power reactor licensees to operate their plants safely. (The impact of deregulation and restructuring on decommissioning funding assurance is being addressed in a separate rulemaking, which was published in the Federal Register on September 10, 1997. A final rule is scheduled to be sent to the Commission by June 30, 1998.) In response to SECY-97-253, the Commission issued a staff requirements memorandum on January 15, 1998, and directed the staff to maintain the existing financial qualifications framework as discussed in Option 2 of SECY-97-253 and to "develop a coherent, efficient plan that would allow timely confirmation of the status of licensees (i.e., whether they meet the definition of 'electric utility')as deregulation actions are finalized by States. " In response, on April 16, 1998, the

L. Joseph Callan /s; Robert S. Wood

1998-01-01T23:59:59.000Z

42

Joint Technical Operations Team | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Joint Technical Operations Team | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

43

INTERNATIONAL CO-OPERATION IN NUCLEAR DATA EVALUATION  

SciTech Connect

The OECD Nuclear Energy Agency (NEA) is organising a co-operation between the major nuclear data evaluation projects in the world. The co-operation involves the ENDF, JEFF, and JENDL projects, and, owing to the collaboration with the International Atomic Energy Agency (IAEA), also the Russian RUSFOND and the Chinese CENDL projects. The Working Party on international nuclear data Evaluation Cooperation (WPEC), comprised of about 20 core members, manages this co-operation and meets annually to discuss progress in each evaluation project and also related experimental activities. The WPEC assesses common needs for nuclear data improvements and these needs are then addressed by initiating joint evaluation efforts. The work is performed in specially established subgroups, consisting of experts from the participating evaluation projects. The outcome of these subgroups is published in reports, issued by the NEA. Current WPEC activities comprise for example a number of studies related to nuclear data uncertainties, including a review of methods for the combined use of integral experiments and covariance data, as well as evaluations of some of the major actinides, such as {sup 235}U and {sup 239}Pu. This paper gives an overview of current and planned activities within the WPEC.

Herman, M.; Katakura,J.; Koning,A.; Nordborg,C.

2010-04-30T23:59:59.000Z

44

DOE/EIS-0373D; Draft Environmental Impact Statement for the Proposed Consolidation of Nuclear Operations Related to Production of Radioisotope Power Systems  

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

For For additional information or for copies of this Draft EIS, contact: AVAILABILITY OF THE DRAFT CONSOLIDATION EIS Printed with soy ink on recycled paper Timothy A. Frazier, EIS Document Manager NE-50/Germantown Building Office of Nuclear Energy, Science and Technology U.S. Department of Energy 1000 Independence Avenue, SW Washington, DC 20585-1290 Telephone: 1-800-919-3706 E-mail: ConsolidationEIS@nuclear.energy.gov This document is available on the Office of Nuclear Energy, Science and Technology's Website (http://consolidationeis.doe.gov) for viewing and downloading. TABLE OF CONTENTS vii TABLE OF CONTENTS Cover Sheet ..................................................................................................................................................................iii Table of Contents ........................................................................................................................................................vii

45

National Nuclear Security Administration (NNSA) Operating Principles  

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

Operating Principles Operating Principles Our wtis.sion is vitcrl ~ r i r l urgent - rue corrstnntly jOcus on missiort outconles. - US nuclear security is the fundamental mission of the NNSA and its laboratories, plants, and test site. - Mission managers bear responsibility for achieving mission outcomes. - Support managers provide technical assistance and support to enable mission delivery. - Our activities reflect a mission-focused, high performing. high reliability enterprise consistently delivering on its commitmerits and addressing national needs. - We constantly strive to drive innovation and reduce barriers to effectively and collaboratively accomplish our mission. Scierrce crnd fecltnology lie crt the hetrrt ?four mission. - The NNSA and its laboratories, plants, and test site are resources to organizations in the US Government

46

Operations Center | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

47

Emergency Operations Training Academy | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

48

Our Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

49

NIST: Methane Symmetry Operations - Nuclear spin stats  

Science Conference Proceedings (OSTI)

... 9.2 Nuclear spin statistics and overall parities. ... Molecule, Rovibrational species, Nuclear spin functions, Overall species, Statistical weight. ...

50

FAQS Qualification Card - Nuclear Operations Specialist | Department of  

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

Nuclear Operations Specialist Nuclear Operations Specialist FAQS Qualification Card - Nuclear Operations Specialist A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NuclearOperationsSpecialist.docx Description Nuclear Operations Specialist Qualification Card More Documents & Publications

51

Space nuclear power, propulsion, and related technologies.  

SciTech Connect

Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government organizations, and has already formed several cooperative alliances and agreements. Because of the synergism of multiple governmental and industrial sponsors of many programs, Sandia is frequently able to provide complex technical solutions in a relatively short time, and often at lower cost to a particular customer. They have listed a few ongoing programs at Sandia related to space nuclear technology as examples of the possible synergisms that could result from forming teams and partnerships with related technologies and objectives.

Berman, Marshall

1992-01-01T23:59:59.000Z

52

Space nuclear power, propulsion, and related technologies.  

SciTech Connect

Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government organizations, and has already formed several cooperative alliances and agreements. Because of the synergism of multiple governmental and industrial sponsors of many programs, Sandia is frequently able to provide complex technical solutions in a relatively short time, and often at lower cost to a particular customer. They have listed a few ongoing programs at Sandia related to space nuclear technology as examples of the possible synergisms that could result from forming teams and partnerships with related technologies and objectives.

Berman, Marshall

1992-01-01T23:59:59.000Z

53

Spent Nuclear Fuel Project operational staffing plan  

SciTech Connect

Using the Spent Nuclear Fuel (SNF) Project`s current process flow concepts and knowledge from cognizant engineering and operational personnel, an initial assessment of the SNF Project radiological exposure and resource requirements was completed. A small project team completed a step by step analysis of fuel movement in the K Basins to the new interim storage location, the Canister Storage Building (CSB). This analysis looked at fuel retrieval, conditioning of the fuel, and transportation of the fuel. This plan describes the staffing structure for fuel processing, fuel movement, and the maintenance and operation (M&O) staffing requirements of the facilities. This initial draft does not identify the support function resources required for M&O, i.e., administrative and engineering (technical support). These will be included in future revisions to the plan. This plan looks at the resource requirements for the SNF subprojects, specifically, the operations of the facilities, balances resources where applicable, rotates crews where applicable, and attempts to use individuals in multi-task assignments. This plan does not apply to the construction phase of planned projects that affect staffing levels of K Basins.

Debban, B.L.

1996-03-01T23:59:59.000Z

54

WEB RESOURCE: Nuclear Physics and Related Computational ...  

Science Conference Proceedings (OSTI)

Feb 6, 2007 ... This site provides presentations from the Nuclear Physics and Related Computational Science R&D for Advanced Fuel Cycles Workshop:

55

Table 3. Nuclear Reactor Characteristics and Operational ...  

U.S. Energy Information Administration (EIA)

Point Beach Nuclear Plant Quad Cities Generating Station R.E. Ginna Nuclear Power Plant PSEG Salem Generating Station Harris South Texas Project PPL ...

56

Executive Director for Operations RENEWAL OF FULL-POWER OPERATING LICENSE FOR PILGRIM NUCLEAR POWER STATION  

E-Print Network (OSTI)

This paper (1) requests that the Commission authorize the Director of the Office of Nuclear Reactor Regulation (NRR) to renew the operating license for Pilgrim Nuclear Power Station (PNPS) for an additional 20 years, and (2) informs the Commission of the results of the U.S. Nuclear Regulatory Commission (NRC) staffs review of the PNPS license renewal application (LRA) (Ref. 1) submitted by Entergy Nuclear Generation Company (Entergy Nuclear) and Entergy Nuclear Operations, Inc. (ENO) (owner and operator, respectively, of PNPS). In the Staff Requirements Memorandum for SECY-02-0088, Turkey Point Nuclear Plant, Units 3 and

R. W. Borchardt

2012-01-01T23:59:59.000Z

57

Nuclear Maintenance Applications Center: Application Guide for Motor-Operated Valves in Nuclear Power Plants - Revision 2  

Science Conference Proceedings (OSTI)

Motor-operated gate and globe valves are widely used in both safety-related and non-safety-related systems in nuclear power plants. Their proper operation is essential for reliable plant performance and can help eliminate costly downtime. This second revision of the Application Guide for Motor-Operated Valves provides the latest in methods for conducting engineering evaluations in order to confirm that motor-operated gate, globe, and butterfly valves will perform their required function and offers sugges...

2007-08-22T23:59:59.000Z

58

HANDBOOK FOR CONDUCTING ORAL HISTORY INTERVIEWS RELATED TO TRIBAL AND INDIAN PARTICIPATION IN THE CONSTRUCTION, OPERATION AND CLEANUP OF THE NUCLEAR WEAPONS COMPLEX  

SciTech Connect

There were three major projects undertaken at the outset of the DOE/EM 22 Cooperative Agreement back in September 1995. There was a project relating to Tribal oral histories. Another project of the Cooperative Agreement related to technology and Tribal values and needs. This project by analogy could apply to issues of technology, environmental cleanup and other indigenous peoples internationally. How can Indian Tribes participate in defining the need for technology development rather than merely learning to adapt themselves and their situations and values to technology developed by others with differing needs, values and economic resources? And the third project was the placement of a Tribal intern in EM-22.

Cristann Gibson; Mervyn L. Tano; Albert Wing

1999-08-31T23:59:59.000Z

59

DHS/National Operations Center | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room...

60

Infrastructure and Operations | National Nuclear Security Administrati...  

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

for Infrastructure and Operations develops and executes NNSA's infrastructure investment, maintenance, and operations programs and policies. Printer-friendly version...

Note: This page contains sample records for the topic "nuclear operations related" 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

Emergency Operations Training Academy | National Nuclear Security...  

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

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

62

Advanced Nuclear Technology: Impact of EPRI Pre-Operational and Operational Configuration Management Report (1022684) on the Nuclear Industry  

Science Conference Proceedings (OSTI)

EPRI Technical Report 1022684, Elements of Pre-Operational and Operational Configuration Management for a New Nuclear Facility, was developed by an EPRI Advanced Nuclear Technology (ANT) technical advisory group whose mission was to develop guidance for establishing a comprehensive configuration management (CM) program for the unique challenges of a new nuclear facility. The program elements developed for the pre-operation phase would then be in place to manage the configuration for the ...

2013-03-20T23:59:59.000Z

63

Nuclear Safety Research and Development Program Operating Plan | Department  

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

Program Operating Plan Program Operating Plan Nuclear Safety Research and Development Program Operating Plan July 5, 2012 Nuclear Safety Research and Development Program Operating Plan This operating plan outlines the mission, goals, and processes for the Department of Energy's (DOE) Nuclear Safety Research & Development (NSR&D) Program. This first version of the operating plan also discusses the startup phase of the program. NSR&D involves a systematic search for knowledge to advance the fundamental understanding of nuclear safety science and technology through scientific study, analysis, modeling, and experiments. Maintaining an effective NSR&D program will support DOE and the National Nuclear Security Administration (NNSA) in standards development, validation of analytical models and

64

Safeguards and Nuclear Materials Management: A view from the DOE Chicago Operations Office  

SciTech Connect

Nuclear Materials Safeguards (also known as Material Control and Accountability or MC&A) and Nuclear Materials Management as practiced within the US Department of Energy (DOE) are separate, but related disciplines with differing goals and objectives. Safeguards and Nuclear Materials Management are closely related through the common use of transaction and inventory reporting data from the Nuclear Materials Management and Safeguards System (NMMSS). Adherence to Nuclear Materials management principals may enhance Nuclear Materials Safeguards, and has the potential to result in savings for both program and safeguards costs. Both the Safeguards and Nuclear Materials Management Programs for the Chicago Operations Office are administered by the Safeguards and Security Division, Safeguards Branch. This paper discusses Safeguards and Materials Management issues within the Chicago Operations Office, some of which relate to problems faced by the DOE complex as a whole.

Healy, F.E.; Ahlberg, C.G.

1994-07-01T23:59:59.000Z

65

Nuclear Power 2010 Program: Combined Construction and Operating License &  

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

Nuclear Power 2010 Program: Combined Construction and Operating Nuclear Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report Nuclear Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report The Nuclear Power 2010 (NP 2010) Construction and Operating License/Design Certification (COL/DC) Demonstration program together with the financial incentives provided by the Energy Policy Act of 2005 are the two primary reasons why a number of license applications for new nuclear construction are before the NRC today, and why the first new nuclear plants in over 30 years are under construction in the United States. As with all significant endeavors, there are lessons to be learned from the

66

Construction or Extended Operation of Nuclear Plant (Vermont) | Department  

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

Construction or Extended Operation of Nuclear Plant (Vermont) Construction or Extended Operation of Nuclear Plant (Vermont) Construction or Extended Operation of Nuclear Plant (Vermont) < Back Eligibility Investor-Owned Utility Utility Program Info State Vermont Program Type Siting and Permitting Any petition for approval of construction of a nuclear energy generating plant within the state, or any petition for approval of the operation of a nuclear energy generating plant beyond the date established in a certificate of public good issued under this title, must be submitted to the public service board no later than four years before the date upon which the approval may take effect. Upon receipt of a petition for approval of construction or operation as provided under this section, the public service board shall notify the

67

NNSA Streamlines Operations | National Nuclear Security Administration  

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

Y-12 Earn 11 R&D 100 Awards Jul 2, 2013 US, International Partners Remove Last Remaining HEU from Vietnam, Set Nuclear Security Milestone View All > Timeline Curious about NNSA...

68

Lempke receives Sandia Emergency Operations Center tour | National Nuclear  

National Nuclear Security Administration (NNSA)

receives Sandia Emergency Operations Center tour | National Nuclear receives Sandia Emergency Operations Center tour | 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 > Lempke receives Sandia Emergency Operations Center tour Lempke receives Sandia Emergency Operations Center tour Posted By Office of Public Affairs NNSA Blog Brian Bielecki, Director & Facility Security Officer for Security &

69

Our Operations | National Nuclear Security Administration  

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

and operations programs and policies. Administration Programs Management and Budget NNSA's Office of Management and Administration's goal is to create a well-managed,...

70

Related Links | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

The National Nuclear Security Administration The National Nuclear Security Administration Related Links Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > Related Links Related Links NNSA Lab Directed Research and Development (LDRD) Lab Directed Research and Development Collaborations DOE Adanced Scientific Computing Research DTRA (Defense Threat Reduction Agency) NAS (National Academy of Sciences) NSF (National Science Foundation) DOD (Department of Defense) NASA Exascale Activities NNSA Exascale Environment Planning Workshop ASCR Co-Design Centers Supercomputing Top 500 List ASC at Supercomputing Conference Printer-friendly version Printer-friendly version Facebook

71

Institute of Nuclear Power Operations 1994 annual report  

SciTech Connect

This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

NONE

1994-12-31T23:59:59.000Z

72

Institute of Nuclear Power Operations annual report, 1993  

SciTech Connect

This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry.

NONE

1993-12-31T23:59:59.000Z

73

Nuclear Power 2010 Program: Combined Construction and Operating License &  

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

Power 2010 Program: Combined Construction and Operating Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report Nuclear Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report The Nuclear Power 2010 (NP 2010) Construction and Operating License/Design Certification (COL/DC) Demonstration program together with the financial incentives provided by the Energy Policy Act of 2005 are the two primary reasons why a number of license applications for new nuclear construction are before the NRC today, and why the first new nuclear plants in over 30 years are under construction in the United States. As with all significant endeavors, there are lessons to be learned from the

74

Energy Fuels Nuclear, Inc. Arizona Strip Operations  

Science Conference Proceedings (OSTI)

Founded in 1975 by uranium pioneer, Robert W. Adams, Energy Fuels Nuclear, Inc. (EFNI) emerged as the largest US uranium mining company by the mid-1980s. Confronting the challenges of declining uranium market prices and the development of high-grade ore bodies in Australia and Canada, EFNI aggressively pursued exploration and development of breccia-pipe ore bodies in Northwestern Arizona. As a result, EFNI's production for the Arizona Strip of 18.9 million pounds U[sub 3]O[sub 8] over the period 1980 through 1991, maintained the company's status as a leading US uranium producer.

Pool, T.C.

1993-05-01T23:59:59.000Z

75

Related Links | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Los Alamos Field Office > Related Los Alamos Field Office > Related Links Related Links NNSA and Other Related Links DOE/NNSA Phonebook Freedom of Information Act Department of Energy DOE Directives DOE Jobs Online Defense Nuclear Facilities Safety Board DOE Pulse Publication DOE Office of Health, Safety and Security USA.Gov Los Alamos County Los Alamos National Laboratory LANL Phonebook National Nuclear Security Administration NNSA Service Center - Albuquerque NNSA Nevada Field Office New Mexico Environmental Department - LANL Sandia National Laboratories Waste Isolation Pilot Plant U.S. Department of Homeland Security Code of Federal Regulations Printer-friendly version Printer-friendly version Facebook Twitter Youtube Flickr General Information About Los Alamos Field Office Contact Us Employee Concerns Program

76

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

nature of the nuclear recipients security environment. ThisKeywords: Nuclear weapons proliferation; security; securitynature of the nuclear recipients security environment. This

Kroenig, Matthew

2006-01-01T23:59:59.000Z

77

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

2004. The nuclear fuel cycle: A challenge forhave mastered parts of the nuclear fuel cycle, but have notprovision of fuel-cycle services, in which nuclear capable

Kroenig, Matthew

2006-01-01T23:59:59.000Z

78

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

of nuclear proliferation: a quantitative test. Journal ofINTERNATIONAL NUCLEAR ASSISTANCE DATA To test this strategictheory of nuclear proliferation faces a difficult test in

Kroenig, Matthew

2006-01-01T23:59:59.000Z

79

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

coupled and complex systems like nuclear weapons arsenals.The complex technology required to build nuclear weapons is

Kroenig, Matthew

2006-01-01T23:59:59.000Z

80

Wolf Creek Nuclear Operating Corporation | Open Energy Information  

Open Energy Info (EERE)

Wolf Creek Nuclear Operating Corporation Wolf Creek Nuclear Operating Corporation Jump to: navigation, search Name Wolf Creek Nuclear Operating Corporation Place Burlington, Kansas Zip 66839-0411 Product Wolf Creek Nuclear Operating Corporation operates the Wolf Creek Generating Station, Kansas' first nuclear power generating station, for three utility owners in Kansas and Missouri. Coordinates 44.446275°, -108.431704° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":44.446275,"lon":-108.431704,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

Note: This page contains sample records for the topic "nuclear operations related" 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

Nuclear magnetic moments and related sum rules  

SciTech Connect

We first review the history and our present understanding of nuclear magnetic moments and Gamow-Teller transitions, with emphasis on the roles of configuration mixing and meson exchange currents. Then we discuss the renormalization of the orbital g-factor in nuclei, and its relation to the E1 sum rule for photoabsorption and the M1 sum rule for the scissors mode of deformed nuclei.

Bentz, Wolfgang [Department of Physics, School of Science, Tokai University, Hiratsuka-shi, Kanagawa 259-1292 (Japan); Arima, Akito [Musashi University, 1-26-1 Toyotama-kami, Nerima-ku, Tokyo 176-8534 (Japan)

2011-05-06T23:59:59.000Z

82

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

204. Bhatia, Shyam. 1988. Nuclear rivals in the Middle East.of the merits of selective nuclear proliferation. Journal ofThe Case for a Ukranian nuclear deterrent. Foreign Affairs.

Kroenig, Matthew

2006-01-01T23:59:59.000Z

83

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

ambitions: The spread of nuclear weapons 1989-1990. Boulder:Determinants of nuclear weapons proliferation. UnpublishedWhy nations forgo nuclear weapons. Montreal: McGill-Queens

Kroenig, Matthew

2006-01-01T23:59:59.000Z

84

Nuclear Safety Reserch and Development Program Operating Plan  

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

Safety Research and Development Safety Research and Development Program Operating Plan Office of Nuclear Safety Office of Health, Safety and Security U.S. Department of Energy June 2012 INTENTIONALLY BLANK NSR&D Program Operating Plan June 2012 Table of Contents 1.0 INTRODUCTION................................................................................................................. 1 2.0 BACKGROUND ................................................................................................................... 1 3.0 OBJECTIVES ....................................................................................................................... 2 4.0 NSR&D PROGRAM PROCESSES .................................................................................... 3

85

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

nuclear trade and nonproliferation. Lexington, MA: LexingtonA challenge for nonproliferation. Disarmament Diplomacy. (Nuclear Suppliers Group. Nonproliferation Review 1(1):110.

Kroenig, Matthew

2006-01-01T23:59:59.000Z

86

Integrating Nuclear Energy to Oilfield Operations Two Case Studies  

Science Conference Proceedings (OSTI)

Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressure steam (no electricity production) was selected as the nuclear power source for both fossil fuel resources. Both cases were based on 50,000 bbl/day output. The oil sands case was a steam-assisted, gravity-drainage (SAGD) operation located in the Canadian oil sands belt. The oil shale development was an in-situ oil shale retorting operation located in western Colorado, USA. The technical feasibility of the integrating nuclear power was assessed. The economic feasibility of each case was evaluated using a discounted cash flow, rate of return analysis. Integrating an HTGR to both the SAGD oil sands operation and the oil shale development was found to be technically feasible for both cases. In the oil sands case, integrating an HTGR eliminated natural gas combustion and associated CO2 emissions, although there were still some emissions associated with imported electrical power. In the in situ oil shale case, integrating an HTGR reduced CO2 emissions by 88% and increased natural gas production by 100%. Economic viabilities of both nuclear integrated cases were poorer than the non-nuclear-integrated cases when CO2 emissions were not taxed. However, taxing the CO2 emissions had a significant effect on the economics of the non-nuclear base cases, bringing them in line with the economics of the nuclear-integrated cases. As we move toward limiting CO2 emissions, integrating non-CO2-emitting energy sources to the development of energy-intense fossil fuel resources is becoming increasingly important. This paper attempts to reduce the barriers that have traditionally separated fossil fuel development and application of nuclear power and to promote serious discussion of ideas about hybrid energy systems.

Eric P. Robertson; Lee O. Nelson; Michael G. McKellar; Anastasia M. Gandrik; Mike W. Patterson

2011-11-01T23:59:59.000Z

87

Freedom of Information Act Related Sites | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

agency established by Congress in 1988 to provide safety oversight of the nuclear weapons complex operated by the DOE. National Technical Information Service A centralized...

88

An analysis of nuclear power plant operating costs: A 1995 update  

SciTech Connect

Over the years real (inflation-adjusted) O&M cost have begun to level off. The objective of this report is to determine whether the industry and NRC initiatives to control costs have resulted in this moderation in the growth of O&M costs. Because the industry agrees that the control of O&M costs is crucial to the viability of the technology, an examination of the factors causing the moderation in costs is important. A related issue deals with projecting nuclear operating costs into the future. Because of the escalation in nuclear operating costs (and the fall in fossil fuel prices) many State and Federal regulatory commissions are examining the economics of the continued operation of nuclear power plants under their jurisdiction. The economics of the continued operation of a nuclear power plant is typically examined by comparing the cost of the plants continued operation with the cost of obtaining the power from other sources. This assessment requires plant-specific projections of nuclear operating costs. Analysts preparing these projections look at past industry-wide cost trends and consider whether these trends are likely to continue. To determine whether these changes in trends will continue into the future, information about the causal factors influencing costs and the future trends in these factors are needed. An analysis of the factors explaining the moderation in cost growth will also yield important insights into the question of whether these trends will continue.

1995-04-21T23:59:59.000Z

89

U.S. Nuclear Power Plant Operating Cost and Experience Summaries  

Science Conference Proceedings (OSTI)

The ''U.S. Nuclear Power Plant Operating Cost and Experience Summaries'' (NUREG/CR-6577, Supp. 2) report has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants during 2000-2001. Costs incurred after initial construction are characterized as annual production costs, which represent fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications, which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operations summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from operating reports submitted by the licensees, the Nuclear Regulatory Commission (NRC) database for enforcement actions, and outage reports.

Reid, RL

2003-09-18T23:59:59.000Z

90

Nuclear Maintenance Applications Center: Air-Operated Valve Maintenance Guide: Revision 2  

Science Conference Proceedings (OSTI)

An increased awareness of the importance of air-operated valves (AOVs) has led to progressively more sophisticated maintenance practices within the nuclear industry. Nonnuclear plants are also heavily dependent on reliable AOV operation. The dynamic method used by fossil power plants to satisfy transient electrical demands places additional stress on plant components, including AOVs. Therefore, there is a growing need for standardized technical guidance related to AOVs. The Electric Power Research Instit...

2008-12-18T23:59:59.000Z

91

Nuclear safety surveillance and control of National Nuclear Safety Administration of PRC during commissioning and operation of nuclear power plants  

Science Conference Proceedings (OSTI)

This article describes the method of nuclear safety surveillance and control of National Nuclear Safety Administration (NNSA) of PRC during commissioning and operation of nuclear power plants (NPPs) and the practice for Qinshan NPP and for Guangdong Daya Bay NPP (GNPS). The results of the practice show that the surveillance models set up for Qinshan NPP and for GNPS commissioning were effective and the surveillance has played an important role for ensuring the quality and safety of the commissioning testing and consequently the nuclear safety of these two plants.

Feng, W.; Zhang, C.

1994-12-31T23:59:59.000Z

92

Institutional plan -- Institute of Nuclear Power Operations, 1993  

Science Conference Proceedings (OSTI)

The US nuclear electric utility industry established the Institute of Nuclear Power Operations (INPO) in 1979 to promote the highest levels of safety and reliability -- to promote excellence -- in the operation of its nuclear plants. After its formation, the Institute grew from a handful of on-loan personnel in late 1979 to an established work force of more than 400 permanent and on-loan personnel. INPO`s early years were marked by growth and evolution of its programs and organization. The Institute now focuses primarily on the effectiveness and enhancement of established programs and activities. For INPO to carry out its role, it must have the support of its members and participants and a cooperative but independent relationship with the NRC. A basis for that support and cooperation is an understanding of INPO`s role. This Institutional Plan is intended to provide that understanding by defining the Institute`s role and its major programs. This plan considers the existing and projected needs of the industry and the overall environment in which INPO and its members and participants operate.

Not Available

1993-12-31T23:59:59.000Z

93

Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors  

DOE Green Energy (OSTI)

The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

OHara J. M.; Higgins, J.; DAgostino, A.

2012-01-17T23:59:59.000Z

94

Cognitive skill training for nuclear power plant operational decision making  

SciTech Connect

Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills.

Mumaw, R.J.; Swatzler, D.; Roth, E.M. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Thomas, W.A. [Quantum Technologies, Inc., Oak Brook, IL (United States)

1994-06-01T23:59:59.000Z

95

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

1987-08-01T23:59:59.000Z

96

Joint Technical Operations Team | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

97

Work for Nuclear Regulatory Commission, Safety Related Applications  

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

Nuclear Regulatory Nuclear Regulatory Commission Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share Nuclear Regulatory Commission International Steam Generator Tube Integrity Program Key objectives of the International Steam Generator Tube Integrity Program

98

Safety Related Applications (Sensors and Instrumentation and NDE) - Nuclear  

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

DOE Office of DOE Office of Nuclear Energy, Science, and Technology Capabilities Sensors and Instrumentation and Nondestructive Evaluation Overview Energy System Applications Safety-Related Applications Overview DOE Office of Nuclear Energy, Science, and Technology Nuclear Regulatory Commission National Aeronautics and Space Administration (NASA) Homeland Security Applications Biomedical Applications Millimiter Wave Group Papers Other NPNS Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Sensors and Instrumentation and Nondestructive Evaluation Safety Related Applications Bookmark and Share DOE Office of Nuclear Energy, Science, and Technology The objective of this Nuclear Energy Plant Optimization Project is to

99

Effects of delaying the operation of a nuclear power plant  

Science Conference Proceedings (OSTI)

This report documents a study of an actual 24-month nuclear power plant licensing delay. A representative utility was chosen for examination. The research was oriented toward determination of the licensing delay's impact on the utility's operating results, ratepayers, and security issues. The methodology utilized to estimate those impacts involved the recursive interaction of a generation costing program to estimate replacement fuel costs and a financial regulatory model to concomitantly determine the impact on the utility, its ratepayers and security issues. The latter model was executed under six alternate scenarios: (1) no delay in the plant's operation; (2) a 24-month delay; (3) a 24-month delay but further assuming all replacement power was generated by coal-fired plants; (4) a 24-month delay assuming all replacement power from oil-fired plants; (5) no delay but assuming the capital cost of the plant was twice as large; and (6) a 24-month delay with the capital cost of the plant twice as large. Three primary conclusions were made. First, under all scenarios, a 24-month delay in operation of the plant has an adverse impact on the utility's internal generation of funds. Second, although electricity rates are not appreciably affected by the delay, the direction of electricity price changes is contingent on the source of fuel used for replacement power. Finally, a 24-month delay has an adverse impact on the indicators used to evaluate the financial soundness of the utility in all cases under consideration.

Hill, L.J.; Rainey, J.A.; Tepel, R.C.; Van Dyke, J.W.

1983-12-01T23:59:59.000Z

100

Savannah River Operations Office Interim Management of Nuclear  

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

0 0 Federal Register / Vol. 62, No. 70 / Friday, April 11, 1997 / Notices 1 The term ''failed'' means that the cladding on the fuel has been breached. The ROD, 60 Fed. Reg. 65300 (December 19, 1995), stated that failed fuel is indicated by gas releases from a fuel storage canister or visible failure of the cladding or canisters. select samples for specialized surveys for example on children's services or on access for persons with disabilities. [FR Doc. 97-9341 Filed 4-10-97; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Savannah River Operations Office Interim Management of Nuclear Materials at the Savannah River Site AGENCY: Department of Energy. ACTION: Supplemental record of decision and supplement analysis determination. SUMMARY: The U.S. Department of Energy (DOE) prepared a final

Note: This page contains sample records for the topic "nuclear operations related" 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

Guide for monitoring equipment environments during nuclear plant operation  

Science Conference Proceedings (OSTI)

This guide is intended to assist utilities in formulating and implementing improved monitoring programs by providing guidance on why, where and how to track environmental conditions such as temperature, radiation, and humidity for equipment in nuclear power plants during operation. The guide describes steps for implementing programs. It also gives advantages, disadvantages and costs for a variety of monitoring methods and devices such as sensors with recording devices, thermographic surveys, and passive thermal and radiation integrating devices. The guide also contains twenty technical papers presented at an environmental monitoring workshop covering the subjects of plant experience with elevated temperatures, plant environmental monitoring programs, and techniques for monitoring temperature and radiation. These individual papers have been cataloged separately.

Danahy, J.W.; Evans, R.W. (Grove Engineering, Inc., Rockville, MD (United States))

1991-06-01T23:59:59.000Z

102

Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992. Operations Services/Technical Programs  

Science Conference Proceedings (OSTI)

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

Not Available

1993-04-01T23:59:59.000Z

103

Related Links | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Livermore Field Office > Related Links Related Links NNSA FOIA DOENNSA Telephone Directory U.S. Department of Energy Lawrence Livermore National Laboratory Printer-friendly...

104

Related Links | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

& Technology Programs > Office of Advanced Simulation and Computing and Institutional R&D Programs > Related Links Related Links NNSA Lab Directed Research and Development...

105

Concept of Operations for Nuclear Warhead Embedded Sensors  

Science Conference Proceedings (OSTI)

Embedded arms-control-sensors provide a powerful new paradigm for managing compliance with future nuclear weapons treaties, where deployed warhead numbers will be reduced to 1000 or less. The CONOPS (Concept of Operations) for use with these sensors is a practical tool with which one may help define design parameters, including size, power, resolution, communications, and physical structure. How frequently must data be acquired and must a human be present? Will such data be acquired for only stored weapons or will it be required of deployed weapons as well? Will tactical weapons be subject to such monitoring or will only strategic weapons apply? Which data will be most crucial? Will OSI's be a component of embedded sensor data management or will these sensors stand alone in their data extraction processes? The problem space is massive, but can be constrained by extrapolating to a reasonable future treaty regime and examining the bounded options this scenario poses. Arms control verification sensors, embedded within the warhead case or aeroshell, must provide sufficient but not excessively detailed data, confirming that the item is a nuclear warhead and that it is a particular warhead without revealing sensitive information. Geolocation will be provided by an intermediate transceiver used to acquire the data and to forward the data to a central processing location. Past Chain-of-Custody projects have included such devices and will be primarily responsible for adding such indicators in the future. For the purposes of a treaty regime a TLI will be verified as a nuclear warhead by knowledge of (a) the presence and mass of SNM, (b) the presence of HE, and (c) the reporting of a unique tag ID. All of these parameters can be obtained via neutron correlation measurements, Raman spectroscopy, and fiber optic grating fabrication, respectively. Data from these sensors will be pushed out monthly and acquired nearly daily, providing one of several verification layers in depth, including on-site inspections, NTM, declarations, and semi-annual BCC meetings. Human intervention will not be necessary. The sheer numbers, small size, and wide distribution of warhead TLIs will mandate the added level of remote monitoring that Embedded Sensors can provide. This multilayer protection will limit the need to increase the frequency of OSIs, by adding confidence that declared TLIs remain as declared and that no undeclared items enter the regime without the other States Party's knowledge. Acceptance of Embedded arms control Sensor technologies will require joint development by all State's Parties involved. Principles of operation and robustness of technologies must be individually evaluated to sustain confidence in the strength of this system against attack. Weapons designers must be assured that these sensors will in no way impact weapon performance and operation, will not affect weapons security and safety, and will have a neutral impact upon weapon system surety. Each State's Party will need to conduct an in depth review of their weapons lifecycle to determine where moves may be reduced to minimize vulnerabilities and where random selection may be used to minimize the ability to make undeclared changes. In the end Verification is a political measure, not a technical one. If the potential users can gain sufficient confidence in the application of Embedded arms control Sensors, they could constitute the final layer of glue to hold together the next Nuclear Arms Control agreement.

Rockett, P D; Koncher, T R

2012-05-16T23:59:59.000Z

106

Identification of good practices in the operation of nuclear power plants  

E-Print Network (OSTI)

This work developed an approach to diagnose problems and identify good practices in the operation of nuclear power plants using the system dynamics technique. The research began with construction of the ORSIM (Nuclear Power ...

Chen, Haibo, 1975-

2005-01-01T23:59:59.000Z

107

Related Links | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Related Links Home > About Us > Our Programs > Defense Programs > Future Science & Technology Programs > Office of Advanced Simulation and Computing Institutional Research...

108

Analysis of Nuclear Power Plant Operating Costs: A 1995 Update, An  

Reports and Publications (EIA)

This report provides an analysis of nuclear power plant operating costs. EIA published three reports on this subject during the period 1988-1995.

James G. Hewlett

1995-04-01T23:59:59.000Z

109

Unified Procedures Applicable to Major Federal Actions Relating to Nuclear  

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

Unified Procedures Applicable to Major Federal Actions Relating to Unified Procedures Applicable to Major Federal Actions Relating to Nuclear Activities Subject to Executive Order 12114 (State Department, 44 Fed Reg 65560) Unified Procedures Applicable to Major Federal Actions Relating to Nuclear Activities Subject to Executive Order 12114 (State Department, 44 Fed Reg 65560) The following unified procedures issued by the State Department are established to satisfy the requirement of the Executive Order for implementing procedures concerning nuclear export activities of Federal agencies. 44 Fed Reg 65560: Department of State: Unified Procedures Applicable to Major Federal Actions Relating to Nuclear Activities Subject to Executive Order 12114 More Documents & Publications Environmental Effects Abroad of Major Federal Actions

110

Briefing, Classification of Nuclear Weapons-Related Information- June 2012  

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

This brief will familiarize individuals from agencies outside of DOE who may come in contact with RD and FRD with the procedures for identifying, classifying, marking, handling, and declassifying documents containing Nuclear Weapons-Related Information.

111

Nuclear Power 2010 Program: Combined Construction and Operating...  

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

applications for new nuclear construction are before the NRC today, and why the first new nuclear plants in over 30 years are under construction in the United States. As with all...

112

DHS/National Operations Center | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering...

113

Reference: Additional Plant Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation, Dresden Nuclear Power Station and Quad Cities Nuclear Power Station  

E-Print Network (OSTI)

2000 In the referenced letter, Commonwealth Edison Company, now Exelon Generation Company (EGC), LLC, submitted a request for changes to the operating licenses and Technical Specifications (TS) for Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2, to allow operation at uprated power levels. In a telephone conference on August 31, 2001, between representatives of EGC and Mr. L. W. Rossbach and other members of the NRC, the NRC requested additional information regarding these proposed changes. The attachment to this letter provides the requested information. Should you have any questions related to this letter, please contact Mr. Allan R. Haeger

K. A. Ainger

2001-01-01T23:59:59.000Z

114

Related Sites, Experimental Resources for Nuclear Data Studies...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

115

Industry Related Projects [Laser Applications Laboratory] - Nuclear  

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

Industry Related Projects Industry Related Projects Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Overview Laser Oil & Gas Well Drilling Laser Heat Treatment Laser Welding of Metals On-line Monitoring Laser Beam Delivery Laser Glazing of Railroad Rails High Power Laser Beam Delivery Decontamination and Decommissioning Refractory Alloy Welding Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Laser Applications Laboratory Industry related projects Bookmark and Share LASER OIL & GAS WELL DRILLING Using high-power lasers to drill and complete gas & oil wells LASER HEAT TREATMENT Optimization of laser beam heat treatment (Caterpillar and USCAR)

116

U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety  

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

U.S. Department of Energy Oak Ridge Operations Nuclear Facility U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide U.S. Department of Energy Oak Ridge Operations Nuclear Facility Safety Basis Fundamentals, Self-Study Guide This is an open-book evaluation. Complete the questions, and submit your answers (hand-written or electronically) to the Training Center. Someone will check and grade your answers. If you achieve a score of at least 80%, you will receive a completion certificate. Nuclear Facility Safety Basis Fundamentals Self-Study Guide Review Questions More Documents & Publications Requirements in DOE O 5480.19, Conduct of Operations Requirements for DOE Facilities Cross-referenced to DOE O 422.1, Conduct of Operations. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility

117

Underwater Maintenance Guide: Revision 2: A Guide to Diving and Remotely-Operated Vehicle Operations for Nuclear Maintenance Personnel  

Science Conference Proceedings (OSTI)

The use of water in nuclear power generating stations, both as an effective radiation barrier and thermal transfer medium, is critical to basic station operations. Consequently, underwater services play an important role in the maintenance and repair of these stations. Revision 2 of this guide expands previous discussions on underwater maintenance and provides new information on underwater welding and cutting operations and tasks.

1994-05-02T23:59:59.000Z

118

Environmental radiation protection studies related to nuclear industries, using AMS  

Science Conference Proceedings (OSTI)

14 C is produced in nuclear reactors during normal operation and part of it is continuously released into the environment. Because of the biological importance of carbon and the long physical half-life of 14 C it is of interest to study these releases. The 14 C activity concentrations in the air and vegetation around some Swedish as well as foreign nuclear facilities have been measured by accelerator mass spectrometry (AMS). 59 Ni is produced by neutron activation in the stainless steel close to the core of a nuclear reactor. The 59 Ni levels have been measured in order to be able to classify the different parts of the reactor with respect to their content of long-lived radionuclides before final storage. The technique used to measure 59 Ni at a small accelerator such as the Lund facility has been developed over the past few years and material from the Swedish nuclear industry has been analyzed.

Ragnar Hellborg; Bengt Erlandsson; Mikko Faarinen; Helena Hkansson; Kjell Hkansson; Madis Kiisk; Carl-Erik Magnusson; Per Persson; Gran Skog; Kristina Stenstrm; Sren Mattsson; Charlotte Thornberg

2001-01-01T23:59:59.000Z

119

Savannah River Operations Office Interim Management of Nuclear...  

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

Disposition of Excess Weapons Plutonium; the Office of Technology Assessment's 1993 report, Dismantling the Bomb and Managing the Nuclear Materials; comments received during the...

120

Extra-terrestrial nuclear power stations : transportation and operation  

E-Print Network (OSTI)

Many challenges exist when considering nuclear power to provide electricity for bases on the Moon or Mars, including launch safety, landing safety, deployment, control, and protecting the astronauts from radiation. Examples ...

Kane, Susan Christine

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Counterintelligence and operations security-support program for the Defense Nuclear Agency. Directive  

Science Conference Proceedings (OSTI)

The Directive establishes the counterintelligence (CI) and operations security (OPSEC) support program for the Defense Nuclear Agency which includes activities designed to protect classified and operationally sensitive unclassified information and material. Included are CI investigations, counterespionage and countersabotage operations, OPSEC analyses, technical surveillance countermeasures services, CI security education, and CI security assistance.

Nelson, L.

1983-01-25T23:59:59.000Z

122

Review of Concrete Biodeterioration in Relation to Buried Nuclear Waste  

Science Conference Proceedings (OSTI)

Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial activity on concrete surfaces are discussed.

Turick, C; Berry, C.

2012-10-15T23:59:59.000Z

123

U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility  

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

Energy, Oak Ridge Operations Office Nuclear Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak Ridge Reservation. By completing this self-study guide, the reader will fulfill ORO Safety Basis Qualification Standard Competency 1, 2 (Part 1), or 7 (Part 1) and gain a familiarity level of knowledge regarding the following:

124

U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility  

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

U.S. Department of Energy, Oak Ridge Operations Office Nuclear U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)] "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak Ridge Reservation. By completing this self-study guide, the reader will fulfill ORO Safety Basis Qualification Standard Competency 1, 2 (Part 1), or 7 (Part 1) and gain a familiarity level of knowledge regarding the following:

125

Operating experience review for nuclear power plants in the Systematic Evaluation Program  

Science Conference Proceedings (OSTI)

The Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program (SEP) whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. This paper describes the methodology and results of the operational experience review portion of the SEP evaluation. SEPB will combine the results from these operational reviews with other safety topic evaluations to perform an integrated assessment of the SEP plants.

Mays, G.T.; Harrington, K.H.

1982-01-01T23:59:59.000Z

126

Spent nuclear fuel project cold vacuum drying facility operations manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-05-12T23:59:59.000Z

127

Nondestructive Evaluation: Recommended Practices for Maintaining Radiation Safety of Radiographic Operations at a Nuclear Plant  

Science Conference Proceedings (OSTI)

Radiation safety programs for radiographic operations at nuclear power plants are more complex than for those operations at other types of industrial and commercial facilities. This level of complexity arises because of the numerous challenges to maintenance of excellence in radiation safety at nuclear power facilities where sources of radiation may be found at various locations in the facility and multiple safety functions must be considered at all times. The facilities themselves are also large with mu...

2010-12-23T23:59:59.000Z

128

Assessment of inservice conditions of safety-related nuclear plant structures  

Science Conference Proceedings (OSTI)

The report is a compilation from a number of sources of information related to the condition Of structures and civil engineering features at operating nuclear power plants in the United States. The most significant information came from the hands-on inspection of the six old plants (licensed prior to 1977) performed by the staff of the Civil Engineering and Geosciences Branch (ECGB) in the Division of Engineering of the Office of Nuclear Reactor Regulation. For the containment structures, most of the information related to the degraded conditions came from the licensees as part of the Licensing Event Report System (10 CFR 50.73), or as part of the requirement under limiting condition of operation of the plant-specific Technical Specifications. Most of the information related to the degradation of other Structures and civil engineering features was extracted from the industry survey, the reported incidents, and the plant visits. The report discusses the condition of the structures and civil engineering features at operating nuclear power plants and provides information that would help detect, alleviate, and correct the degraded conditions of the structures and civil engineering features.

Ashar, H.; Bagchi, G.

1995-06-01T23:59:59.000Z

129

Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications  

SciTech Connect

The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

Naus, Dan J [ORNL

2009-05-01T23:59:59.000Z

130

Multimedia Resources related to Argonne's Nuclear Science and...  

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

Science and Technology Legacy > Multimedia Director's Welcome Organization Achievements Nuclear Energy Nuclear Reactors CP-1 70th Anniversary Argonne's Nuclear Science and...

131

BOOK: Safety Related Issues of Spent Nuclear Fuel Storage  

Science Conference Proceedings (OSTI)

Sep 26, 2007... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science ... Fifteen papers cover aluminum-clad fuel discharged from research...

132

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - EM Statement - November 24, 2009  

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

Defense Nuclear Facilities Safety Board Public Meeting on Defense Nuclear Facilities Safety Board Public Meeting on Oversight of Complex High Hazard Nuclear Operations Statement of Dr. Ines Triay Assistant Secretary, DOE Office of Environmental Management November 24, 2009 Good morning Mr. Vice Chairman and Members of the Defense Nuclear Facilities Safety Board. I appreciate the opportunity to be here today to represent the Department of Energy's Office of Environmental Management (EM) and address the actions our office has taken regarding oversight of complex high hazard nuclear operations. My remarks cover the six topics you provided to the Secretary in your letter dated August 25, 2009. Expectations of the senior Department of Energy (DOE) leadership with respect to safety philosophy and safety management approach.

133

DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its  

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

DOE Selects Savannah River Nuclear Solutions, LLC to Manage and DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its Savannah River Site DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its Savannah River Site January 10, 2007 - 10:24am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Savannah River Nuclear Solutions (SRNS), LLC has been selected as the management and operating contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $800 million per year and is for a five-year base period with the option to extend it for up to five additional years. SRNS is a limited liability corporation consisting of Fluor Federal Services, Inc., Honeywell International, Inc., and Newport News

134

DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its  

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

Savannah River Nuclear Solutions, LLC to Manage and Savannah River Nuclear Solutions, LLC to Manage and Operate its Savannah River Site DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its Savannah River Site January 10, 2007 - 10:24am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Savannah River Nuclear Solutions (SRNS), LLC has been selected as the management and operating contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $800 million per year and is for a five-year base period with the option to extend it for up to five additional years. SRNS is a limited liability corporation consisting of Fluor Federal Services, Inc., Honeywell International, Inc., and Newport News

135

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - NNSA Statement - November 24, 2009  

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

Defense Nuclear Facilities Safety Board Public Meeting on Defense Nuclear Facilities Safety Board Public Meeting on Oversight of Complex, High Hazard Nuclear Operations Statement of Garrett Harencak, BRIG GEN, USAF Principal Assistant Deputy Administrator for Military Application Office of Defense Programs November 24, 2009 Good Morning, Mr. Vice-Chairman. I appreciate the opportunity to speak to the Board this morning regarding the Defense Programs approach to ensuring the safe management and operation of the nuclear security enterprise. Defense Programs Safety Approach and Safety Philosophy Consistent with the rest of the Department of Energy, the foundation of Defense Program's safety philosophy is Integrated Safety Management (ISM). Defense Programs and its Management and Operating Contractors continue to mature their implementation of ISM.

136

Software: MSET-related Patents - Nuclear Engineering Division (Argonne)  

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

Multivariate State Estimation Technique (MSET) Computer Code Multivariate State Estimation Technique (MSET) Computer Code Bookmark and Share Detailed Patent Information Each link below goes to the full text patent (made available at the United States Patent and Trademark Office). If you wish to view any of the images, you will need to download a viewer available from the US Patent Office. "Expert System for Online Surveillance of Nuclear Reactor Coolant Pumps," K. C. Gross, K. E. Humenik and R. M. Singer, U.S. Patent 5,223,207 (June 1993). "Expert System for Safety-Critical and Mission-Critical Equipment Operability Surveillance," K. C. Gross and R. M Singer, U.S. Patent 5,761,090 (June 1998). "Spectrum-Transformed Sequential Testing Apparatus for Sensor-Operability Surveillance Applications," K. C. Gross, K. K. Hoyer, and K E. Humenik,

137

Verification of EPRI's Nuclear Power Plant Emergency Operating Procedure Tracking System (EOPTS)  

Science Conference Proceedings (OSTI)

EPRI's emergency operating procedure tracking system (EOPTS) for BWRs was created to reduce reactor operator load and human error under nuclear power plant emergency conditions. This report describes a method for systematically verifying EOPTS. This method can help other utilities in verifying their EOPTS.

1992-10-01T23:59:59.000Z

138

Water Hammer Handbook for Nuclear Plant Engineers and Operators  

Science Conference Proceedings (OSTI)

Water hammer events continue to be responsible for costly equipment damage and plant outages. This Water Hammer Handbook is designed to help utility engineers prevent, mitigate, and accommodate water hammer events. The handbook provides assessment techniques, design approaches, and operating procedures. Also included are a root cause summary and an extensive overview of BWR and PWR water hammer experience on a system-by-system basis.

1996-10-04T23:59:59.000Z

139

Cesium Isotope Ratios as Indicators of Nuclear Power Plant Operations  

SciTech Connect

There are multiple paths by which radioactive cesium can reach the effluent from reactor operations. The radioactive 135Cs/137Cs ratios are controlled by these paths. In an effort to better understand the origin of this radiation, these 135Cs/137Cs ratios in effluents from three power reactor sites have been measured in offsite samples. These ratios are different from global fallout by up to six fold and as such cannot have a significant component from this source. A cesium ratio for a sample collected outside of the plant boundary provides integration over the operating life of the reactor. A sample collected inside the plant at any given time can be much different from this lifetime ratio. The measured cesium ratios vary significantly for the three reactors and indicate that the multiple paths have widely varying levels of contributions. There are too many ways these isotopes can fractionate to be useful for quantitative evaluations of operating parameters in an offsite sample, although it may be possible to obtain limited qualitative information for an onsite sample.

Darin Snyder; James Delmore; Troy Tranter; Nick Mann; Michael Abbott; John Olson

2011-11-01T23:59:59.000Z

140

Development of a safety assessment approach for decontamination and decommissioning operations at nuclear facilities  

SciTech Connect

The US Department of Energy (DOE) is responsible for nearly 1000 nuclear facilities which will eventually be decommissioned. In order to ensure that the health and safety of the workers, other personnel on site and the public in general is maintained during decontamination and decommissioning (D&D) operations, a methodology specifically for use in evaluating the nuclear safety of the associated activities is being developed within the Department. This methodology represents not so much a departure from that currently fish in the DOE when conducting safety assessments of operations at nuclear facilities but, rather, a formalization of those methods specifically adapted to the D&D activities. As such, it is intended to provide the safety assessment personnel with a framework on which they can base their technical judgement, to assure a consistent approach to safety assessment of D&D operations and to facilitate the systematic collection of data from facilities in the post-operational part of the life cycle.

Worthington, P.R. [USDOE, Washington, DC (United States); Cowgill, M.G. [Brookhaven National Lab., Upton, NY (United States)

1994-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Life-Limiting Issues for Long-Term Operation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report identifies and investigates issues that can be life-limiting for nuclear power plants operating beyond 60 years. It also provides a foundation and basis for evaluating life-limiting conditions and events that might challenge long-term operations. The report addresses these questions: Are there any showstoppers that will prevent plants from operating beyond 60 years? If so, what are those issues? How should these issues be managed?

2010-11-30T23:59:59.000Z

142

EDF Nuclear Power Plants Operating Experience with MOX fuel  

Science Conference Proceedings (OSTI)

EDF started Plutonium recycling in PWR in 1987 and progressively all the 20 reactors, licensed in using MOX fuel, have been loaded with MOX assemblies. At the origin of MOX introduction, these plants operated at full power in base load and the core management limited the irradiation time of MOX fuel assemblies to 3 annual cycles. Since 1995 all these reactors can operate in load follow mode. Since that time, a large amount of experience has been accumulated. This experience is very positive considering: - Receipt, handling, in core behaviour, pool storage and shipment of MOX fuel; - Operation of the various systems of the plant; - Environment impact; - Radioprotection; - Safety file requirements; - Availability for the grid. In order to reduce the fuel cost and to reach a better adequacy between UO{sub 2} fuel reprocessing flow and plutonium consumption, EDF had decided to improve the core management of MOX plants. This new core management call 'MOX Parity' achieves parity for MOX and UO{sub 2} assemblies in term of discharge burn-up. Compared to the current MOX assembly the Plutonium content is increased from 7,08% to 8,65% (equivalent to natural uranium enriched to respectively 3,25% and 3,7%) and the maximum MOX assembly burn-up moves from 42 to 52 GWd/t. This amount of burn-up is obtained from loading MOX assemblies for one additional annual cycle. Some, but limited, adaptations of the plant are necessary. In addition a new MOX fuel assembly has been designed to comply with the safety criteria taking into account the core management performances. These design improvements are based on the results of an important R and D program including numerous experimental tests and post-irradiated fuel examinations. In particular, envelope conditions compared to MOX Parity neutronic solicitations has been extensively investigated in order to get a full knowledge of the in reactor fuel behavior. Moreover, the operating conditions of the plant have been evaluated in many details and finally no important impact is anticipated. The industrial maturity of plutonium recycling activities is fully demonstrated and a new progress can be done with a complete confidence. The licensing process of 'MOX Parity' core management is in progress and its implementation on the 20 PWR is now expected at mid 2007. (author)

Thibault, Xavier [EDF Generation, Tour EDF Part Dieu - 9 rue des Cuirassiers B.P.3181 - 69402 Lyon Cedex 03 (France)

2006-07-01T23:59:59.000Z

143

Analytical relations between nuclear symmetry energy and single-nucleon potentials in isospin asymmetric nuclear matter  

E-Print Network (OSTI)

Using the Hugenholtz-Van Hove theorem, we derive general expressions for the quadratic and quartic symmetry energies in terms of single-nucleon potentials in isospin asymmetric nuclear matter. These analytical relations are useful for gaining deeper insights into the microscopic origins of the uncertainties in our knowledge on nuclear symmetry energies especially at supra-saturation densities. As examples, the formalism is applied to two model single-nucleon potentials that are widely used in transport model simulations of heavy-ion reactions.

Xu, Chang; Chen, Lie-Wen; Ko, Che Ming

2010-01-01T23:59:59.000Z

144

FUNDAMENTALS IN THE OPERATION OF NUCLEAR TEST REACTORS. VOLUME 2. MATERIALS TESTING REACTOR DESIGN AND OPERATION  

SciTech Connect

The reactor components, building, control system and circuitry, and experimental and handling facilities are described and discussed, together with operation, shutdown, tank work and supplemental facilities. Training questions and answers are included. (D.C.W.)

1963-10-01T23:59:59.000Z

145

Shutdown and low-power operation at commercial nuclear power plants in the United States. Final report  

Science Conference Proceedings (OSTI)

The report contains the results of the NRC Staff`s evaluation of shutdown and low-power operations at US commercial nuclear power plants. The report describes studies conducted by the staff in the following areas: Operating experience related to shutdown and low-power operations, probabilistic risk assessment of shutdown and low-power conditions and utility programs for planning and conducting activities during periods the plant is shut down. The report also documents evaluations of a number of technical issues regarding shutdown and low-power operations performed by the staff, including the principal findings and conclusions. Potential new regulatory requirements are discussed, as well as potential changes in NRC programs. A draft report was issued for comment in February 1992. This report is the final version and includes the responses to the comments along with the staff regulatory analysis of potential new requirements.

Not Available

1993-09-01T23:59:59.000Z

146

Impact of Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Release  

Science Conference Proceedings (OSTI)

As nuclear power plants continue to implement best practices to reduce the total radioactivity in plant effluents, other radionuclides that were not previously significant fractions of the effluent streams will need to be quantified and reported. Carbon-14 can become a principal radionuclide for the gaseous effluent pathway as the concentrations of other radionuclides decrease. This report documents the potential opportunities for further understanding the impact of nuclear power plant operations on Carb...

2011-12-08T23:59:59.000Z

147

Motor-operated valve reliability programs: Lessons learned to meet new NRC (Nuclear Regulatory Commission) requirements  

Science Conference Proceedings (OSTI)

In recent years, reliability problems have surfaced with power plant motor-operated valves (MOVs) that (a) fail to perform as designed, and/or (b) require excessive maintenance to perform their intended function. As a result, the US Nuclear Regulatory Commission (NRC) mandated certain testing and reporting requirements in inspection and enforcement bulletin 85-03 (85-03). The NRC's generic letter 89-10 (89-10) significantly expands these requirements, to include all safety-related and position-changeable MOVs. The MOV program experience at the Sacramento Municipal Utility District (SMUD) Rancho Seco plant is particularly valuable since the NRC, to a large extent, utilized this program as the prototype for 89-10's requirements. The MOV inspection, overhaul, and testing began in September 1986, with completion scheduled for December 1986. The paper discusses problems encountered, recovery plant, results of recovery planning, and lessons learned. Experience at Rancho Seco has shown that comprehensive valve programs incorporating appropriate design practices, preventive maintenance practices, and operational constraints can improve plant availability.

Anderson, M.W.; Fadel, D.P.; Fraser, P.J.

1990-06-01T23:59:59.000Z

148

Online Condition Monitoring to Enable Extended Operation of Nuclear Power Plants  

SciTech Connect

Safe, secure, and economic operation of nuclear power plants will remain of strategic significance. New and improved monitoring will likely have increased significance in the post-Fukushima world. Prior to Fukushima, many activities were already underway globally to facilitate operation of nuclear power plants beyond their initial licensing periods. Decisions to shut down a nuclear power plant are mostly driven by economic considerations. Online condition monitoring is a means to improve both the safety and economics of extending the operating lifetimes of nuclear power plants, enabling adoption of proactive aging management. With regard to active components (e.g., pumps, valves, motors, etc.), significant experience in other industries has been leveraged to build the science base to support adoption for online condition-based maintenance and proactive aging management in the nuclear industry. Many of the research needs are associated with enabling proactive management of aging in passive components (e.g., pipes, vessels, cables, containment structures, etc.). This paper provides an overview of online condition monitoring for the nuclear power industry with an emphasis on passive components. Following the overview, several technology/knowledge gaps are identified, which require addressing to facilitate widespread online condition monitoring of passive components.

Meyer, Ryan M.; Bond, Leonard J.; Ramuhalli, Pradeep

2012-03-31T23:59:59.000Z

149

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

Hoopingarner, K.R.; Vause, J.W.

1987-08-01T23:59:59.000Z

150

Sustainable Forward Operating Base Nuclear Power Evaluation (Relationship Mapping System) Users Manual  

SciTech Connect

The Sustainable Forward Operating Base (FOB) Nuclear Power Evaluation was developed by the Idaho National Laboratory Systems Engineering Department to support the Defense Advanced Research Projects Agency (DARPA) in assessing and demonstrating the viability of deploying small-scale reactors in support of military operations in theatre. This document provides a brief explanation of how to access and use the Sustainable FOB Nuclear Power Evaluation utility to view assessment results as input into developing and integrating the program elements needed to create a successful demonstration.

Not Listed

2012-01-01T23:59:59.000Z

151

Operator decision aid for breached fuel operation in liquid metal cooled nuclear reactors  

SciTech Connect

The purpose of this paper is to report the development of an expert system that provides continuous assessment of the safety significance and technical specification conformance of Delayed Neutron (DN) signals during breached fuel operation. The completed expert system has been parallelized on an innovative distributed-memory network-computing system that enables the computationally intensive kernel of the expert system to run in parallel on a group of low-cost Unix workstations. 1 ref.

Gross, K.C.; Hawkins, R.E.; Nickless, W.K.

1991-01-01T23:59:59.000Z

152

IMPROVEMENTS IN OR RELATING TO STEAM-OPERATED POWER PLANT  

SciTech Connect

A nuclear power plant is designed in which the reactor is steam-cooled and radioactivity is removed from the steam before entering the turbine. The plant has a steam circuit in which the steam from the reactor is passed through one flow path of a heat exchanger and then part of this steam is passed through contact washing equipment before being reheated in a second flow path of the heat exchanger and being led to the turbine. (D.L.C.)

Bauer, S.G.; Kendon, M.H.

1962-09-19T23:59:59.000Z

153

Introductory Human Factors Engineering Training Course for Operating Nuclear Power Plant Personnel  

Science Conference Proceedings (OSTI)

This report provides training materials for a one-day course in human factors engineering (HFE). The course is intended for utility personnel involved in modernizing operating nuclear power plant (NPP) designs and is also useful for vendors and other stakeholders. The primary focus of the HFE training is the main control room and its human-system interfaces (HSIs). In addition, it addresses other operator work locations such as the remote shutdown station, local control stations, and emergency ...

2013-05-01T23:59:59.000Z

154

Some political issues related to future special nuclear materials production  

Science Conference Proceedings (OSTI)

The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors.

Peaslee, A.T. Jr.

1981-08-01T23:59:59.000Z

155

Bevalac Operations, 1989  

Science Conference Proceedings (OSTI)

This report discusses the following topics in relation to the Bevalac accelerator: accelerator technology operations summary; nuclear science; biomedical research; and publications and presentations.

Not Available

1990-06-01T23:59:59.000Z

156

An analysis of the impacts of economic incentive programs on commercial nuclear power plant operations and maintenance costs  

SciTech Connect

Operations and Maintenance (O and M) expenditures by nuclear power plant owner/operators possess a very logical and vital link in considerations relating to plant safety and reliability. Since the determinants of O and M outlays are considerable and varied, the potential linkages to plant safety, both directly and indirectly, can likewise be substantial. One significant issue before the US Nuclear Regulatory Commission is the impact, if any, on O and M spending from state programs that attempt to improve plant operating performance, and how and to what extent these programs may affect plant safety and pose public health risks. The purpose of this study is to examine the role and degree of impacts from state promulgated economic incentive programs (EIPs) on plant O and M spending. A multivariate regression framework is specified, and the model is estimated on industry data over a five-year period, 1986--1990. Explanatory variables for the O and M spending model include plant characteristics, regulatory effects, financial strength factors, replacement power costs, and the performance incentive programs. EIPs are found to have statistically significant effects on plant O and M outlays, albeit small in relation to other factors. Moreover, the results indicate that the relatively financially weaker firms are more sensitive in their O and M spending to the presence of such programs. Formulations for linking spending behavior and EIPs with plant safety performance remains for future analysis.

Kavanaugh, D.C.; Monroe, W.H. [Pacific Northwest Lab., Richland, WA (United States); Wood, R.S. [Nuclear Regulatory Commission, Washington, DC (United States)

1996-02-01T23:59:59.000Z

157

A Case for Employing Near-field Measurements to Detect Important Effluents from Nuclear Material Processing Operations  

Science Conference Proceedings (OSTI)

General discussion of effluents from nuclear material reprocessing operations and the opportunity to detect important effluents in the near-field domain.

Hartman, John S.; Kelly, James F.; Birnbaum, Jerome C.

2007-01-31T23:59:59.000Z

158

Review of the Sandia Site Office Quality Assurance Assessment of the Manzano Nuclear Operations, January 2013  

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

of the of the Sandia Site Office Quality Assurance Assessment of the Manzano Nuclear Operations January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background ........................................................................................................................................... 1 4.0 Methodology ......................................................................................................................................... 2

159

FUNDAMENTALS IN THE OPERATION OF NUCLEAR TEST REACTORS. VOLUME 1. REACTOR SCIENCE AND TECHNOLOGY  

SciTech Connect

A resume of nuclear physics basic to reactor operation precedes discussion of aspects of reactor physics, engineering, chemistry, metallurgy, instrumentation, control, kinetics, and safety. The object is to provide an approach to and understanding of problems in irradiation test programs in the Materials Testing and Engineering Test Reactors. (D.C.W.)

1963-06-01T23:59:59.000Z

160

Safety/safeguards interactions during safety-related emergencies at Nuclear Power Reactor Facilities  

Science Conference Proceedings (OSTI)

This report contains an analysis of the safety/safeguards interactions that could occur during safety-related emergencies at licensed nuclear power reactors, and the extent to which these interactions are addressed in existing or proposed NRC guidance. The safety/safeguards interaction during a series of postulated emergencies was systematically examined to identify any potential performance deficiencies or conflicts between the Operations (safety) and Security (safeguards) organizations. This examination included the impacts of coordination with off-site emergency response personnel. Duties, responsibilities, optimal methods, and procedural actions inherent in these interactions were explored.

Moul, D.A.; Pilgrim, M.K.; Schweizer, R.L.; McEwen, J.E. Jr.

1985-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - HSS Statement draft, November 24, 2009  

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

-20-09 -20-09 1 Defense Nuclear Facilities Safety Board Public Meeting on Oversight of Complex, High Hazard Nuclear Operations Statement of Mr. Glenn Podonsky Chief Health, Safety and Security Officer U. S. Department of Energy November 24, 2009 INTRODUCTION Mr. Vice Chairman and Members of the Defense Nuclear Facilities Safety Board (DNFSB or "Board"), I am pleased to have this opportunity to discuss the Department's actions in response to the Board's Recommendation 2004-1 and other significant recommendations, initiatives, and management actions affecting nuclear safety in the Department. As the Department's Chief Health, Safety and Security Officer, I am here to update you on what we are doing and where we stand on pertinent issues, including our commitment to programs and processes aimed at the safe

162

A historical perspective of remote operations and robotics in nuclear facilities. Robotics and Intelligent Systems Program  

SciTech Connect

The field of remote technology is continuing to evolve to support man`s efforts to perform tasks in hostile environments. The technology which we recognize today as remote technology has evolved over the last 45 years to support human operations in hostile environments such as nuclear fission and fusion, space, underwater, hazardous chemical, and hazardous manufacturing. The four major categories of approach to remote technology have been (1) protective clothing and equipment for direct human entry, (2) extended reach tools using distance for safety, (3) telemanipulators with barriers for safety, and (4) teleoperators incorporating mobility with distance and/or barriers for safety. The government and commercial nuclear industry has driven the development of the majority of the actual teleoperator hardware available today. This hardware has been developed largely due to the unsatisfactory performance of the protective-clothing approach in many hostile applications. Manipulation systems which have been developed include crane/impact wrench systems, unilateral power manipulators, mechanical master/slaves, and servomanipulators. Viewing systems have included periscopes, shield windows, and television systems. Experience over the past 45 years indicates that maintenance system flexibility is essential to typical repair tasks because they are usually not repetitive, structured, or planned. Fully remote design (manipulation, task provisions, remote tooling, and facility synergy) is essential to work task efficiency. Work for space applications has been primarily research oriented with relatively few successful space applications, although the shuttle`s remote manipulator system has been quite successful. In the last decade, underwater applications have moved forward significantly, with the offshore oil industry and military applications providing the primary impetus.

Herndon, J.N.

1992-12-31T23:59:59.000Z

163

Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect

Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

Naus, Dan J [ORNL

2014-01-01T23:59:59.000Z

164

Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures  

SciTech Connect

Nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: degradation mechanisms, damage models, and material performance; assessment and remediation (i.e., component selection, in-service inspection, non-destructive examinations, and remedial actions); and estimation of performance at present or some future point in time (i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk). Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

Naus, Dan J [ORNL

2010-01-01T23:59:59.000Z

165

Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository  

Science Conference Proceedings (OSTI)

In the present energy dilemma in which we find ourselves, the magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. Nuclear energy must be a major portion of the distribution. One often-cited strategic hurdle to the commercial production of nuclear energy is the apparent lack of an acceptable nuclear waste repository. This issue has been quietly addressed at the U. S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP; see http://www.wipp.energy.gov), the closest population center of significant size being Carlsbad, New Mexico. WIPP has been operating for about nine years, disposing of over 250,000 drum-equivalents of nuclear waste. From the standpoint of addressing operational and environmental risk, as well as public fear, WIPP has had extensive human health and environmental monitoring. The Carlsbad Environmental Monitoring and Research Center is in the Institute for Energy and the Environment, in the College of Engineering at New Mexico State University. Located in Carlsbad, NM, CEMRC has been the independent monitoring facility for the area around WIPP from 1993 to the present, i.e., from six years before disposal operations began to nine years of waste disposal operations (www.cemcr.org). Based on the radiological analyses of monitoring samples completed to date for area residents and site workers, and for selected aerosols, soils, sediments, drinking water and surface waters, there is no evidence of increases in radiological contaminants in the region of WIPP that could be attributed to releases from WIPP. Levels of radiological and non-radiological analytes measured since operations began in 1999 have been within the range of baseline levels measured previously, and are within the ranges measured by other entities at the State and local levels since well before disposal phase operations began in 1999. (authors)

Conca, J.; Kirchner, Th.; Monk, J.; Sage, S. [Carlsbad Environmental Monitoring and Research Center, IEE NMSU, 1400 University Drive, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

166

Receiver Operating Characteristic Analysis for Detecting Explosives-related Threats  

SciTech Connect

The Department of Homeland Security (DHS) and the Transportation Security Administration (TSA) are interested in developing a standardized testing procedure for determining the performance of candidate detection systems. This document outlines a potential method for judging detection system performance as well as determining if combining the information from a legacy system with a new system can signi????????cantly improve performance. In this document, performance corresponds to the Neyman-Pearson criterion applied to the Receiver Operating Characteristic (ROC) curves of the detection systems in question. A simulation was developed to investigate how the amount of data provided by the vendor in the form of the ROC curve e???????¤ects the performance of the combined detection system. Furthermore, the simulation also takes into account the potential e???????¤ects of correlation and how this information can also impact the performance of the combined system.

Mark E. Oxley; Alexander M. Venzin

2012-11-14T23:59:59.000Z

167

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-07-02T23:59:59.000Z

168

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual  

Science Conference Proceedings (OSTI)

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

2000-02-03T23:59:59.000Z

169

Overview of Activities in U.S. Related to Continued Service of Nuclear Power Plant Concrete Structures  

SciTech Connect

Safety-related nuclear power plant concrete structures are described and commentary on continued service assessments of these structures is provided. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status noted. A summary of operating experience related to U.S. nuclear power plant concrete structures is presented. Several candidate areas are identified where additional research would be of benefit to aging management of NPP concrete structures. Finally current ORNL activities related to aging-management of concrete structures are outlined: development of operating experience database, application of structural reliability theory, and compilation of elevated temperature concrete material property data and information.

Naus, Dan J [ORNL

2011-01-01T23:59:59.000Z

170

Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989  

SciTech Connect

Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

Not Available

1990-08-01T23:59:59.000Z

171

Nuclear Physics Related Brochures | U.S. DOE Office of Science (SC)  

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

Nuclear Nuclear Physics Related Brochures and Videos Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources NP Workforce Survey Results .pdf file (258KB) Links Databases Workshop Reports Nuclear Physics Related Brochures and Videos 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 » News & Resources Nuclear Physics Related Brochures and Videos Print Text Size: A A A RSS Feeds FeedbackShare Page Brochures Accelerating Innovation NP Highlights Image Accelerating Innovation (2011) .pdf file (1.2MB): How nuclear physics benefits us all

172

Review of the Sandia Site Office Quality Assurance Assessment of the Manzano Nuclear Operations, January 2013  

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

Review of the Review of the Sandia Site Office Quality Assurance Assessment of the Manzano Nuclear Operations January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background ........................................................................................................................................... 1 4.0 Methodology ......................................................................................................................................... 2

173

Improving Text and Document-Based Operations For Advanced Nuclear Plants  

Science Conference Proceedings (OSTI)

An important industry goal for Advanced Nuclear Plants (ANPs) is to ensure they are equipped with a modern, full scope, integrated Information Management System (IMS). As part of this overall goal, there is a need to identify ANP activities that could readily and greatly benefit from the application of existing and emerging IMS technologies. The objective of this project is to identify and prioritize work in such areas for ANPs based on current plant operations and maintenance (O&M) activities. Activitie...

2000-05-22T23:59:59.000Z

174

EPRI Alpha Monitoring and Control Guidelines for Operating Nuclear Power Stations, Revision 2  

Science Conference Proceedings (OSTI)

In 2006, the Electric Power Research Institute (EPRI) first published the EPRI Alpha Monitoring Guidelines for Operating Nuclear Stations (EPRI report 1013509), to provide standardized guidance for monitoring alpha contamination. Minor revisions were made to the guidelines, which were re-issued in 2009 (1019500). Most US and some international utilities have implemented the guidelines, and several areas of improvement were identified to enhance information to support the monitoring and ...

2013-08-29T23:59:59.000Z

175

Batch Preheat for glass and related furnace processing operations  

SciTech Connect

The objectives that our development work addressed are: (1) Establish through lab tests a salt eutectic with a melting point of about 250 F and a working range of 250 to 1800 F. (2) Establish the most economical material of construction for the screened salt eutectics identified in the first objective. (3) Establish the material of construction for the salt heater liner. Objectives 2 and 3 were determined through corrosion tests using selected metallurgical samples. Successful completion of the above-stated goals will be incorporated in a heat recovery design that can be used in high temperature processes and furnaces, typical of which is the glass melting process. The process design incorporates the following unit operations: a vertical batch heater (whereby the batch flows down through tubes in a shell and tube exchanger; a molten salt eutectic is circulated on the shell side); a molten salt heater utilizing furnace flue gas in a radiation type heater (molten salt is circulated in the annular space between the inner and outer shells of the vertical heater, and flue gas passes from the furnace exhaust through the inner shell of the heater); a cantilever type molten salt circulating pump; and a jacketed mixer/conveyor to drive off moisture from the batch prior to feeding the batch to the vertical batch heater. Historically, radiation heaters, when applied to glass or fiberglass furnace recuperation, have experienced failures due to uneven heat flux rates, which increases internal stresses and spot overheating conditions. Low heat transfer coefficients result in requirements for large heat transfer surface areas in gas to gas or gas to air exchangers. Fouling is another factor that results in lower unit availability and reduced performance. These factors are accommodated in this process by the incorporation of several design features. The salt heater will be a vertical double wall radiation design, similar to radiation air heaters used in high temperature heat recovery. The unit utilizes an inner shell that the furnace exhaust gas passes through: this provides essentially a self-cleaning surface. Utilization of radiation air heaters in fiberglass furnaces has demonstrated that the inner shell provides a surface from which molten ash can drain down. The molten salt eutectic will be pumped through the annulus between this inner wall and the outer wall of the unit. The annular space tempering via the molten salt will promote more uniform expansion for the unit, and thereby promote more uniform heat flux rates. Heat transfer would be via radiation mainly, with a minor convective contributor.

Energy & Environmental Resources, Inc

2002-08-12T23:59:59.000Z

176

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - NNSA Lines of Inquiry, November 24, 2009  

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

1 1 Written Reponse to DNFSB Lines of Inquiry Garrett Harencak, BRIG GEN, USAF Principal Assistant Deputy Administrator for Military Application DNFSB Public Meeting Oversight of Complex, High-Hazard Nuclear Operations 1. Expectations of the senior Department leadership with respect to safety philosophy and safety management approach. LOI 1.1, What are your nuclear safety goals? Secretary of Energy Notice 35-91, Nuclear Safety Policy, established nuclear safety goals for DOE. The goals in this notice have not been updated or revised since its publication. The notice states: DOE has adopted two quantitative safety goals to limit the risks of fatalities associated with its nuclear operations. These goals are the same as those established for nuclear power plants by the Nuclear Regulatory Commission

177

A comparative study of worker and general public risks from nuclear facility operation using MACCS2  

Science Conference Proceedings (OSTI)

Over the last five years, the US Department of Energy (DOE) has attempted to establish quantitative risk indices as minimum acceptance criteria for assurance of safe operation of its nuclear facilities. The risk indices serve as aiming points or targets to include consideration of all aspects of operation including normal conditions as well as abnormal, design basis events, and beyond-design basis events. Although initial focus of the application of these safety targets had been on DOE`s reactors, more recent assessments have also considered non-reactor facilities including those encompassing storage and nuclear processing activities. Regardless of the facility`s primary function, accident progression, event tree/fault tree logic models, and probabilistic (dose) consequence assessment model must be implemented to yield a fully integrated analysis of facility operation. The primary tool for probabilistic consequence assessment in the US is the MELCOR Accident Consequence Code System (MACCS). In this study, two version of MACCS are applied to representative source terms developed in the safety analysis associated with a waste processing facility at the Westinghouse Savannah River Company`s (WSRC`s) Savannah River Site (SRS). The MACCS versions are used to estimate population dose and subsequent health effects to workers and the general public from the SRS referenced facility operation. When combined with the frequency of occurrence evaluation, the margin of compliance with the safety targets may be quantified.

East, J.M.; O`Kula, K.R.

1994-10-01T23:59:59.000Z

178

CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing  

Office of Legacy Management (LM)

tudies/B ackground tudies/B ackground Book 1 CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing Areas Vol. 11, April 1988 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. CERCLA PRELIMINARY ASSESSMENT OF DOE'S NEVADA OPERATIONS OFFICE WCILEAR WEAPONS T E S r n G AREAS Prepared by Water Resources Center Desert Research Institute University of Nevada System ,Prepared for U . S . Department of Energy Nevada Operations Office Las Vegas, Nevada under contract DE-AC08-85NV10384 A p r i l 1988 CONTENTS VOLUME I I. INTRODUCTION 1.1 11. NEVADA TEST SITE TESTING AREAS 2.1 Frenchman Flat (Area 5) 2.1.1 2.2 Yucca Flat (Areas 1, 2, 3, 4, 6, 7, 8, 9, 10, 11, and 15)

179

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01T23:59:59.000Z

180

Reliability quantification of nuclear safety-related software  

E-Print Network (OSTI)

The objective of this study is to improve quality and reliability of safety-critical software in the nuclear industry. It is accomplished by focusing on the following two areas: Formulation of a standard extensive integrated ...

Zhang, Yi, 1973-

2004-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the Presidents Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project.

Edward J. Gorski; Charles V. Park; Finis H. Southworth

2004-06-01T23:59:59.000Z

182

November 24, 2009, Board Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - Transcript  

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

Neal R. Gross & Co., Inc. Neal R. Gross & Co., Inc. 202-234-4433 Page 1 UNITED STATES OF AMERICA + + + + + DEFENSE NUCLEAR FACILITIES SAFETY BOARD + + + + + OVERSIGHT OF COMPLEX, HIGH-HAZARD NUCLEAR OPERATIONS + + + + + TUESDAY NOVEMBER 24, 2009 + + + + + The Board met in the DNFSB Hearing Room at 625 Indiana Avenue, N.W., Suite 700, Washington, DC 20004, at 9:00 a.m., John E. Mansfield, Vice Chairman, presiding. UPRESENTU : JOHN E. MANSFIELD, Ph.D., Vice Chairman JOSEPH F. BADER, Board Member LARRY W. BROWN, Board Member PETER S. WINOKUR, Ph.D., Board Member USTAFF PRESENTU : RICHARD A. AZZARO, General Counsel TIMOTHY J. DWYER, Technical Director BRIAN GROSNER, General Manager RICHARD E. TONTODONATO, Deputy Technical Director Neal R. Gross & Co., Inc.

183

Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications (NCIG-07)  

Science Conference Proceedings (OSTI)

The reduced availability of spare and replacement parts designed specifically for nuclear safety related components has made it necessary for utilities to purchase commercial grade parts. This study, the seventh in a series cosponsored by the Nuclear Construction Issues Group (NCIG), outlines an acceptance procedure for ensuring that commercial grade items conform with requirements for their use in safety related applications.

1988-06-01T23:59:59.000Z

184

Development of a hybrid intelligent system for on-line real-time monitoring of nuclear power plant operations  

E-Print Network (OSTI)

A nuclear power plant (NPP) has an intricate operational domain involving systems, structures and components (SSCs) that vary in scale and complexity. Many of the large scale SSCs contribute to the lost availability in the ...

Yildiz, Bilge, 1976-

2003-01-01T23:59:59.000Z

185

Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1  

SciTech Connect

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

NONE

1995-08-01T23:59:59.000Z

186

Freedom of Information Act Related Sites | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

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...

187

Nuclear criticality safety in D and D operations: a Los Alamos experience  

SciTech Connect

Decommissioning operations at the Los Alamos National Laboratory require the interaction of several disciplines so that the effort to D&D radiological facilities can proceed unencumbered, on schedule, and within budget. Although playing a minor role, the Laboratory`s Nuclear Criticality Safety Group has provided criticality safety guidance to one such D&D team efficiently and cost-effectively. During the first major D&D effort at Los Alamos, a total of about 6 kilograms of uranium [U(93)] was recovered from a facility thought to contain only tens of grams.

Schlesser, J.A.

1996-12-31T23:59:59.000Z

188

Method for operating a steam turbine of the nuclear type with electronic reheat control of a cycle steam reheater  

SciTech Connect

An electronic system is provided for operating a nuclear electric power plant with electronic steam reheating control applied to the nuclear turbine system in response to low pressure turbine temperatures, and the control is adapted to operate in a plurality of different automatic control modes to control reheating steam flow and other steam conditions. Each of the modes of control permit turbine temperature variations within predetermined constraints and according to predetermined functions of time. (Official Gazette)

Luongo, M.C.

1975-08-12T23:59:59.000Z

189

OPERATING EXPERIENCE WITH THE SODIUM REACTOR EXPERIMENT AND ITS APPLICATION TO THE HALLAM NUCLEAR POWER FACILITY  

SciTech Connect

The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled graphitemoderated reactors for central station power. The operating experience of SRE has provided valuable data for the design of the Hallam Nuclear Power Facillty (HNPF) now under construction. Some of the difficulties found in the SRE, which HNPF will be designed to avoid, are the sodium-sodium intermediate heat exchanger (horizontal position in SRE gave trouble; a vertical position will be used in HNPF), sodium pumps, handling of broken fuel elements, and excessive thermal stresses due to inadequate coolant flow. Other features of HNPF include the addition of an activity monitoring system for the core cover gas, elimination of tetralin for auxiliary cooling of plant equipment, instrumentation of fuel elements, and addition of carbon traps in the primary sodium system. SRE operation has demonstrated unusual reactor stability and capability for rapid power changes. (D.L.C.)

Beeley, R.J.; Mahlmeister, J.E.

1960-01-01T23:59:59.000Z

190

Aging of turbine drives for safety-related pumps in nuclear power plants  

SciTech Connect

This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented.

Cox, D.F. [Oak Ridge National Lab., TN (United States)

1995-06-01T23:59:59.000Z

191

Evaluation of Next Generation Nuclear Power Plant (NGNP) Intermediate Heat Exchanger (IHX) Operating Conditions  

DOE Green Energy (OSTI)

This report summarizes results of a preliminary evaluation to determine the operating conditions for the Next Generation Nuclear Plant (NGNP) Intermediate Heat Exchanger (IHX) that will transfer heat from the reactor primary system to the demonstration hydrogen production plant(s). The Department of Energy is currently investigating two primary options for the production of hydrogen using a high temperature reactor as the power source. These options are the High Temperature Electrolysis (HTE) and Sulfur-Iodine (SI) thermochemical hydrogen production processes. However, since the SI process relies entirely on process heat from the reactor, while the HTE process relies primarily on electrical energy with only a small amount of process heat required, the design of the IHX is dictated by the SI process heat requirements. Therefore, the IHX operating conditions were defined assuming 50 MWt is available for the production of hydrogen using the SI process. Three configurations for the intermediate loop were evaluated, including configurations for both direct and indirect power conversion systems. The HYSYS process analysis software was used to perform sensitivity studies to determine the influence of reactor outlet temperatures, intermediate loop working fluids (helium and molten salt), intermediate loop pressures, and intermediate loop piping lengths on NGNP performance and IHX operating conditions. The evaluation of NGNP performance included assessments of overall electric power conversion efficiency and estimated hydrogen production efficiency. Based on these evaluations, recommended IHX operating conditions are defined.

E. A. Harvego

2006-04-01T23:59:59.000Z

192

On energy exchange rate and entropy production operators in quantum fluctuation-dissipation relations  

E-Print Network (OSTI)

For quantum systems with externally time-varied Hamiltonians a definition of operators of system's energy change rate (work per unit time) and entropy production observables is suggested and discussed in the context of rigorous statistical equalities (generalized fluctuation-dissipation relations) under the Jordan-symmetrized chronological operator ordering rule.

Yu. E. Kuzovlev

2013-05-15T23:59:59.000Z

193

Review of nuclear power plant offsite power source reliability and related recommended changes to the NRC rules and regulations  

SciTech Connect

The NRC has stated its concern about the reliability of the offsite power system as the preferred emergency source and about the possible damage to a pressurized water reactor (PWR) that could result from a rapid decay of power grid frequency. ORNL contracted with NRC to provide technical assistance to establish criteria that can be used to evaluate the offsite power system for the licensing of a nuclear power plant. The results of many of the studies for this contract are recommendations to assess and control the power grid during operation. This is because most of the NRC regulations pertaining to the offsite power system are related to the design of the power grid, and we believe that additional emphasis on monitoring the power grid operation will improve the reliability of the nuclear plant offsite power supply. 46 refs., 10 figs.

Battle, R.E.; Clark, F.H.; Reddoch, T.W.

1980-05-01T23:59:59.000Z

194

An Extended Procedure for Implementing the Relative Operating Characteristic Graphical Method  

Science Conference Proceedings (OSTI)

The functional relationship between the relative operating characteristic (ROC) and the economic value (EV) graphical methods have been exploited to develop a hybrid procedure called the extended ROC (EROC) method. The EROC retains the appealing ...

Fredrick H. M. Semazzi; Roberto J. Mera

2006-09-01T23:59:59.000Z

195

DEVELOPMENT, INSTALLATION AND OPERATION OF THE MPC&A OPERATIONS MONITORING (MOM) SYSTEM AT THE JOINT INSTITUTE FOR NUCLEAR RESEARCH (JINR) DUBNA, RUSSIA  

Science Conference Proceedings (OSTI)

The Material Protection, Control and Accounting (MPC&A) Operations Monitoring (MOM) systems handling at the International Intergovernmental Organization - Joint Institute for Nuclear Research (JINR) is described in this paper. Category I nuclear material (plutonium and uranium) is used in JINR research reactors, facilities and for scientific and research activities. A monitoring system (MOM) was installed at JINR in April 2003. The system design was based on a vulnerability analysis, which took into account the specifics of the Institute. The design and installation of the MOM system was a collaborative effort between JINR, Brookhaven National Laboratory (BNL) and the U.S. Department of Energy (DOE). Financial support was provided by DOE through BNL. The installed MOM system provides facility management with additional assurance that operations involving nuclear material (NM) are correctly followed by the facility personnel. The MOM system also provides additional confidence that the MPC&A systems continue to perform effectively.

Kartashov,V.V.; Pratt,W.; Romanov, Y.A.; Samoilov, V.N.; Shestakov, B.A.; Duncan, C.; Brownell, L.; Carbonaro, J.; White, R.M.; Coffing, J.A.

2009-07-12T23:59:59.000Z

196

Department of Energy Issues Requests for Applications for Nuclear-Related  

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

Requests for Applications for Requests for Applications for Nuclear-Related Science and Engineering Scholarships and Fellowships Department of Energy Issues Requests for Applications for Nuclear-Related Science and Engineering Scholarships and Fellowships March 12, 2010 - 12:00am Addthis Washington, D.C. - The Department of Energy today issued two Request for Applications (RFA) for scholarships and fellowships as part of its efforts to recruit and train the next generation of nuclear scientists and engineers. The Department's Nuclear Energy University Programs (NEUP) will provide approximately $5 million for scholarships and fellowships for students enrolled in two-year, four-year and graduate engineering and science programs related to nuclear energy at accredited U.S. universities

197

Department of Energy Issues Requests for Applications for Nuclear-Related  

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

Issues Requests for Applications for Issues Requests for Applications for Nuclear-Related Science and Engineering Scholarships and Fellowships Department of Energy Issues Requests for Applications for Nuclear-Related Science and Engineering Scholarships and Fellowships March 12, 2010 - 12:37pm Addthis Washington, D.C. - The Department of Energy today issued two Request for Applications (RFA) for scholarships and fellowships as part of its efforts to recruit and train the next generation of nuclear scientists and engineers. The Department's Nuclear Energy University Programs (NEUP) will provide approximately $5 million for scholarships and fellowships for students enrolled in two-year, four-year and graduate engineering and science programs related to nuclear energy at accredited U.S. universities

198

ENTERPRISE SRS: LEVERAGING ONGOING OPERATIONS TO ADVANCE NUCLEAR FUEL CYCLES RESEARCH AND DEVELOPMENT PROGRAMS  

SciTech Connect

The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ?all things nuclear? as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scaletechnology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS assets will continue to accomplish DOE?s critical nuclear material missions (e.g., processing in H-Canyon and plutonium storage in K-Area). Thus, the demonstration can be accomplished by leveraging the incremental cost of performing demonstrations without needing to cover the full operational cost of the facility. Current Center activities have been focused on integrating advanced safeguards monitoring technologies demonstrations into the SRS H-Canyon and advanced location technologies demonstrations into K-Area Materials Storage. These demonstrations are providing valuable information to researchers and customers as well as providing the Center with an improved protocol for demonstration management that can be exercised across the entire SRS (as well as to offsite venues) so that future demonstrations can be done more efficiently and provide an opportunity to utilize these unique assets for multiple purposes involving national laboratories, academia, and commercial entities. Key among the envisioned future demonstrations is the use of H-Canyon to demonstrate new nuclear materials separations technologies critical for advancing the mission needs DOE-Nuclear Energy (DOE-NE) to advance the research for next generation fuel cycle technologies. The concept is to install processing equipment on frames. The frames are then positioned into an H-Canyon cell and testing in a relevant radiological environment involving prototypic radioactive materials can be performed.

Murray, A.; Marra, J.; Wilmarth, B.; Mcguire, P.; Wheeler, V.

2013-07-03T23:59:59.000Z

199

Initial assessment of the operability of the VHTR-HTSE nuclear hydrogen plant.  

DOE Green Energy (OSTI)

The generation of hydrogen from nuclear power will need to compete on three fronts: production, operability, and safety to be viable in the energy marketplace of the future. This work addresses the operability of a coupled nuclear and hydrogen-generating plant while referring to other work for progress on production and safety. Operability is a measure of how well a plant can meet time-varying production demands while remaining within equipment limits. It can be characterized in terms of the physical processes that underlie operation of the plant. In this work these include the storage and transport of energy within components as represented by time constants and energy capacitances, the relationship of reactivity to temperature, and the coordination of heat generation and work production for a near-ideal gas working fluid. Criteria for assessing operability are developed and applied to the Very High Temperature Reactor coupled to the High Temperature Steam Electrolysis process, one of two DOE/INL reference plant concepts for hydrogen production. Results of preliminary plant control and stability studies are described. A combination of inventory control in the VHTR plant and flow control in the HTSE plant proved effective for maintaining hot-side temperatures near constant during quasi-static change in hydrogen production rate. Near constant electrolyzer outlet temperature is achieved by varying electrolyzer cell area to control cell joule heating. It was found that rates of temperature change in the HTSE plant for a step change in hydrogen production rate are largely determined by the thermal characteristics of the electrolyzer. It's comparatively large thermal mass and the presence of recuperative heat exchangers result in a tight thermal coupling of HTSE components to the electrolyzer. It was found that thermal transients arising in the chemical plant are strongly damped at the reactor resulting in a stable combined plant. The large Doppler reactivity component, three times greater than next reactivity component, per unit temperature, is mainly responsible. This is the case even when one of the conditions for out-of-phase oscillations between reactor inlet and outlet temperature, a large time for transport of process heat between the reactor and chemical plant, exists.

Vilim, R. B.; Nuclear Engineering Division

2007-11-01T23:59:59.000Z

200

Nuclear skill related training and job identification and placement service for migrant and seasonal farm workers  

Science Conference Proceedings (OSTI)

The success rate of the NSRT Program - based on placement in unsubsidized employment - was 90%. Most of the participants who did not graduate from the NSRT Program were transferred to other less technical programs, such as TAT, REECO, and the EAST/SLAC programs, and obtained skills that made them employable elsewhere. The follow-up process at the Center for Nuclear Studies continues. Officials here can list place of employment, technical rating, and salary of all of the 90 graduates. Several are now full-fledged nuclear reactor operators licensed by the Nuclear Regulatory Commission.

Not Available

1980-01-01T23:59:59.000Z

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


201

Measurement of Lake Roosevelt Biota in Relation to Reservoir Operations; 1991 Annual Report.  

DOE Green Energy (OSTI)

The purpose of this study was to collect biological data from Lake Roosevelt to be used in the design of a computer model that would predict biological responses to reservoir operations as part of the System Operation Review program. Major components of the Lake Roosevelt model included: quantification of impacts to phytoplankton, zooplanktons, benthic invertebrates, and fish caused by reservoir drawdowns and low water retention times; quantification of number, distribution, and use of fish food organisms in the reservoir by season; determination of seasonal growth of fish species as related to reservoir operations, prey abundance and utilization; and quantification of entrainment levels of zooplankton and fish as related to reservoir operations and water retention times. This report summarized the data collected on Lake Roosevelt for 1991 and includes limnological, zooplankton, benthic macroinvertebrate, fishery, and reservoir operation data. Discussions cover reservoir operation affect upon zooplankton, benthic macroinvertebrates, and fish. Reservoir operations brought reservoir elevations to a low of 1,221.7 in April, the result of power operations and a flood control shift from Dworshak Dam, in Idaho, to Grand Coulee Dam. Water retention times were correspondingly low reaching a minimum of 14.7 days on April 27th.

Griffith, Janelle R.; McDowell, Amy C.; Scholz, Allan T.

1995-08-01T23:59:59.000Z

202

Design and Operation of Equipment to Detect and Remove Water within Used Nuclear Fuel Storage Bottles  

SciTech Connect

Inspection and drying equipment has been implemented in a hot cell to address the inadvertent ingress of water into used nuclear fuel storage bottles. Operated with telemanipulators, the system holds up to two fuel bottles and allows their threaded openings to be connected to pressure transducers and a vacuum pump. A prescribed pressure rebound test is used to diagnose the presence of moisture. Bottles found to contain moisture are dried by vaporization. The drying process is accelerated by the application of heat and vacuum. These techniques detect and remove virtually all free water (even water contained in a debris bed) while leaving behind most, if not all, particulates. The extracted water vapour passes through a thermoelectric cooler where it is condensed back to the liquid phase for collection. Fuel bottles are verified to be dry by passing the pressure rebound test.

C.C. Baker; T.M. Pfeiffer; J.C. Price

2013-09-01T23:59:59.000Z

203

History of remote operations and robotics in nuclear facilities. Robotics and Intelligent Systems Program  

SciTech Connect

The field of remote technology is continuing to evolve to support man`s efforts to perform tasks in hostile environments. Remote technology has roots which reach into the early history of man. Fireplace pokers, blacksmith`s tongs, and periscopes are examples of the beginnings of remote technology. The technology which we recognize today has evolved over the last 45-plus years to support human operations in hostile environments such as nuclear fission and fusion, space, underwater, hazardous chemical, and hazardous manufacturing. The four major categories of approach to remote technology have been (1) protective clothing and equipment for direct human entry, (2) extended reach tools using distance for safety, (3) telemanipulators with barriers for safety, and (4) teleoperators incorporating mobility with distance and/or barriers for safety. The government and commercial nuclear industry has driven the development of the majority of the actual teleoperator hardware available today. This hardware has been developed due to the unsatisfactory performance of the protective-clothing approach in many hostile applications. Systems which have been developed include crane/impact wrench systems, unilateral power manipulators, mechanical master/slaves, and servomanipulators. Work for space applications has been primarily research oriented with few successful space applications, although the shuttle`s remote manipulator system has been successful. In the last decade, underwater applications have moved forward significantly, with the offshore oil industry and military applications providing the primary impetus. This document consists of viewgraphs and subtitled figures.

Herndon, J.N.

1992-05-01T23:59:59.000Z

204

Measurement of Lake Roosevelt Biota in Relation to Reservoir Operations Appendices; 1991 Annual Report.  

DOE Green Energy (OSTI)

This report consists of appendices A-F containing the biological data which were collected from Lake Roosevelt, Washington. The data are to be used in the design of a computer model that would predict biological responses of reservoir operations as part of the System Operation Review program. Major components of the model included: Quantification of impacts to phytoplankton, zooplanktons, benthic invertebrates, and fish caused by reservoir drawdowns and low water retention times; quantification of number, distribution, and use of fish food organisms in the reservoir by season; determination of seasonal growth of fish species as related to reservoir operations, prey abundance and utilization; and quantification of entrainment levels of zooplankton and fish as related to reservoir operations and water retention times.

Griffith, Janelle R.; McDowell, Amy C.; Scholz, Allan T.

1995-08-01T23:59:59.000Z

205

for Renewal of Operating Licenses for Nuclear Power Plants. " The staff determined that the  

E-Print Network (OSTI)

LRA was complete and acceptable for docketing on May 15, 2009 (74 FR 22978). The staff has reviewed the PVNGS LRA, conducted site audits, issued requests for additional information (RAls), reviewed the applicant's responses to the staffs RAls, developed its "Safety Evaluation Report with Open Item Related to the License Renewal of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 " (SER with Open Item), and reviewed the applicant's comments on the SER with Open Item. The SER with Open Item was discussed at an Advisory Committee on Reactor Safeguards (ACRS) subcommittee meeting on September 8,2010. The staff has closed the open item discussed in the SER with Open Item. Section 1.5 of the attached "Safety Evaluation Report Related to the License Renewal of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 " (SER), provides a summary of the open item including actions to close the item. On the basis of this review, the staff has developed the enclosed SER to document its findings associated with the safety review of the LRA and supporting documentation. This SER is scheduled to be discussed at the ACRS full committee meeting on

United States; Mr. Randall; K. Edington

2011-01-01T23:59:59.000Z

206

Live Operation Data Collection Optimization and Communication for the Domestic Nuclear Detection Offices Rail Test Center  

Science Conference Proceedings (OSTI)

For the Domestic Nuclear Detection Offices Rail Test Center (i.e., DNDOs RTC), port operation knowledge with flexible collection tools and technique are essential in both technology testing design and implementation intended for live operational settings. Increased contextual data, flexibility in procedures, and rapid availability of information are keys to addressing the challenges of optimization, validation, and analysis within live operational setting data collection. These concepts need to be integrated into technology testing designs, data collection, validation, and analysis processes. A modified data collection technique with a two phased live operation test method is proposed.

Gelston, Gariann M.

2010-04-06T23:59:59.000Z

207

Nuclear Transmutations in HFIR's Beryllium Reflector and Their Impact on Reactor Operation and Reflector Disposal  

SciTech Connect

The High Flux Isotope Reactor located at the Oak Ridge National Laboratory utilizes a large cylindrical beryllium reflector that is subdivided into three concentric regions and encompasses the compact reactor core. Nuclear transmutations caused by neutron activation occur in the beryllium reflector regions, which leads to unwanted neutron absorbing and radiation emitting isotopes. During the past year, two topics related to the HFIR beryllium reflector were reviewed. The first topic included studying the neutron poison (helium-3 and lithium-6) buildup in the reflector regions and its affect on beginning-of-cycle reactivity. A new methodology was developed to predict the reactivity impact and estimated symmetrical critical control element positions as a function of outage time between cycles due to helium-3 buildup and was shown to be in better agreement with actual symmetrical critical control element position data than the current methodology. The second topic included studying the composition of the beryllium reflector regions at discharge as well as during decay to assess the viability of transporting, storing, and ultimately disposing the reflector regions currently stored in the spent fuel pool. The post-irradiation curie inventories were used to determine whether the reflector regions are discharged as transuranic waste or become transuranic waste during the decay period for disposal purposes and to determine the nuclear hazard category, which may affect the controls invoked for transportation and temporary storage. Two of the reflector regions were determined to be transuranic waste at discharge and the other region was determined to become transuranic waste in less than 2 years after being discharged due to the initial uranium content (0.0044 weight percent uranium). It was also concluded that all three of the reflector regions could be classified as nuclear hazard category 3 (potential for localized consequences only).

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL; Proctor, Larry Duane [ORNL

2012-01-01T23:59:59.000Z

208

The Emergence of Weather-Related Testbeds Linking Research and Forecasting Operations  

Science Conference Proceedings (OSTI)

Testbeds have emerged as a critical mechanism linking weather research with forecasting operations. The U.S. Weather Research Program (USWRP) was formed in the 1990s to help identify key gaps in research related to major weather prediction problems and ...

F. Martin Ralph; Janet Intrieri; David Andra; Jr.; Robert Atlas; Sid Boukabara; David Bright; Paula Davidson; Bruce Entwistle; John Gaynor; Steve Goodman; Jiann-Gwo Jiing; Amy Harless; Jin Huang; Gary Jedlovec; John Kain; Steven Koch; Bill Kuo; Jason Levit; Shirley Murillo; Lars Peter Riishojgaard; Timothy Schneider; Russell Schneider; Travis Smith; Steven Weiss

209

The Emergence of Weather-Related Test Beds Linking Research and Forecasting Operations  

Science Conference Proceedings (OSTI)

Test beds have emerged as a critical mechanism linking weather research with forecasting operations. The U.S. Weather Research Program (USWRP) was formed in the 1990s to help identify key gaps in research related to major weather prediction problems and ...

F. Martin Ralph; Janet Intrieri; David Andra Jr.; Robert Atlas; Sid Boukabara; David Bright; Paula Davidson; Bruce Entwistle; John Gaynor; Steve Goodman; Jiann-Gwo Jiing; Amy Harless; Jin Huang; Gary Jedlovec; John Kain; Steven Koch; Bill Kuo; Jason Levit; Shirley Murillo; Lars Peter Riishojgaard; Timothy Schneider; Russell Schneider; Travis Smith; Steven Weiss

2013-08-01T23:59:59.000Z

210

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999  

SciTech Connect

This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2000-02-01T23:59:59.000Z

211

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998  

Science Conference Proceedings (OSTI)

This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the major Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.

NONE

1999-02-01T23:59:59.000Z

212

On selection and operation of an international interim storage facility for spent nuclear fuel  

E-Print Network (OSTI)

Disposal of post-irradiation fuel from nuclear reactors has been an issue for the nuclear industry for many years. Most countries currently have no long-term disposal strategy in place. Therefore, the concept of an ...

Burns, Joe, 1966-

2004-01-01T23:59:59.000Z

213

Results of the first year of operation at Embalse Nuclear Power Station in Argentina  

SciTech Connect

As a part of the International Remote Monitoring Project, during March 1995, a Remote Monitoring System (RMS) was installed at the Embalse Nuclear Power Station in Embalse, Argentina. This system monitors the status of four typical Candu spent fuel dry storage silos. The monitoring equipment for each silo consists of analog sensors for temperature and gamma radiation measurement; digital sensors for motion detection; and electronic fiber-optic seals. The monitoring system for each silo is connected to a wireless Authenticate Item Monitoring System (AIMS). This paper describes the operation of the RMS during the first year of the trial and presents the results of the signals reported by the system compared with the on site inspections conducted by the regulatory bodies, ABACC, IAEA, ENREN. As an additional security feature, each sensor periodically transmits authenticated State-of-Health (SOH) messages. This feature provides assurance that all sensors are operational and have not been tampered with. The details of the transmitted information and the incidents of loss of SOH, referred to as Missing SOH Event, and the possible causes which produced the MSOHE are described. The RMS at the embalse facility uses gamma radiation detectors in a strong radiation field of spent fuel dry storage silos. The detectors are Geiger Muller tubes and Silicon solid state diodes. The study of the thermal drift of electronics in GM detectors and the possible radiation damage in silicon detectors is shown. Since the initial installation, the system has been successfully interrogated from Buenos Aires and Albuquerque. The experience gained, and the small changes made in the hardware in order to improve the performance of the system is presented.

Bonino, A.; Pizarro, L.; Higa, Z. [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina); Dupree, S.A.; Schoeneman, J.L. [Sandia National Labs., Albuquerque, NM (United States)

1996-07-16T23:59:59.000Z

214

Nuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology for energy, environment, and health. NRG offers a wide range of services to energy  

E-Print Network (OSTI)

Nuclear Research & Consultancy Group (NRG) develops and provides sustainable nuclear technology organizations and various branches of industry - including the nuclear, financial services and medical sectors configurations will contribute to an improved design, safety, and operation of nuclear reactors. In relation

Lindken, Ralph

215

Measurement of Lake Roosevelt Biota in Relation to Reservoir Operations; 1992 Annual Report.  

DOE Green Energy (OSTI)

The purpose of this research project is to collect data to model resident fish requirements for Lake Roosevelt as part of the Bonneville Power Administration (BPA), Bureau of Reclamation (BoR), and U.S. Army Corps of Engineer`s (ACE) System Operation Review. The System Operation Review (SOR) is a tri-agency team functioning to review the use and partitioning of Columbia Basin waters. User groups of the Columbia have been defined as power, irrigation, flood control, anadromous fish, resident fish, wildlife, recreation, water quality, navigation, and cultural resources. Once completed the model will predict biological responses to different reservoir operation strategies. The model being developed for resident fish is based on Montana Department of Fish, Wildlife, and Parks model for resident fish requirements within Hungry Horse and Libby Reservoirs. While the Montana model predicts fish growth based on the impacts of reservoir operation and flow conditions on primary and secondary production levels, the Lake Roosevelt model will also factor in the affects of water retention time on zooplankton production levels and fish entrainment. Major components of the Lake Roosevelt model include: (1) quantification of impacts to zooplankton, benthic invertebrates, and fish caused by reservoir drawdowns and low water retention times; (2) quantification of number, distribution, and use of fish food organisms in the reservoir by season; (3) determination of seasonal growth of fish species as related to reservoir operations, prey abundance and utilization; and (4) quantification of entrainment levels of fish as related to reservoir operations and water retention times. This report contains the results of the resident fish system operation review program for Lake Roosevelt from January through December 1992.

Griffith, Janelle R.; McDowell, Amy C.

1996-01-01T23:59:59.000Z

216

A survey of nuclear-related agreements and possibilities for nuclear cooperation in South Asia: Cooperative Monitoring Center Occasional Paper/15  

SciTech Connect

Several existing nuclear-related agreements already require India and Pakistan, as members, to share information. The agreements are bilateral, regional, and international. Greater nuclear transparency between India and Pakistan could be promoted by first understanding the information flows required by existing agreements. This understanding is an essential step for developing projects that can incrementally advance the sensitivity of the information being shared. This paper provides a survey of existing nuclear-related agreements involving India and Pakistan, and suggests future confidence-building projects using the frameworks provided by these agreements. The Bilateral Agreement on the Prohibition of Attack against Nuclear Reactors and Nuclear Facilities is discussed as a basis for creating further agreements on restricting the use and deployment of nuclear weapons. The author suggests options for enhancing the value of the list of nuclear facilities exchanged annually as a part of this agreement. The International Atomic Energy Agency's regional cooperation agreement among countries in the Asia-Pacific region is an opportunity for greater subregional nuclear cooperation in South Asia. Linking the regional agreement with South Asian environmental cooperation and marine pollution protection efforts could provide a framework for projects involving Indian and Pakistani coastal nuclear facilities. Programs of the Food and Agriculture Organization of the United Nations that use nuclear techniques to increase food and crop production and optimize water management in arid areas also provide similar opportunities for nuclear cooperation. Other frameworks for nuclear cooperation originate from international conventions related to nuclear safety, transportation of nuclear wastes, worker protection against ionizing radiation, and the nondeployment of nuclear weapons in certain areas. The information shared by existing frameworks includes: laws and regulations (including internal inspection procedures that enforce compliance); lists of nuclear facilities; emergency response procedures and available resources; information related to the transportation of nuclear wastes (particularly via shipping); understanding and notification of accidental releases; and radionuclide release data from select coastal facilities. Incremental increases in the sensitivity of the information being shared could strengthen norms for Indian and Pakistani nuclear transparency. This paper suggests seven technology-based Indian and Pakistani nuclear transparency projects for consideration. Existing nuclear-related agreements provide an information-sharing framework within which the projects could occur. Eventually, as confidence increases and new agreements are negotiated, future projects could begin to deal with the accounting of fissile materials and nuclear weapons disposition and control.

RAJEN,GAURAV

2000-04-01T23:59:59.000Z

217

Thermal Operator and Dispersion Relation in QED at Finite Temperature and Chemical Potential  

E-Print Network (OSTI)

Combining the thermal operator representation with the dispersion relation in QED at finite temperature and chemical potential, we determine the complete retarded photon self-energy only from its absorptive part at zero temperature. As an application of this method, we show that, even for the case of a nonzero chemical potential, the temperature dependent part of the one loop retarded photon self-energy vanishes in $(1+1)$ dimensional massless QED.

Ashok Das; J. Frenkel

2007-05-17T23:59:59.000Z

218

Case studies of energy information systems and related technology: Operational practices, costs, and benefits  

SciTech Connect

Energy Information Systems (EIS), which can monitor and analyze building energy consumption and related data throughout the Internet, have been increasing in use over the last decade. Though EIS developers describe the capabilities, costs, and benefits of EIS, many of these descriptions are idealized and often insufficient for potential users to evaluate cost, benefit and operational usefulness. LBNL has conducted a series of case studies of existing EIS and related technology installations. This study explored the following questions: (1) How is the EIS used in day-to-day operation? (2) What are the costs and benefits of an EIS? (3) Where do the energy savings come from? This paper reviews the process of these technologies from installation through energy management practice. The study is based on interviews with operators and energy managers who use EIS. Analysis of energy data trended by EIS and utility bills was also conducted to measure the benefit. This paper explores common uses and findings to identify energy savings attributable to EIS, and discusses non-energy benefits as well. This paper also addresses technologies related to EIS that have been demonstrated and evaluated by LBNL.

Motegi, Naoya; Piette, Mary Ann; Kinney, Satkartar; Dewey, Jim

2003-09-02T23:59:59.000Z

219

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

and Diablo Canyon 2 nuclear reactors. Data were taken fromCapacity Operation of nuclear reactors for power generationby the operation of nuclear reactors. Therefore, ap-

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

220

High fidelity gate operations within the coupled nuclear and electron spins of a nitrogen vacancy center in diamond  

E-Print Network (OSTI)

In this article we investigate the dynamics of a single negatively charged nitrogen-vacancy center (NV-) coupled to the spin of the nucleus of a 15-nitrogen atom and show that high fidelity gate operations are possible without the need for complicated composite pulse sequences. These operations include both the electron and nuclear spin rotations, as well as an entangling gate between them. These are experimentally realizable gates with current technology of sufficiently high fidelities that they can be used to build graph states for quantum information processing tasks.

Mark S. Everitt; Simon Devitt; W. J. Munro; Kae Nemoto

2013-09-12T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Human Factors Engineering Training Course for Utilities Involved in New Nuclear Power Plant Designs, Construction, and Operation  

Science Conference Proceedings (OSTI)

This report provides training materials for a three-day course in human factors engineering (HFE). The course was developed for utility personnel involved in new nuclear power plant (NPP) design and is also useful for vendors and other stakeholders. The primary focus of the HFE training is the main control room and its human-system interfaces (HSIs). However, it also addresses other operator work locations such as the remote shutdown station, local control stations, and emergency response facilities. In ...

2011-12-23T23:59:59.000Z

222

Hydrogen Gas Production from Nuclear Power Plant in Relation to Hydrogen Fuel Cell Technologies Nowadays  

Science Conference Proceedings (OSTI)

Recently, world has been confused by issues of energy resourcing, including fossil fuel use, global warming, and sustainable energy generation. Hydrogen may become the choice for future fuel of combustion engine. Hydrogen is an environmentally clean source of energy to end-users, particularly in transportation applications because without release of pollutants at the point of end use. Hydrogen may be produced from water using the process of electrolysis. One of the GEN-IV reactors nuclear projects (HTGRs, HTR, VHTR) is also can produce hydrogen from the process. In the present study, hydrogen gas production from nuclear power plant is reviewed in relation to commercialization of hydrogen fuel cell technologies nowadays.

Yusibani, Elin [Research Center for Hydrogen Industrial Use and Storage, AIST (Japan); Department of Physics, Universitas Syiah Kuala (Indonesia); Kamil, Insan; Suud, Zaki [Department of Physics, Institut Teknologi Bandung (Indonesia)

2010-06-22T23:59:59.000Z

223

Requirements for Computer Based-Procedures for Nuclear Power Plant Field Operators Results from a Qualitative Study  

SciTech Connect

Although computer-based procedures (CBPs) have been investigated as a way to enhance operator performance on procedural tasks in the nuclear industry for almost thirty years, they are not currently widely deployed at United States utilities. One of the barriers to the wide scale deployment of CBPs is the lack of operational experience with CBPs that could serve as a sound basis for justifying the use of CBPs for nuclear utilities. Utilities are hesitant to adopt CBPs because of concern over potential costs of implementation, and concern over regulatory approval. Regulators require a sound technical basis for the use of any procedure at the utilities; without operating experience to support the use CBPs, it is difficult to establish such a technical basis. In an effort to begin the process of developing a technical basis for CBPs, researchers at Idaho National Laboratory are partnering with industry to explore CBPs with the objective of defining requirements for CBPs and developing an industry-wide vision and path forward for the use of CBPs. This paper describes the results from a qualitative study aimed at defining requirements for CBPs to be used by field operators and maintenance technicians.

Katya Le Blanc; Johanna Oxstrand

2012-05-01T23:59:59.000Z

224

National Nuclear Data Center Nuclear Data Portal www.nndc.bnl.gov  

E-Print Network (OSTI)

National Nuclear Data Center #12;Nuclear Data Portal www.nndc.bnl.gov Nuclear Data Portal New generation of nuclear data services, using modern and powerful DELL servers, Sybase relational database software, Linux operating system, and Java programming language. The Portal includes nuclear structure

Homes, Christopher C.

225

Classification of Invariant Differential Operators for Non-Compact Lie Algebras via Parabolic Relations  

E-Print Network (OSTI)

In the present paper we review the progress of the project of classification and construction of invariant differential operators for non-compact semisimple Lie groups. Our starting points is the class of algebras, which we called earlier 'conformal Lie algebras' (CLA), which have very similar properties to the conformal algebras of Minkowski space-time, though our aim is to go beyond this class in a natural way. For this we introduced recently the new notion of {\\it parabolic relation} between two non-compact semisimple Lie algebras $\\cal G$ and $\\cal G'$ that have the same complexification and possess maximal parabolic subalgebras with the same complexification. Thus, we consider the exceptional algebra $E_{7(7)}$ which is parabolically related to the CLA $E_{7(-25)}$. Other interesting examples are the orthogonal algebras $so(p,q)$ all of which are parabolically related to the conformal algebra $so(n,2)$ with $p+q=n+2$, the parabolic subalgebras including the Lorentz subalgebra $so(n-1,1)$ and its analogs $so(p-1,q-1)$. Further we consider the algebras $sl(2n,R)$ and for $n=2k$ the algebras $su^*(4k)$ which are parabolically related to the CLA $su(n,n)$. Further we consider the algebras $sp(r,r)$ which are parabolically related to the CLA $sp(2r,R)$. We consider also $E_{6(6)}$ and $E_{6(2)}$ which are parabolically related to the hermitian symmetric case $E_{6(-14)}$.

V. K. Dobrev

2013-11-29T23:59:59.000Z

226

Advanced Nuclear Technology: Regulatory Performance Requirements for Safety-Related Instrumentation, Revision 1  

Science Conference Proceedings (OSTI)

This report proposes an acceptable methodology to apply to safety-related instrumentation to demonstrate 95% probability and 95% confidence (95/95) uncertainties in support of the requirements of Nuclear Regulatory Commission Regulatory Guide (RG) 1.105 Revision 3. This methodology should serve as a means to specify testing and analysis requirements to instrumentation manufacturers and suppliers for their use in meeting the RG 1.105 Revision 3 95% probability and 95% confidence requirements. A ...

2013-08-07T23:59:59.000Z

227

Executive Director for Operations CONSIDERATION OF ECONOMIC CONSEQUENCES WITHIN THE U.S. NUCLEAR REGULATORY COMMISSIONS REGULATORY FRAMEWORK  

E-Print Network (OSTI)

The purpose of this Commission paper (SECY) is to provide the Commission with information and options to address to what extent, if any, the U.S. Nuclear Regulatory Commissions (NRCs) regulatory framework should be modified regarding its consideration of the economic consequences of an unintended release of licensed nuclear materials to the environment. SUMMARY: The accident at the Fukushima Dai-ichi nuclear power plant in Japan initiated discussion of how the NRCs regulatory framework considers offsite property damage and other economic consequences caused by a significant radiological release from an NRC-licensed facility and licensed material. In response to this discussion, on April 6, 2012, the Office of the Executive Director for Operations (OEDO) directed the staff (see Enclosure 1, Tasking for RES) to provide a notation vote paper to the Commission on how the NRCs regulatory framework currently considers the economic consequences associated with the unintended 1 release of licensed nuclear material to the environment and alternatives for Commission consideration. CONTACT:

R. W. Borchardt; Alysia Bone Res/dra

2012-01-01T23:59:59.000Z

228

May 21, 2004, Board letter forwarding Recommendation 2004-1, Oversight of Complex, High-Hazard Nuclear Operations  

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

John I Conway, Chdmnm A J Fggenberger, Vice C h u m a n John F Mmsfield R Bruce lMalrhews 625 Indmna Avenue, NW, Suite 700, Washmgton, D C 20004-290 1 (202) 694-7000 May 2 1,2004 The Honorable Spencer Abraham Secretary of Energy 1000 Independence Avenue, SW Washington, DC 20585- 1000 Dear Secretary Abraham: On May 2 1 , 2004, the Defense Nuclear Facilities Safety Board (Board), in accordance with 42 U.S.C. 8 2286d(a), unanimously approved Recommendation 2004-1, which is enclosed for your consideration. Recommendation 2004- 1 deals with Oversight of Complex, High-Hazard Nuclear Operations. After your receipt of this recommendation and as required by 42 U.S.C. 0 2286d(a), the Board will promptly make it available to the public. The Board believes that the

229

Relative Economic Incentives for Hydrogen from Nuclear, Renewable, and Fossil Energy Sources  

DOE Green Energy (OSTI)

The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because 'free' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen.

Forsberg, Charles W [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL)

2007-01-01T23:59:59.000Z

230

RELATIVE ECONOMIC INCENTIVES FOR HYDROGEN FROM NUCLEAR, RENEWABLE, AND FOSSIL ENERGY SOURCES  

SciTech Connect

The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because 'free' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen.

Gorensek, M; Charles W. Forsberg, C

2008-08-04T23:59:59.000Z

231

RELATIVE ECONOMIC INCENTIVES FOR HYDROGEN FROM NUCLEAR, RENEWABLE, AND FOSSIL ENERGY SOURCES  

SciTech Connect

The specific hydrogen market determines the value of hydrogen from different sources. Each hydrogen production technology has its own distinct characteristics. For example, steam reforming of natural gas produces only hydrogen. In contrast, nuclear and solar hydrogen production facilities produce hydrogen together with oxygen as a by-product or co-product. For a user who needs both oxygen and hydrogen, the value of hydrogen from nuclear and solar plants is higher than that from a fossil plant because 'free' oxygen is produced as a by-product. Six factors that impact the relative economics of fossil, nuclear, and solar hydrogen production to the customer are identified: oxygen by-product, avoidance of carbon dioxide emissions, hydrogen transport costs, storage costs, availability of low-cost heat, and institutional factors. These factors imply that different hydrogen production technologies will be competitive in different markets and that the first markets for nuclear and solar hydrogen will be those markets in which they have a unique competitive advantage. These secondary economic factors are described and quantified in terms of dollars per kilogram of hydrogen.

Gorensek, M; Charles W. Forsberg, C

2008-08-04T23:59:59.000Z

232

SURVEY OF OPERATION AND MAINTENANCE-RELATED MATERIALS NEEDS IN GEOTHERMAL POWER PLANTS  

SciTech Connect

A survey was conducted to determine operation and maintenance (O and M)-related materials needs in geothermal power plants and to identify future research and development to address these needs. A total of 44 questionnaires was mailed to geothermal plant operators and industry consultants. The response rate was 54%. The participants were asked to describe type and frequency of materials problems, strategies currently used to mitigate such problems, barriers to using new or alternative materials and technologies, sources of information and give their views research and development priorities. A. wide range of opinions was obtained, reflecting each individual respondent's perspective and the site-specific nature of some problems. However, the consensus is that corrosion and scaling remain major issues and that components requiring performance improvements include pipelines, well casing, turbines, heat exchangers, condensers, valves and cooling towers. It is recommended that appropriate research and development continue to be directed at reducing O and M costs associated with materials failure or inadequate service. There should be a balance between optimizing existing materials through better design and understanding of behavior in geothermal environments and development of new materials. Life extension of existing equipment, service life prediction, education of plant personnel in materials and methods for mitigating corrosion, and improvements in inhibitors and biocides would also be beneficial.

ALLAN,M.L.

1998-06-01T23:59:59.000Z

233

Survey of operation and maintenance-related materials needs in geothermal power plants  

DOE Green Energy (OSTI)

A survey was conducted to determine operation and maintenance (O and M)-related materials needs in geothermal power plants and to identify future research and development to address these needs. A total of 44 questionnaires was mailed to geothermal plant operators and industry consultants. The response rate was 54%. The participants were asked to describe type and frequency of materials problems, strategies currently used to mitigate such problems, barriers to using new or alternative materials and technologies, sources of information and give their views on research and development priorities. A wide range of opinions was obtained, reflecting each individual respondent`s perspective and the site-specific nature of some problems. However, the consensus is that corrosion and scaling remain major issues and that components requiring performance improvements include pipelines, well casing, turbines, heat exchangers, condensers, valves and cooling towers. It is recommended that appropriate research and development continue to be directed at reducing O and M costs associated with materials failure or inadequate service. There should be a balance between optimizing existing materials through better design and understanding of behavior in geothermal environments and development of new materials. Life extension of existing equipment, service life prediction, education of plant personnel in materials and methods for mitigating corrosion, and improvements in inhibitors and biocides would also be beneficial.

Allan, M.L.

1998-06-01T23:59:59.000Z

234

SURVEY OF OPERATION AND MAINTENANCE-RELATED MATERIALS NEEDS IN GEOTHERMAL POWER PLANTS  

DOE Green Energy (OSTI)

A survey was conducted to determine operation and maintenance (O and M)-related materials needs in geothermal power plants and to identify future research and development to address these needs. A total of 44 questionnaires was mailed to geothermal plant operators and industry consultants. The response rate was 54%. The participants were asked to describe type and frequency of materials problems, strategies currently used to mitigate such problems, barriers to using new or alternative materials and technologies, sources of information and give their views research and development priorities. A. wide range of opinions was obtained, reflecting each individual respondent's perspective and the site-specific nature of some problems. However, the consensus is that corrosion and scaling remain major issues and that components requiring performance improvements include pipelines, well casing, turbines, heat exchangers, condensers, valves and cooling towers. It is recommended that appropriate research and development continue to be directed at reducing O and M costs associated with materials failure or inadequate service. There should be a balance between optimizing existing materials through better design and understanding of behavior in geothermal environments and development of new materials. Life extension of existing equipment, service life prediction, education of plant personnel in materials and methods for mitigating corrosion, and improvements in inhibitors and biocides would also be beneficial.

ALLAN,M.L.

1998-06-01T23:59:59.000Z

235

Recent Studies Related to Past Operations at the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

During the past year, two topics related to past operations of the High Flux Isotope Reactor (HFIR) were reviewed in response to on-going programs at Oak Ridge National Laboratory (ORNL). Currently, studies are being conducted to determine if HFIR can be converted from high enriched uranium (HEU) fuel to low enriched uranium (LEU). While the basis for conversion is the current performance of the reactor, redesign studies revealed an apparent slight degradation in performance of the reactor over its 40 year lifetime. A second program requiring data from HFIR staff is the Integrated Facility Disposition Project (IFDP). The IFDP is a program that integrates environmental cleanup with modernization and site revitalization plans and projects. Before a path of disposal can be established for discharged HFIR beryllium reflector regions, the reflector components must be classified as to type of waste and specifically, determine if they are transuranic waste.

Chandler, David [ORNL; Primm, Trent [ORNL

2009-01-01T23:59:59.000Z

236

System dynamics modeling for human performance in nuclear power plant operation  

E-Print Network (OSTI)

Perfect plant operation with high safety and economic performance is based on both good physical design and successful organization. However, in comparison with the affection that has been paid to technology research, the ...

Chu, Xinyuan

2006-01-01T23:59:59.000Z

237

Modelling the Effects of Nuclear Fuel Reservoir Operation in a Competitive Electricity Market  

E-Print Network (OSTI)

In many countries, the electricity systems are quitting the vertically integrated monopoly organization for an operation framed by competitive markets. In such a competitive regime one can ask what the optimal management ...

Lykidi, Maria

238

An investigation of dual-mode operation of a nuclear-thermal rocket engine  

DOE Green Energy (OSTI)

A preliminary assessment of the technical feasibility and mass competitiveness of a dual-mode nuclear propulsion and power system based on Rover-type reactors has been completed. Earlier studies have indicated that dual-mode systems appear attractive for electrical power levels of a few kilowatts. However, at the megawatt electrical power level considered in this study, it appears that extensive modifications to the nuclear-thermal engines would be required, the feasibility of which is unclear. Mass competitiveness at high electrical power levels is also uncertain. Further study of reactor and shield design in conjuction with mission and vehicle studies is necessary in order to determine a useful dual-mode power range. 9 refs., 20 figs., 4 tabs.

Kirk, W.L.; Hedstrom, J.C.; Moore, S.W.; McFarland, R.D.; Merrigan, M.A.; Buksa, J.J.; Cappiello, M.W.; Hanson, D.L.; Woloshun, K.A.

1991-06-01T23:59:59.000Z

239

Evaluation of an Advanced Radiation Shielding Material for Permanent Installation at an Operating Commercial Nuclear Reactor  

Science Conference Proceedings (OSTI)

The industry continues to investigate, validate, and implement new radiation field reduction measures in response to increased emphasis on reducing dose to workers. Many nuclear plants are interested in permanent shielding applications to further reduce personnel exposure and to reduce the recurring effort associated with temporary installations. In 2008, a flexible, impregnated, layered matrix material was identified as a possible material for incorporating a shielding substance. This report provides an...

2010-09-30T23:59:59.000Z

240

Operations and Maintenance Development: Preventive Maintenance Program Implementation Self-Assessment Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Preventive maintenance (PM) programs throughout nuclear plants in the United States have evolved from strict compliance with the supplier's general recommendations (which are likely to be much too conservative) to more flexible tasks that are intended to accommodate plant-specific service conditions. During the 1990s, the industry, with support from the Electric Power Research Institute (EPRI), embarked on Preventive Maintenance Optimization (PMO) programs. Most utilities either have implemented or are i...

2007-12-20T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

EXECUTIVE SUMMARY In March of2002, the FirstEnergy Nuclear Operating Company (FENOC) discovered a  

E-Print Network (OSTI)

significant degradation ofthe Davis-Besse Nuclear Power Station (the Station) reactor pressure vessel head and entered an extended shutdown. The Station was placed under the U.S. Nuclear Regulatory Commission's Inspection Manual Chapter 0350 process for restart. As part ofthe FENOC Restart Plan, the Station committed to perform an independent evaluation ofthe safety culture at Davis-Besse. This report describes the results ofan evaluation ofthe safety culture at the Davis-Besse Station conducted dUring February 2003. The primary objective ofthe evaluation was to provide information regarding the presence or absence ofsafety culture characteristics at Davis-Besse. Observations regarding the Station's safety culture characteristics and areas in need of improvement with respect to those characteristics are presented. Safety culture characteristics that are important for the existence ofa positive safety culture within a nuclear facility have been identified to include: Safety is a clearly recognized value in the organization. Accountability for safety in tbe organization is clear. Safety is integrated into aU activities in the organization.

unknown authors

2003-01-01T23:59:59.000Z

242

Technical considerations in repowering a nuclear plant for fossil fueled operation  

SciTech Connect

Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today`s world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal.

Patti, F.J.

1996-03-01T23:59:59.000Z

243

Classification of Nuclear Weapons-Related Information (Restricted Data and Formerly Restricted Data)  

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

CLASSIFICATION OF CLASSIFICATION OF NUCLEAR WEAPONS-RELATED INFORMATION Restricted Data and Formerly Restricted Data (RD and FRD) June 2012 2 3 Purpose To familiarize individuals from agencies outside of DOE who may come in contact with RD and FRD with the procedures for identifying, classifying, marking, handling, and declassifying documents containing that information as required by  The Atomic Energy Act and  10 Code of Federal Regulation (CFR) Part 1045, Nuclear Classification and Declassification §1045.35 4 Not the Purpose This briefing does not authorize you to classify or declassify documents containing RD or FRD. Additional training is required to classify documents containing RD or FRD or identify RD or FRD within a document for redaction. Only authorized DOE

244

November 24, 2009, Board Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - Transcript  

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

2-234-4433 2-234-4433 Neal R. Gross & Co., Inc. Page 1 UNITED STATES OF AMERICA + + + + + DEFENSE NUCLEAR FACILITIES SAFETY BOARD + + + + + WEDNESDAY MAY 12, 2010 + + + + + The Board met in the DNFSB Hearing Room at 625 Indiana Avenue, N.W., Suite 300, Washington, D.C., Peter S. Winokur, Chairman, presiding. PRESENT: PETER S. WINOKUR, Chairman JOHN E. MANSFIELD, Vice Chairman JOSEPH F. BADER, Board Member LARRY W. BROWN, Board Member JESSIE H. ROBERSON, Board Member STAFF PRESENT: RICHARD A. AZZARO, General Counsel TIMOTHY J. DWYER, Technical Director

245

A health physics program for operation with failed nuclear fuel; Dealing with fleas  

SciTech Connect

The San Onofre Unit 3 nuclear plant suffered fuel cladding failures during its first fuel cycle. As a result, primary systems and parts of the station were contaminated with fleas--tiny highly radioactive, and highly mobile fuel fragments. This article describes the special health physics practices needed to control flea contamination and to evaluate skin doses when personnel contaminations occur. Included are descriptions of a modified Eberline RO-2 ion chamber survey instrument with enhance flea detection capabilities and a laundry monitor that is used to check protective clothing for fleas.

Warnock, R.V.; Cooper, T.L.; Bray, L.G.; Goldin, E.M.; Knapp, P.J.; Lewis, M.N.; Rigby, W.F. (Southern California Edison Co., San Onofre Nuclear Generating Station, San Clemente, CA (US))

1987-07-01T23:59:59.000Z

246

Advanced Pipe Replacement Procedure for a Defective CRDM Housing Nozzle Enables Continued Normal Operation of a Nuclear Power Plant  

SciTech Connect

During the 2003 outage at the Ringhals Nuclear Plant in Sweden, a leak was found in the vicinity of a Control Rod Drive Mechanism (CRDM) housing nozzle at Unit 1. Based on the ALARA principle for radioactive contamination, a unique repair process was developed. The repair system includes utilization of custom, remotely controlled GTAW-robots, a CNC cutting and finishing machine, snake-arm robots and NDE equipment. The success of the repair solution was based on performing the machining and welding operations from the inside of the SCRAM pipe through the CRDM housing since accessibility from the outside was extremely limited. Before the actual pipe replacement procedure was performed, comprehensive training programs were conducted. Training was followed by certification of equipment, staff and procedures during qualification tests in a full scale mock-up of the housing nozzle. Due to the ingenuity of the overall repair solution and training programs, the actual pipe replacement procedure was completed in less than half the anticipated time. As a result of the successful pipe replacement, the nuclear power plant was returned to normal operation. (authors)

Gilmore, Geoff; Becker, Andrew [Climax Portable Machine Tools, Inc., 2712 East Second Street, Newberg, OR 97132 (United States)

2006-07-01T23:59:59.000Z

247

Design and Operating Guidelines for Condensate Polishers in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Control of impurity ingress to PWR steam generators is essential to prevent significant corrosion damage. A properly designed and operated condensate polisher system can significantly reduce the quantity of impurities transported to steam generators and can provide a measure of protection in the event of a condenser leak.

1991-09-19T23:59:59.000Z

248

Nuclear Maintenance Applications Center: Air-Operated Valve Diagnostic Testing Guide  

Science Conference Proceedings (OSTI)

This report provides information for personnel involved in the performance of air-operated valve (AOV) diagnostic testing, including the benefits of using diagnostics to understand valve health and to tie information into preventive maintenance programs. It provides insights for experienced personnel as well as basic information, guidance, and instructions for personnel assigned to perform, analyze, or purchase diagnostic test equipment.

2011-12-23T23:59:59.000Z

249

Condition monitoring of motor-operated valves in nuclear power plants Pierre Granjon  

E-Print Network (OSTI)

to the valve and increases radiation exposure of operators, leading to long overhaul outage and high techniques rely on the measurement of an internal mechanical quantity and require the presence of human of any internal MOV quantity. In this article, the instantaneous active power absorbed by the induction

Paris-Sud XI, Université de

250

Fuzzy control for nuclear reactor operation -- strengths, weaknesses, opportunities and threats  

Science Conference Proceedings (OSTI)

Assessment of four real fuzzy control applications at the MIT research reactor in the US, the FUGEN heavy water reactor in Japan, the BR1 research reactor in Belgium, and a TRIGA Mark III reactor in Mexico will be analyzed through an analysis of strengths, ... Keywords: Artificial Intelligence, Br1 Reactor, Fuzzy Control, Reactor Operation, Triga Mark Iii Reactor

Da Ruan; Jorge S. Bentez-Read

2005-10-01T23:59:59.000Z

251

Executive Director for Operations USE OF INSURANCE AS A METHOD TO PROVIDE FINANCIAL ASSURANCE FOR DECOMMISSIONING NUCLEAR POWER REACTORS  

E-Print Network (OSTI)

The purpose of this memorandum is to inform the Commission of the staffs proposed Standard Review Plan (SRP) criteria for evaluating the insurance method of providing financial assurance for decommissioning nuclear power reactors and provide the status of the staffs ongoing reviews of two insurance proposals. In a memorandum dated May 20, 2004, from then Executive Director for Operations, Dr. William Travers, the Commission was informed of the staffs receipt of two first-of-a-kind proposals submitted by Marsh USA (Marsh) and Nuclear Electric Insurance Limited (NEIL) to use insurance to provide financial assurance for decommissioning nuclear power reactors pursuant to 10 CFR 50.75(e)(1)(iii). In that memorandum, the staff stated that it would develop SRP criteria to evaluate the use of insurance, commence reviews of the two proposals, and inform the Commission of its progress by October 2004. The U.S. Nuclear Regulatory Commission (NRC) regulations at 10 CFR 50.75(e) specify that insurance is an acceptable method for a licensee to demonstrate reasonable assurance that sufficient funds will be available for the plant decommissioning process. Specifically, 10 CFR 50.75(e)(1)(iii) requires that certain terms and conditions must be present in the decommissioning insurance policy. These conditions include: automatic renewal, 90-days advance notice by the insurer of intent not to renew the policy, and payment of the full face amount into a trust if the licensee fails to provide an acceptable replacement after receiving notice of the insurers intent to cancel the policy. CONTACT: Ronald B. Uleck, NRR/DRIP 301-415-3741 The Commissioners-2-However, 10 CFR 50.75 contains only limited requirements for use of the insurance method. Similarly, existing guidance provided by NUREG-1577, Rev. 1, Standard Review Plan on

unknown authors

2004-01-01T23:59:59.000Z

252

Reducing Operations and Maintenance Costs of Nuclear Power Plant Fire Protection Programs  

Science Conference Proceedings (OSTI)

This report discusses opportunities for utilities to reduce fire protection operations and maintenance (O&M) costs. A number of these opportunities have been implemented by some utilities and can be implemented now by others. Other opportunities can be implemented in the short term with some additional development. These other opportunities are amenable to cooperative projects with costs shared by multiple utilities. There is also a group of opportunities that are probably best developed on an industry w...

1997-01-08T23:59:59.000Z

253

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - Chairman's Opening Statement - May 12, 2010  

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

CHAIRMAN'S OPENING STATEMENT CHAIRMAN'S OPENING STATEMENT GOOD MORNING. MY NAME IS PETER WINOKUR AND I AM THE CHAIRMAN OF THE DEFENSE NUCLEAR FACILITIES SAFETY BOARD. I WILL PRESIDE OVER THIS PUBLIC MEETING AND HEARING. I WOULD LIKE TO INTRODUCE THE MEMBERS OF THE SAFETY BOARD WHO ARE ALL PRESENT HERE TODAY. TO MY IMMEDIATE LEFT IS DR. JOHN MANSFIELD, AND TO HIS LEFT IS MR. JOSEPH BADER. ON MY RIGHT IS MR. LARRY BROWN, AND TO HIS RIGHT IS MS. JESSIE ROBERSON. WE FIVE CONSTITUTE THE BOARD. THE BOARD'S GENERAL COUNSEL, RICHARD AZZARO, IS SEATED TO MY FAR LEFT, AND NEXT TO HIM IS THE BOARD'S GENERAL MANAGER, BRIAN GROSNER. THE BOARD'S TECHNICAL DIRECTOR, TIMOTHY DWYER, IS SEATED TO MY FAR RIGHT. SEVERAL MEMBERS OF OUR STAFF CLOSELY INVOLVED WITH OVERSIGHT OF THE DEPARTMENT OF ENERGY'S DEFENSE

254

Structure for a Living Requirements Repository for Long Term Operation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report describes the structure and specifications for a relational repository that will capture long-term requirements (LTRs) and their dependencies on underlying technologies. In addition, it presents principles and prototypical examples for graphical models that supplement the relational repository and support the development, capture, and re-use of long-term instrumentation and control architectural elements to support plant modifications that enable long-term ...

2013-04-29T23:59:59.000Z

255

Test Operation of Oxygen-Enriched Incinerator for Wastes From Nuclear Fuel Fabrication Facility  

SciTech Connect

The oxygen-enriched combustion concept, which can minimize off-gas production, has been applied to the incineration of combustible uranium-containing wastes from a nuclear fuel fabrication facility. A simulation for oxygen combustion shows the off-gas production can be reduced by a factor of 6.7 theoretically, compared with conventional air combustion. The laboratory-scale oxygen enriched incineration (OEI) process with a thermal capacity of 350 MJ/h is composed of an oxygen feeding and control system, a combustion chamber, a quencher, a ceramic filter, an induced draft fan, a condenser, a stack, an off-gas recycle path, and a measurement and control system. Test burning with cleaning paper and office paper in this OEI process shows that the thermal capacity is about 320 MJ/h, 90 % of design value and the off-gas reduces by a factor of 3.5, compared with air combustion. The CO concentration for oxygen combustion is lower than that of air combustion, while the O2 concentration in off-gas is kept above 25 vol % for a simple incineration process without any grate. The NOx concentration in an off-gas stream does not reduce significantly due to air incoming by leakage, and the volume and weight reduction factors are not changed significantly, which suggests a need for an improvement in sealing.

Kim, J.-G.; Yang, H.cC.; Park, G.-I.; Kim, I.-T.; Kim, J.-K.

2002-02-26T23:59:59.000Z

256

Nuclear Power 2010 Program Lessons Learned Report on the Combined Construction and Operating License/Design Certification Demonstration Projects  

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

Nuclear Power 2010 Program Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report August 30, 2012 Prepared by Longenecker and Associates DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not

257

Measurement of Lake Roosevelt Biota in Relation to Reservoir Operations : Final Report 1993.  

DOE Green Energy (OSTI)

The purpose of this study was to collect biological data from Lake Roosevelt to be used in the design of a computer model that will predict biological responses to reservoir operations as part of the System Operation Review Program. This study worked in conjunction with Lake Roosevelt Monitoring Project which investigated the effectiveness of two kokanee salmon hatcheries. This report summarized the data collected from Lake Roosevelt from 1993 and includes limnological, reservoir operation, zooplankton, benthic macroinvertebrate, experimental trawling, and net-pen rainbow trout tagging data. Major components of the Lake Roosevelt model include quantification of impacts to zooplankton, benthic macroinvertebrates, and fish caused by reservoir drawdowns and low water retention times.

Voeller, Amy C.

1993-01-01T23:59:59.000Z

258

Assessment of modular construction for safety-related structures at advanced nuclear power plants  

SciTech Connect

Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules.

Braverman, J.; Morante, R.; Hofmayer, C.

1997-03-01T23:59:59.000Z

259

Environmental assessment related to the operation of Argonne National Laboratory, Argonne, Illinois  

Science Conference Proceedings (OSTI)

In order to evaluate the environmental impacts of Argonne National Laboratory (ANL) operations, this assessment includes a descriptive section which is intended to provide sufficient detail to allow the various impacts to be viewed in proper perspective. In particular, details are provided on site characteristics, current programs, characterization of the existing site environment, and in-place environmental monitoring programs. In addition, specific facilities and operations that could conceivably impact the environment are described at length. 77 refs., 16 figs., 47 tabs.

Not Available

1982-08-01T23:59:59.000Z

260

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:

Note: This page contains sample records for the topic "nuclear operations related" 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

"1. W A Parish","Coal","NRG Texas Power LLC",3664 "2. South Texas Project","Nuclear","STP Nuclear Operating Co",2560  

U.S. Energy Information Administration (EIA) Indexed Site

Texas" Texas" "1. W A Parish","Coal","NRG Texas Power LLC",3664 "2. South Texas Project","Nuclear","STP Nuclear Operating Co",2560 "3. Martin Lake","Coal","TXU Generation Co LP",2425 "4. Comanche Peak","Nuclear","TXU Generation Co LP",2406 "5. Monticello","Coal","TXU Generation Co LP",1890 "6. Sabine","Gas","Entergy Texas Inc.",1814 "7. Limestone","Coal","NRG Texas Power LLC",1689 "8. Fayette Power Project","Coal","Lower Colorado River Authority",1641 "9. Forney Energy Center","Gas","FPLE Forney LP",1640

262

Department of Energy Issues Request for Pre-Applications to U.S. Universities for Nuclear Energy - Related Research and Development Proposals  

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

The U.S. Department of Energys Nuclear Energy University Programs (NEUP) is now accepting pre-applications from universities interested in conducting nuclear energy- related research and development (R&D) projects.

263

Department of Energy Issues Call for Proposals to U.S. Universities for Nuclear Energy-Related Integrated Research Project Proposals  

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

The U.S. Department of Energys Nuclear Energy University Programs is now accepting applications from universities interested in conducting nuclear energy-related Integrated Research Projects.

264

Instrumentation and Control, Human System Interface, and Information Technology Requirements Project Plan for Nuclear Power Plant Lo ng-Term Operation  

Science Conference Proceedings (OSTI)

Nuclear power plant owners are looking to extend the operating life of their plants to 80 years and potentially longer. Instrumentation and control, human system interface, and information technologies have changed drastically since the plants were built and will change even more drastically before the plants reach the end of their operating life. A project plan to develop requirements for these technologies is defined here. These requirements will enable plants to better identify future solutions that w...

2010-02-03T23:59:59.000Z

265

2012 Nuclear Safety Workshop Presentations | Department of Energy  

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

2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations 2012 Nuclear Safety Workshop Presentations Wednesday, September 19 - Plenary Session September 19, 2012 Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company September 19, 2012 A Commissioner's Perspective on USNRC Actions in Response to the Fukushima Nuclear Accident Presenter: Honorable William C. Ostendorff, Commissioner US Nuclear Regulatory Commission September 19, 2012 International Perspective on Fukushima Accident Presenter: Miroslav Lipár, Head, Operational Safety Section, Department of

266

List of currently classified documents relative to Hanford Production Facilities Operations originated on the Hanford Site between 1961 and 1972  

Science Conference Proceedings (OSTI)

The United States Department of Energy (DOE) has declared that all Hanford plutonium production- and operations-related information generated between 1944 and 1972 is declassified. Any documents found and deemed useful for meeting Hanford Environmental Dose Reconstruction (HEDR) objectives may be declassified with or without deletions in accordance with DOE guidance by Authorized Derivative Declassifiers. The September 1992, letter report, Declassifications Requested by the Technical Steering Panel of Hanford Documents Produced 1944--1960, (PNWD-2024 HEDR UC-707), provides an important milestone toward achieving a complete listing of documents that may be useful to the HEDR Project. The attached listing of approximately 7,000 currently classified Hanford-originated documents relative to Hanford Production Facilities Operations between 1961 and 1972 fulfills TSP Directive 89-3. This list does not include such titles as the Irradiation Processing Department, Chemical Processing Department, and Hanford Laboratory Operations monthly reports generated after 1960 which have been previously declassified with minor deletions and made publicly available. Also Kaiser Engineers Hanford (KEH) Document Control determined that no KEH documents generated between January 1, 1961 and December 31, 1972 are currently classified. Titles which address work for others have not been included because Hanford Site contractors currently having custodial responsibility for these documents do not have the authority to determine whether other than their own staff have on file an appropriate need-to-know. Furthermore, these documents do not normally contain information relative to Hanford Site operations.

Not Available

1993-04-01T23:59:59.000Z

267

Expert Identity construct in analysing prerequisites for expertise development: a case study of nuclear power plant operators on-the-job training  

Science Conference Proceedings (OSTI)

This article discusses how shifting the focus of research to the emotional side of human actions and cognition could create new perspectives on the problem of how to support the human operator in the control of rare disturbances. A new construct, Expert ... Keywords: Emotions, Expert Identity, Nuclear power plant, On-the-job training, Process control, Work analysis

Maaria Nuutinen

2005-11-01T23:59:59.000Z

268

Nuclear Sites Map  

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

reactor operations, nuclear research, weapons disassembly, maintenance and testing, hot cell operations, nuclear material storage and processing and waste disposal. Each...

269

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Dose Commitments from Nuclear Tests carried out beforeDose Commitments from Nuclear Tests carried out before 1968,of the dose from nuclear weapons test fallout. As indicated

Nero, A.V.

2010-01-01T23:59:59.000Z

270

Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980  

SciTech Connect

This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

McCormack, K.E.; Gallaher, R.B.

1982-03-01T23:59:59.000Z

271

Guidelines for the Selection, Procurement, and Acceptance of Nuclear Safety-Related Mild Environment Motor Insulation for Rewinds  

Science Conference Proceedings (OSTI)

As existing nuclear power plants mature, a need exists to provide high quality repair services for safety-related electric motors. This guideline supplements previous EPRI efforts to provide guidance on the selection, procurement, acceptance, and dedication of the insulating materials used during the rewinding of motors located in mild environment plant areas.

1994-09-14T23:59:59.000Z

272

Nuclear Data Resources for Capture gamma-Ray Spectroscopy and Related Topics  

E-Print Network (OSTI)

Nuclear reaction data play an important role in nuclear reactor, medical, and fundamental science and national security applications. The wealth of information is stored in internally adopted ENDF-6 and EXFOR formats. We present a complete calculation of resonance integrals, Westcott factors, thermal and Maxwellian-averaged cross sections for Z=1-100 using evaluated nuclear reaction data. The addition of newly-evaluated neutron reaction libraries, and improvements in data processing techniques allows us to calculate nuclear industry and astrophysics parameters, and provide additional insights on all currently available neutron-induced reaction data. Nuclear reaction calculations will be discussed and an overview of the latest reaction data developments will be given.

B. Pritychenko

2011-08-23T23:59:59.000Z

273

Nuclear Data Resources for Capture gamma-Ray Spectroscopy and Related Topics  

E-Print Network (OSTI)

Nuclear reaction data play an important role in nuclear reactor, medical, and fundamental science and national security applications. The wealth of information is stored in internally adopted ENDF-6 and EXFOR formats. We present a complete calculation of resonance integrals, Westcott factors, thermal and Maxwellian-averaged cross sections for Z=1-100 using evaluated nuclear reaction data. The addition of newly-evaluated neutron reaction libraries, and improvements in data processing techniques allows us to calculate nuclear industry and astrophysics parameters, and provide additional insights on all currently available neutron-induced reaction data. Nuclear reaction calculations will be discussed and an overview of the latest reaction data developments will be given.

Pritychenko, B

2011-01-01T23:59:59.000Z

274

Design modification for the modular helium reactor for higher temperature operation and reliability studies for nuclear hydrogen production processes  

E-Print Network (OSTI)

Design options have been evaluated for the Modular Helium Reactor (MHR) for higher temperature operation. An alternative configuration for the MHR coolant inlet flow path is developed to reduce the peak vessel temperature (PVT). The coolant inlet path is shifted from the annular path between reactor core barrel and vessel wall through the permanent side reflector (PSR). The number and dimensions of coolant holes are varied to optimize the pressure drop, the inlet velocity, and the percentage of graphite removed from the PSR to create this inlet path. With the removal of ~10% of the graphite from PSR the PVT is reduced from 541 0C to 421 0C. A new design for the graphite block core has been evaluated and optimized to reduce the inlet coolant temperature with the aim of further reduction of PVT. The dimensions and number of fuel rods and coolant holes, and the triangular pitch have been changed and optimized. Different packing fractions for the new core design have been used to conserve the number of fuel particles. Thermal properties for the fuel elements are calculated and incorporated into these analyses. The inlet temperature, mass flow and bypass flow are optimized to limit the peak fuel temperature (PFT) within an acceptable range. Using both of these modifications together, the PVT is reduced to ~350 0C while keeping the outlet temperature at 950 0C and maintaining the PFT within acceptable limits. The vessel and fuel temperatures during low pressure conduction cooldown and high pressure conduction cooldown transients are found to be well below the design limits. The reliability and availability studies for coupled nuclear hydrogen production processes based on the sulfur iodine thermochemical process and high temperature electrolysis process have been accomplished. The fault tree models for both these processes are developed. Using information obtained on system configuration, component failure probability, component repair time and system operating modes and conditions, the system reliability and availability are assessed. Required redundancies are made to improve system reliability and to optimize the plant design for economic performance. The failure rates and outage factors of both processes are found to be well below the maximum acceptable range.

Reza, S.M. Mohsin

2007-05-01T23:59:59.000Z

275

National Nuclear Security Administration  

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

National Nuclear Security Administration Finding of No Significant Impact for the Construction and Operation of a New Office Building and Related Structures within TA-3 at Los Alamos National Laboratory, Los Alamos, New Mexico U. S. Department of Energy National Nuclear Security Administration Los Alamos Area Office 528 35th Street Los Alamos, N M 8 7 5 4 4 DEPARTMENT OF ENERGY. NATIONAL NUCLEAR SECUIRTY ADMINISTRATION FINDING OF NO SIGNIFICANT INIPACT Construction and Operation of a New Office Building and Related Structures withinTA-3 at Los Alarnos National Laboratory, Los Alamos. New Mexico FINAL ENVIRONMENTAL ASSESSMENT: The Environmental Assessment (EA) for Construction and Operation of a New Office Building and Related Structures within TA-3 at L os Alamos National Laboratory, Los Alamos, New Mexico (DOE/EA- 7 375)

276

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site  

Science Conference Proceedings (OSTI)

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

L.E. Demick

2011-10-01T23:59:59.000Z

277

Light Water Reactor Sustainability (LWRS) Initiative Science-Based R&D to Extend Nuclear Plant Operation  

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

Nuclear Energy Nuclear Energy Updates Dr. Pete Lyons Acting Assistant Secretary for Nuclear Energy U.S. Department of Energy December 9, 2010 NEAC Meeting Leadership Changes Pete Miller retired Pete Lyons - Acting NE-1 Shane Johnson - Acting NE-2 Dennis Miotla - Acting COO Monica Regalbuto - Acting DAS for Fuel Cycle Technologies John Herczeg- Acting ADAS for Fuel Cycle Technologies John Kelly - DAS for Nuclear Reactor Technologies Bob Boudreau- Acting ADAS International Nuclear Energy Coop Monica Regalbuto John Kelly NE University Programs (NEUP) - Overview and FY 2011 Schedule NEUP FY 2011 Solicitations Schedule RPA/FOA Pre- Applications Proposals Due Awards Announced R&D (PS and Blue Sky) Oct. '10 Dec. '10 Feb. '11 May '11 Integrated Research Projects (IRP) Dec. '10 Late Jan '11

278

The nuclear structure and related properties of some low-lying isomers of free-space O_n clusters (n=6, 8, 12)  

E-Print Network (OSTI)

After some introductory comments relating to antiferromagnetism of crystalline O_2, and brief remarks on the geometry of ozone, Hartree-Fock (HF) theory plus second-order Moller-Plesset (MP2) corrections are used to predict the nuclear structure of low-lying isomers of free-space O_n clusters, for n=6, 8, and 12. The equilibrium nuclear-nuclear potential energy is also discussed in relation to the number n of oxygen atoms in the cluster.

Forte, G; March, N H; Pucci, R

2013-01-01T23:59:59.000Z

279

Supplement Analysis for the Final Environmental Impact Statement for the Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components  

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

D D E P A R T M E N T O F E N E R G Y U N I T E D S T A T E S O F A M E R I C A SUPPLEMENT ANALYSIS FOR THE FINAL ENVIRONMENTAL IMPACT STATEMENT FOR THE CONTINUED OPERATION OF THE PANTEX PLANT AND ASSOCIATED STORAGE OF NUCLEAR WEAPON COMPONENTS DOE/EIS-0225/SA-03 United States Department of Energy National Nuclear Security Administration Pantex Site Operations P.O. Box 30030 Amarillo, Texas 79120-0030 February 2003 i Summary The U.S. Department of Energy's (DOE's) National Environmental Policy Act (NEPA) Implementing Procedures at 10 CFR 1021.330(d) require evaluation of its site-wide environmental impact statements (EISs) at least every 5 years by preparation of a supplement analysis (SA), as provided in 10 CFR 1021.314. Based on the SA, a determination is made as to whether the existing EIS remains

280

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

U. S. Conunercial Nuclear Power Plants", Report WASH-1400 (for Light-Water Cooled Nuclear Power Plants to Assess PlantStandards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

applies, not only to the nuclear reactor, but also to otherdetailed de- sign of nuclear reactor power s tations is vgreat importance in nuclear reactor accidents. 3.2 Increase

Nero, A.V.

2010-01-01T23:59:59.000Z

282

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

refabrication. through which nuclear fuel passes. Fusion.with the experience at the Nuclear Fuel Services Plant (seecommitment from the nuclear fuel cycle; see Section 3.2.3. )

Nero, A.V.

2010-01-01T23:59:59.000Z

283

Nuclear Detonation Detection | National Nuclear Security Administratio...  

National Nuclear Security Administration (NNSA)

Research and Development > Nuclear Detonation Detection Nuclear Detonation Detection NNSA builds the nation's operational sensors that monitor the entire planet from space to...

284

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Table 17. Purchases of enrichment services by owners and operators of U.S. civilian nuclear power reactors by contract type in delivery year, 2012

285

Relation between the 2{nu}{beta}{beta} and 0{nu}{beta}{beta} nuclear matrix elements  

SciTech Connect

A formal relation between the GT part of the nuclear matrix elements M{sub GT}{sup 0{nu}} of 0{nu}{beta}{beta} decay and the closure matrix elements M{sub cl}{sup 2{nu}} of 2{nu}{beta}{beta} decay is established. This relation is based on the integral representation of these quantities in terms of their dependence on the distance r between the two nucleons undergoing transformation. We also discuss the difficulties in determining the correct values of the closure 2{nu}{beta}{beta} decay matrix elements.

Vogel, Petr [Kellogg Radiation Laboratory, Caltech, Pasadena, CA 91125 (United States); Simkovic, Fedor [Department of Nuclear Physics and Biophysics, Comenius University, Mlynska dolina F1, SK-84248 Bratislava (Slovakia)

2011-12-16T23:59:59.000Z

286

The (safety-related) heat exchangers aging management guideline for commercial nuclear power plants, and developments since 1994  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE), in cooperation with the Electric Power Research Institute (EPRI) and US nuclear power plant utilities, is preparing a series of aging management guidelines (AMGs) for commodity types of components (e.g., heat exchangers, electrical cable and terminations, pumps). Commodities are included in this series based on their importance to continued nuclear plant operation and license renewal. The AMGs contain a detailed summary of operating history, stressors, aging mechanisms, and various types of maintenance and surveillance practices that can be combined to create an effective aging management program. Each AMG is intended for use by the systems engineers and plant maintenance staff (i.e., an AMG is intended to be a hands-on technical document rather than a licensing document). The heat exchangers AMG, published in June 1994, includes the following information of interest to nondestructive examination (NDE) personnel: aging mechanisms determined to be non-significant for all applications; aging mechanisms determined to be significant for some applications; effective conventional programs for managing aging; and effective unconventional programs for managing aging. Since the AMG on heat exchangers was published four years ago, a brief review has been conducted to identify emerging regulatory issues, if any. The results of this review and lessons learned from the collective set of AMGs are presented.

Clauss, J.M.

1998-08-01T23:59:59.000Z

287

Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

288

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - Statement of Thomas P. DAgostino - May 12, 2010  

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

of Thomas P. D'Agostino of Thomas P. D'Agostino Administrator, National Nuclear Security Administration Defense Nuclear Facilities Safety Board Public Hearing on Line and Independent Oversight May 12, 2010 Mr. Chairman, members of the Board, thank you for this opportunity to meet with you in this public forum to discuss effective oversight of our nuclear facilities. You provided written lines of inquiry prior to this meeting, and my formal response is organized around them. Of course, I will also be happy to answer any additional questions you may have. Let me begin by describing our overall oversight approach as it currently exists. I will discuss its effectiveness, point out both its strengths and weaknesses, and use it as a basis for describing the changes we are considering. I will then discuss our approach to

289

Long-Term Global Trade-Offs Related to Nuclear Energy  

SciTech Connect

An overall comparative assessment of different energy systems and their potential long-term role in contributing to a sustainable energy mix is examined through the use of a global, long-term Energy, Economics, Environment (E{sup 3}) model. This model is used to generate a set of surprise-free futures that encompass a range of economic potentialities. The focus of this study is nuclear energy (NE), and the range of possible futures embodies extrema of NE growth [a Basic Option (BO)] to an NE Phase Out (PO). These NE scenario extrema are expressed against a background that reflects E{sup 3} circumstances ranging from a Business-As-Usual (BAU) to one that is Ecologically Driven (ED), with the latter emphasizing price-induced reductions in greenhouse-gas (GHG) emissions associate with a mix of fossil energy sources. Hence, four ''views-of-the-future'' scenarios emerge to form the framework of this study: BAU/BO, BAU/PO, ED/BO, and ED/PO. Model results ranging from (regional and temporal) primary- and nuclear-energy demands, carbon-dioxide emissions, nuclear-material (plutonium) accumulations and attendant proliferation-risk implications, Gross National Product (GNP) impacts, and a range of technology requirements provide essential input to the subject assessment.

Krakowski, R.A.

1999-08-25T23:59:59.000Z

290

The BURNUP package of applied programs used for computing the isotopic composition of materials of an operating nuclear reactor  

SciTech Connect

This paper described the procedure of implementation and the possibilities of the BURNUP program. The purpose of the program is to predict the change in the nuclear composition of the materials of which a reactor is made in the course of its run and compute the radiation characteristics of the materials after their irradiation.

Yudkevich, M. S., E-mail: umark@adis.vver.kiae.ru [National Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

291

July 24, 2006, Department letter providing status and path forward for the 2004-1 implementation plan, Oversight of Complex, High-Hazard Nuclear Operations  

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

July 24, 2006 July 24, 2006 The Honorable A. J. Eggenberger Chairman Defense Nuclear Facilities Safety Board 625 Indiana Avenue, NW, Suite 700 Washington, DC 20004-294 1 Dear Mr. Chairman: In June 2005, I provided you with a copy of the Department's revised Implementation Plan to Improve Oversight of Nuclear Operations in response to Board recommendation 2004- 1 . Since that time, the Department has completed numerous planned actions and has learned from this experience how best to sustain real improvement in this area. Based on the feedback to date, we are preparing to make a course correction on our implementation plan to improve its effectiveness and to bolster line management accountability. To this end, we plan to revise our 2004-1 implementation plan and provide you with this revision by

292

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

293

Issues relating to spent nuclear fuel storage on the Oak Ridge Reservation  

Science Conference Proceedings (OSTI)

Currently, about 2,800 metric tons of spent nuclear fuel (SNF) is stored in the US, 1,000 kg of SNF (or about 0.03% of the nation`s total) are stored at the US Department of Energy (DOE) complex in Oak Ridge, Tennessee. However small the total quantity of material stored at Oak Ridge, some of the material is quite singular in character and, thus, poses unique management concerns. The various types of SNF stored at Oak Ridge will be discussed including: (1) High-Flux Isotope Reactor (HFIR) and future Advanced Neutron Source (ANS) fuels; (2) Material Testing Reactor (MTR) fuels, including Bulk Shielding Reactor (BSR) and Oak Ridge Research Reactor (ORR) fuels; (3) Molten Salt Reactor Experiment (MSRE) fuel; (4) Homogeneous Reactor Experiment (HRE) fuel; (5) Miscellaneous SNF stored in Oak Ridge National Laboratory`s (ORNL`s) Solid Waste Storage Areas (SWSAs); (6) SNF stored in the Y-12 Plant 9720-5 Warehouse including Health. Physics Reactor (HPRR), Space Nuclear Auxiliary Power (SNAP-) 10A, and DOE Demonstration Reactor fuels.

Klein, J.A.; Turner, D.W.

1994-12-31T23:59:59.000Z

294

Pacific Northwest Laboratory: Annual report for 1986 to the Assistant Secretary for Environment, Safety and Health: Part 5, Nuclear and operational safety  

Science Conference Proceedings (OSTI)

Part 5 of the 1986 Annual Report to the Department of Energy's Assistant Secretary for Environment, Safety and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis. For each project, as identified by the Field Task Proposal/Agreement, articles describe progress made during fiscal year 1986. Authors of these articles represent a broad spectrum of capabilities derived from three of the seven research departments of the Laboratory, reflecting the interdisciplinary nature of the work.

Faust, L.G.; Kennedy, W.E.; Steelman, B.L.; Selby, J.M.

1987-02-01T23:59:59.000Z

295

Public Meeting on Oversight of Complex, High Hazard Nuclear Operations - Vice Chairman's Opening Statement - November 24, 2009  

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

VICE CHAIRMAN'S OPENING STATEMENT VICE CHAIRMAN'S OPENING STATEMENT GOOD MORNING. MY NAME IS JOHN MANSFIELD AND I AM THE VICE CHAIRMAN OF THE DEFENSE NUCLEAR FACILITIES SAFETY BOARD. I WILL PRESIDE OVER THIS PUBLIC MEETING AND HEARING. I WOULD LIKE TO INTRODUCE THE MEMBERS OF THE SAFETY BOARD WHO ARE PRESENT HERE TODAY. TO MY IMMEDIATE LEFT IS MR. JOSEPH BADER. AND TO HIS LEFT IS DR. PETER WINOKUR. ON MY RIGHT IS MR. LARRY BROWN. WE FOUR CONSTITUTE THE BOARD. THE BOARD'S GENERAL COUNSEL, RICHARD AZZARO, IS SEATED TO MY FAR LEFT, AND NEXT TO HIM IS THE BOARD'S GENERAL MANAGER, BRIAN GROSNER. THE BOARD'S TECHNICAL DIRECTOR, TIM DWYER, IS SEATED TO MY FAR RIGHT. SEVERAL MEMBERS OF OUR STAFF CLOSELY INVOLVED WITH OVERSIGHT OF THE DEPARTMENT OF ENERGY'S DEFENSE NUCLEAR FACILITIES ARE ALSO

296

Nondestructive Evaluation: 5th International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurized Compo nents  

Science Conference Proceedings (OSTI)

The 5th International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurized Components was held May 1012, 2006, in San Diego, California. The conference was co-organized by the EPRI NDE Center and the European Commissions Joint Research Centre, Institute for Energy (EC-JRC/IE). The theme of this conference series is to provide a link between the information originated by NDE and the use made of this information in assessing structural integrity. In this context, there is often...

2006-12-13T23:59:59.000Z

297

Commercial Nuclear Electric Power in the United States: Problems and Prospects  

Reports and Publications (EIA)

This article briefly reviews the origins of commercial nuclear electric power, the efforts to dispose of high-level nuclear waste, the costs of building and operating nuclear electric power plants, and other energy-related developments pertinent to the future of nuclear electric power.

Information Center

1994-08-01T23:59:59.000Z

298

The distribution and history of nuclear weapons related contamination in sediments from the Ob River, Siberia as determined by isotopic ratios of Plutonium, Neptunium, and Cesium  

E-Print Network (OSTI)

This thesis addresses the sources and transport of nuclear weapons related contamination in the Ob River region, Siberia. In addition to being one of the largest rivers flowing into the Arctic Ocean, the bulk of the former ...

Kenna, Timothy C

2002-01-01T23:59:59.000Z

299

Ground motion from earthquakes and underground nuclear weapons tests: a comparison as it relates to siting a nuclear waste storage facility at NTS  

Science Conference Proceedings (OSTI)

Ground motion generated by a magnitude 4.3 earthquake at Massachusetts Mountain on the Nevada Test Site was measured at the control point and compared with ground motion generated at about the same distance by four underground nuclear weapons tests. The depth of the earthquake was between 4 and 4.6 km. The resulting signal at the distance considered was almost entirely body-wave components and had little or no contribution from the surface wave. The motion from the relatively shallower weapons tests had a signal with a pronounced surface-wave component. Comparison of the Pseudo Relative Response Velocity (PSRV) plots shows the earthquake signal richer in high frequencies and the weapons-test signals richer in low frequencies. If relationship between ground motion from the two sources can be confirmed for other earthquakes, weapons test ground motion could be used to estimate earthquake ground motion for magnitudes for which probability of occurrence in a given montoring period would be very small.

Vortman, L.J.

1982-01-01T23:59:59.000Z

300

Nuclear Science & Technology  

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

Nuclear Science & Technology Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. /No/ Nuclear Science & Technology Some of these resources are LANL-only and will require Remote Access. Key Resources Databases Organizations Journals Key Resources International Atomic Energy Agency IAEA scientific and technical publications cover areas of nuclear power, radiation therapy, nuclear security, nuclear law, and emergency repose. Search under Publications/Books and Reports for scientific books, standards, technical guides and reports National Nuclear Data Center Nuclear physics data for basic nuclear research and for applied nuclear technologies, operated by Brookhaven.

Note: This page contains sample records for the topic "nuclear operations related" 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

Method to predict relative hydriding within a group of zirconium alloys under nuclear irradiation  

DOE Patents (OSTI)

An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-based materials is disclosed. Samples of zirconium-based materials having different compositions and/or fabrication methods are autoclaved in a relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solution at constant temperatures within the water reactor coolant temperature range (280 to 316 C). Samples tested by this out-of-reactor procedure, when compared on the basis of the ratio of hydrogen weight gain to oxide weight gain, accurately predict the relative rate of hydriding for the same materials when subject to in-reactor (irradiated) corrosion. 1 figure.

Johnson, A.B. Jr.; Levy, I.S.; Trimble, D.J.; Lanning, D.D.; Gerber, F.S.

1990-04-10T23:59:59.000Z

302

Guidelines for the Repair of Nuclear Power Plant Safety-Related Motors (NCIG-12)  

Science Conference Proceedings (OSTI)

These guidelines, the twelfth in a series cosponsored by NCIG, provide utilities with information on the repair of all classes of safety-related electric motors. Use of this information will permit capable repair shops to repair motors under the extension of utility quality assurance programs or by dedication of a commercially repaired motor.

1990-04-24T23:59:59.000Z

303

Countering Nuclear Terrorism | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism | National Nuclear Security Administration Countering Nuclear Terrorism | 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 The National Nuclear Security Administration Countering Nuclear Terrorism Home > Our Mission > Countering Nuclear Terrorism Countering Nuclear Terrorism NNSA provides expertise, practical tools, and technically informed policy

304

U.S. Nuclear Command and Control System Support Staff, "Assessment Report: Department of Energy Nuclear Weapons-Related Security Oversight Process," March 1998  

E-Print Network (OSTI)

August 5, 1977 DOE, "Plutonium: The First 50 Years. United States Plutonium Production, Acquisition, and Utilization from 1944 Through 1994 GAO/RCED-92-39, "Nuclear Security: Safeguards and Security Weaknesses at DOE's Weapons Facilities," December 13, 1991 GAO/RCED/AIMD-95-5, "Nuclear Nonproliferation: U.S. International Nuclear Materials Tracking Capabilities are Limited," December 27, 1994 GAO/AIMD-95-165, "Department of Energy: Poor Management of Nuclear Materials Tracking Capabilities Are Limited," August 3, 1995 Classified DOE report.

Gao Rced- Major

1999-01-01T23:59:59.000Z

305

Overview of the nuclear data related to the Hiroshima Dosimetry Discrepancy  

Science Conference Proceedings (OSTI)

Nearly half a century ago the first atomic bomb was dropped on Hiroshima; several days later, a second atomic bomb was dropped on Nagasaki. Japan immediately initiated a study of all aspects of the effects of the bombings. Thus the initial effort was begun to estimate the overall risks of radiation effects in man due to nuclear detonations. By the 1950s, Japan and the United States had produced several studies that reported on the elevated risk of cancer. In 1957 the first dose estimates for survivors were designated as Tentative 1957 Doses or T57D. In 1965 a revised dosimetry system was adopted to replace T57D, and the dose estimates were designated as Tentative 1965 Doses or T65D. The current evaluation, known as Dosimetry System 1986 or DS86, was the result of a presentation by H.H. Rossi in 1976 to the US National Council on Radiation Protection and Measurements (NCRP). In the presentation, Rossi recommended that the NCRP reduce its permissible neutron dose limits by an order of magnitude. A direct result of this drastic proposal was a new dosimetry reevaluation effort. After the calculations were made and compared to the measurements, it was found that the thermal data at both cities was in disagreement. The state-of-the-art radiation transport calculational codes require evaluated neutron and gamma-ray reaction cross-section data (which themselves were determined empirically or theoretically) to complete the cycle and calculate the measured data. This paper will review some of the more important in situ measured data taken over the last forty-five years, the measurement and reevaluation of some of the major cross sections required for the calculations, and the effort to agreement through calculations with some of the in situ measurements.

Pace, J.V. III

1994-09-01T23:59:59.000Z

306

Pilot Application of Risk-Informed Safety Margins to Support Nuclear Plant Long-Term Operation Decisions  

Science Conference Proceedings (OSTI)

This report describes an industry application of the risk-informed safety margin characterization (RISMC) framework to the analysis of the impacts of a power uprate to a loss of main feedwater (LOMFW) event. The primary objective of this effort was to assess the changes in the safety margins for this event that result from the elevated power levels associated with a hypothetical plant power uprate. This analysis focused on the probabilistic risk assessment modeling of feed-and-bleed operation for ...

2012-12-12T23:59:59.000Z

307

Light Water Reactor Sustainability (LWRS) Initiative Science-Based R&D to Extend Nuclear Plant Operation  

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

9, 2010 9, 2010 New Program Proposal for Fiscal Year 2011 - Modified Open Cycle Carter "Buzz" Savage Nuclear Energy Advisory Committee Meeting April 29, 2010 Washington, DC April 29, 2010 Recycle of Used Fuel Option to recycle used fuel has been the subject of much debate and discussion. Nonproliferation issues and economics have limited recycle options. Recycle of used fuel enables increased utilization of uranium resource and potential waste management benefits. - Once through fuel cycle uses less than 1% of energy value of the uranium. Courtesy AREVA 2 April 29, 2010 Summary of Fuel Cycle Options 3 Once-Through Fuel Cycle - One pass through reactor, used fuel directly disposed in a geologic repository. Modified Open Cycle - No or limited separations steps and

308

Nuclear Forensics | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Forensics | National Nuclear Security Administration Forensics | 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 Nuclear Forensics Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Nuclear Forensics Nuclear Forensics Forensics Operations The National Technical Nuclear Forensics (NTNF) program is a Homeland Security Council and National Security

309

LWR Sustainability: Assessment of Aging of Nuclear Power Plant Safety Related Concrete Strutures  

Science Conference Proceedings (OSTI)

Current regulatory testing and inspection requirements are reviewed and a summary of degradation experience is presented. Techniques commonly used to inspect NPP concrete structures to assess and quantify age-related degradation are summarized. An approach for conduct of condition assessments of structures in NPPs is presented. Criteria, based primarily on visual indications, are provided for use in classification and assessment of concrete degradation. Materials and techniques for repair of degraded structures are generally discussed.

Graves III, Herman [U.S. Nuclear Regulatory Commission; Naus, Dan J [ORNL

2013-01-01T23:59:59.000Z

310

Using population risk assessment as a basis for administrative decisions related to storage of irradiated nuclear fuel  

SciTech Connect

Available in abstract form only. Full text of publication follows: Optimization of safety related decisions by local authorities could be improved using information on potential risks to a regional population. A joint Russia-US effort in 2001-2002 modeled potential population health risks for a proposed nuclear waste storage facility in northern Russia. Conducting such an assessment in addition to the standard PRA is proposed as an innovation in Russia aimed at better meeting the needs of local decision makers. This case-study analysis was conducted for the proposed facility to provide insights into potential population health risks. In the case study results, the background population risks from radiation accident exposures were very low compared to risks from chemical background exposures - an unexpected outcome for those that perceive any nuclear facility as very hazardous to the local population. The paper notes that rather than requiring a proposed low-risk facility for hazardous materials be made even safer, these results give the local authority the option of proposing a trade-off of having a major unrelated regional risks mitigated. The results show the value of conducting a population risk assessment in addition to a facility-oriented PRA as a means of better defining the potential impacts. (authors)

Droppo, James G. [Pacific Northwest National Laboratory, PO Box 999, Richland WA 99352 (United States); Eremenko, V.A. [International Knowledge Bridge LLC (Russian Federation); Linde, J. [Association on Computer Technology and Informational Systems - ACTIS (Russian Federation); Shilova, E. [Moscow Institute of International Economic Relations, 76, Vernadsky av. 119454 Moscow (Russian Federation)

2007-07-01T23:59:59.000Z

311

D and D Operational Experience  

SciTech Connect

This paper describes the operational experience gained from more than 25 million man-hours of Decontamination and Decommissioning (D and D) work on both Department of Energy sites and commercial nuclear facilities in the United States. Nuclear D and D activities encompass some of the most hazardous activities imaginable - protecting workers from a huge range and endless combinations of industrial safety, radiological, nuclear safety, and industrial hygiene issues which challenges managers and safety professionals. Performing D and D activities safely is essential to project success. Managers must ensure that work is properly planned and executed, that hazards are identified and mitigated, and that operational experience is captured and utilized on future projects. Many of the lessons learned directly relate to the principles of behavioral-based safety. Our experience indicates that improved safety performance leads to improved productivity. (authors)

Meyer, K.A.; Smith, C.B. [BNG America, 9781 S. Meridian Blvd., Suite 100, Englewood, CO 80112 (United States)

2006-07-01T23:59:59.000Z

312

Experimental and theoretical investigation of operational and survivability issues in thermal radiators for thermionic space nuclear power systems. Final report  

SciTech Connect

Heat pipes are a promising candidate for spacecraft radiators. This report describes a program designed to investigate the mass migration phenomenon in heat pipes. The program involved experiments to observe and measure the mass migration rates in both high and low operating temperature heat pipes. The low-temperature experiments were intended to simulate the operation of high-temperature, liquid metal heat pipes. Octadecane was the selected low-temperature working fluid. It is a paraffin and exhibits some of the characteristics of liquid metal working fluids. Sodium was the working fluid used in the high temperature experiment. A one-dimensional compressible flow model was developed for describing the hydrodynamics of rarefied vapor flow in heat pipe condensers. This model was compared with experimental data for the low-temperature octadecane heat pipes and the high-temperature sodium heat pipe. The model was found to satisfactorily predict the temperature profiles and location of freeze-fronts for the low-temperature heat pipes. Mass migration rate predictions using the model were satisfactory for the low-temperature heat pipes as well. However, the mass migration prediction for the high-temperature, sodium heat pipe was not in agreement with experimental data. An analytical model which accounts for property variations in the radial as well as longitudinal directions is recommended. A one-dimensional model was unsatisfactory for predicting mass migration rates in liquid metal heat pipes.

Keddy, M.D.

1994-03-15T23:59:59.000Z

313

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

DOE Green Energy (OSTI)

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

314

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

315

Rail versus truck fuel efficiency: The relative fuel efficiency of truck-competitive rail freight and truck operations compared in a range of corridors. Final report  

SciTech Connect

The report summarizes the findings of a study to evaluate the fuel efficiency of rail freight operations relative to competing truckload service. The objective of the study was to identify the circumstances in which rail freight service offers a fuel efficiency advantage over alternative truckload options, and to estimate the fuel savings associated with using rail service. The findings are based on computer simulations of rail and truck freight movements between the same origins and destinations. The simulation input assumptions and data are based on actual rail and truck operations. Input data was provided by U.S. regional and Class I railroads and by large truck fleet operators.

Not Available

1991-04-01T23:59:59.000Z

316

Studies Related to Chemical Mechanisms of Gas Formation in Hanford High-Level Nuclear Wastes  

DOE Green Energy (OSTI)

The objective of this work is to develop a more detailed mechanistic understanding of the thermal reactions that lead to gas production in certain high-level waste storage tanks at the Hanford, Washington site. Prediction of the combustion hazard for these wastes and engineering parameters for waste processing depend upon both a knowledge of the composition of stored wastes and the changes that they undergo as a result of thermal and radiolytic decomposition. Since 1980 when Delagard first demonstrated that gas production (H2and N2O initially, later N2 and NH3)in the affected tanks was related to oxidative degradation of metal complexants present in the waste, periodic attempts have been made to develop detailed mechanisms by which the gases were formed. These studies have resulted in the postulation of a series of reactions that account for many of the observed products, but which involve several reactions for which there is limited, or no, precedent. For example, Al(OH)4 has been postulated to function as a Lewis acid to catalyze the reaction of nitrite ion with the metal complexants, NO is proposed as an intermediate, and the ratios of gaseous products may be a result of the partitioning of NO between two or more reactions. These reactions and intermediates have been the focus of this project since its inception in 1996.

E. Kent Barefield; Charles L. Liotta; Henry M. Neumann

2002-04-08T23:59:59.000Z

317

Nuclear / Radiological Advisory Team | National Nuclear Security  

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

/ Radiological Advisory Team | National Nuclear Security / Radiological Advisory Team | 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 Nuclear / Radiological Advisory Team Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations > Nuclear / Radiological Advisory Team Nuclear / Radiological Advisory Team

318

Nuclear Chirality  

Science Conference Proceedings (OSTI)

Nuclear chirality is a novel manifestation of spontaneous symmetry breaking resulting from an orthogonal coupling of angular momentum vectors in triaxial nuclei. Three perpendicular angular momenta can form two systems of opposite handedness; the time reversal operator

Krzysztof Starosta

2005-01-01T23:59:59.000Z

319

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Table 21. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2008-2012

320

Nuclear Deterrence  

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

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

Note: This page contains sample records for the topic "nuclear operations related" 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

U.S. Nuclear Regulatory  

E-Print Network (OSTI)

Consultation correspondence related to the evaluation of the renewal of the operating license | for Vermont Yankee Nuclear Power Station (VYNPS) is identified in Table E-1. Copies of the correspondence are included at the end of this appendix. The licenses, permits, consultations, and other approvals obtained from Federal and State | authorities for VYNPS are listed in Table E-2.

Commission (r. L. Franovich; U. S. Fish; Wildlife Service; U. S. Fish; Wildlife Service

2006-01-01T23:59:59.000Z

322

Nuclear Operations Application to Environmental Restoration at Corrective Action Unit 547, Miscellaneous Contaminated Waste Sites, at the Nevada National Security Site  

SciTech Connect

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has responsibility for environmental restoration at the Nevada National Security Site (formerly the Nevada Test Site). This includes remediation at locations where past testing activities have resulted in the release of plutonium to the environment. One of the current remediation efforts involves a site where an underground subcritical nuclear safety test was conducted in 1964. The underground test was vented through a steel pipe to the surface in a closed system where gas samples were obtained. The piping downstream of the gas-sampling apparatus was routed belowground to a location where it was allowed to vent into an existing radioactively contaminated borehole. The length of the pipe above the ground surface is approximately 200 meters. This pipe remained in place until remediation efforts began in 2007, at which time internal plutonium contamination was discovered. Following this discovery, an assessment was conducted to determine the quantity of plutonium present in the pipe. This site has been identified as Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites. The quantity of plutonium identified at CAU 547 exceeded the Hazard Category 3 threshold but was below the Hazard Category 2 threshold specified in DOE Standard DOE-STD-1027-92. This CAU, therefore, was initially categorized as a Hazard Category 3 environmental restoration site. A contaminated facility or site that is initially categorized as Hazard Category 3, however, may be downgraded to below Hazard Category 3 if it can be demonstrated through further analysis that the form of the material and the energy available for release support reducing the hazard category. This is an important consideration when performing hazard categorization of environmental restoration sites because energy sources available for release of material are generally fewer at an environmental restoration site than at an operating facility and environmental restoration activities may result in the complete removal of source material.

Kevin Cabble (NSO), Mark Krauss and Patrick Matthews (N-I)

2011-03-03T23:59:59.000Z

323

The Office of Nuclear Detonation Detection (NDD) | National Nuclear...  

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

of Nuclear Detonations: Develops and builds space sensors for the nation's operational nuclear test treaty monitoring and Integrated Threat WarningAttack Assessment...

324

Analysis of environmental issues related to small-scale hydroelectric development. VI. Dissolved oxygen concentrations below operating dams  

DOE Green Energy (OSTI)

Results are presented of an effort aimed at determining whether or not water quality degradation, as exemplified by dissolved oxygen concentrations, is a potentially significant issue affecting small-scale hydropower development in the US. The approach was to pair operating hydroelectric sites of all sizes with dissolved oxygen measurements from nearby downstream US Geological Survey water quality stations (acquired from the WATSTORE data base). The USGS data were used to calculate probabilities of non-compliance (PNCs), i.e., the probabilities that dissolved oxygen concentrations in the discharge waters of operating hydroelectric dams will drop below 5 mg/l. PNCs were estimated for each site, season (summer vs remaining months), and capacity category (less than or equal to 30 MW vs >30 MW). Because of the low numbers of usable sites in many states, much of the subsequent analysis was conducted on a regional basis. During the winter months (November through June) all regions had low mean PNCs regardless of capacity. Most regions had higher mean PNCs in summer than in winter, and summer PNCs were greater for large-scale than for small-scale sites. Among regions, the highest mean summer PNCs were found in the Great Basin, the Southeast, and the Ohio Valley. To obtain a more comprehensive picture of the effects of season and capacity on potential dissolved oxygen problems, cumulative probability distributions of PNC were developed for selected regions. This analysis indicates that low dissolved oxygen concentrations in the tailwaters below operating hydroelectric projects are a problem largely confined to large-scale facilities.

Cada, G.F.; Kumar, K.D.; Solomon, J.A.; Hildebrand, S.G.

1982-01-01T23:59:59.000Z

325

Internships Give Nuclear Technician Students Hands-on Experience...  

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

in ESTEC's nuclear operations technician program. "It's been amazing. I work with reactor operators and attend the same training that qualifies them to operate nuclear...

326

Simulation of operational transients in a VVER-1000 nuclear power plant using the RELAP5/MOD3.2 computer program  

E-Print Network (OSTI)

A RELAP5/MOD3.2 nodalization model of a VVER-1OOO (V-320) nuclear power plant was updated, improved and validated against available experimental data. The data included integrated test results obtained from actual power plant testing. The steady state and the operational transients test data describe the behavior of the Unit 5 of Kozloduy NPP (Bulgaria). The operational transients consisted of a loss of flow caused by the successive trip of two main coolant pumps without reactor scram. A validation process of the developed model has been performed in two stages comprising an initial and a transient validation. The comparison between experimental data and calculation results proved the adequacy of the model and also the code capacity to reproduce main plant parameter evolutions. The plant model was also used for a preliminary analysis of a large break loss of coolant accident (LB LOCA) which is the design basis accident (DBA) for the VVER-1000 plants. Due to the limitations of the utilized code version (unavailability of the redwood model), only the first stage (blowdown) of the accident was investigated. The results have been compared with similar calculations obtained by the Russian specialists with an indigenous thermal-hydraulic code (TECH-M). The comparison showed a good agreement. For the most important calculated parameter (hot spot cladding temperature) an uncertainty analysis using the response surface method was performed. The nodalization model seems to be adequate for the class of transients and accidents investigated, but the inclusion of the reactor specific point kinetics parameters, emergency headwater system model and updating some of the component parameters (e.g. main coolant pump friction) will increase its area of applicability.

Moscalu, Dionisie Radu

1999-01-01T23:59:59.000Z

327

EIS-0426: Site-Wide Environmental Impact Statement for Continued Operation of the Department of Energy / National Nuclear Security Administration Nevada National Security Site and Off-Site Locations in the State of Nevada  

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

This Site-Wide EIS evaluates the potential environmental impacts of proposed alternatives for continued management and operation of the Nevada National Security Site (NNSS) (formerly known as the Nevada Test Site) and other U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA)-managed sites in Nevada.

328

Innovations in Nuclear Infrastructure  

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

Innovations in Nuclear Infrastructure Innovations in Nuclear Infrastructure and Education (INIE) Innovations in Nuclear Infrastructure and Education (INIE) Presented to the Nuclear Energy Research Advisory Committee Crystal City, Virginia John Gutteridge Director, University Programs Office of Nuclear Energy, Science and Technology September 30 - October 1, 2002 Office of Nuclear Energy, Science and Technology Gutteridge/Sep-Oct_02 INIE-NERAC.ppt (2) INIE The Stimuli .... INIE The Stimuli .... 6 Declining number of operating university research/training reactors 6 Dwindling student population in nuclear engineering 6 Closing or loss of identity of university nuclear engineering programs 6 Looming shortage of nuclear engineering graduates 6 Threat of additional reactor closures -- Cornell, Michigan, MIT

329

Operation Redwing-Project 6. 4. Airborne antennas and phototubes for determination of nuclear-weapon yield. Report for May-July 1956  

SciTech Connect

Airborne equipment was designed for determining the location and yield of a nuclear detonation. This equipment determines yield from a measurement of the interval between the time of the burst and the time of the second peak in the thermal-radiation intensity curve. Flush-mounted ferrite-core magnetic loop antennas for use in detecting the electromagnetic signal and thus fixing the time of the burst, performed successfully during Operation Redwing. Two kinds of photocubes for detecting the second thermal peak were tested and were found about equally satisfactory. The method selected for yield determination gave results accurate + or - 16% for five shots. Detailed study of the data showed that the electromagnetic signal, consisting of a direct pulse followed by a series of ionosphere-reflected sky waves, could be used in many waves to give information concerning the detonation and the ionsphere. From the time intervals between the ground wave and sky waves, it was foun possible to compute both the distance between and receiver and the height of the reflecting ionosphere layer.

Waters, A.J.; Clapp, R.E.

1985-04-01T23:59:59.000Z

330

Collaborating Organizations - Nuclear Data Program, Nuclear Engineering  

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

Collaborating Organizations Collaborating Organizations Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program Collaborating Organizations Bookmark and Share National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York. International Nuclear Structure and Decay Data Network, coordinated by IAEA, Vienna, Austria Heavy-Ion Nuclear Physics Group, Physics Division, Argonne National Laboratory, Argonne, Illinois. Nuclear Spectroscopy Group, Department of Nuclear Physics,

331

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

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

Data Program Data Program Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies. Bookmark and Share Recent Events Nuclear Structure 2012 Conference Argonne National Laboratory hosted the

332

EIS-0225: Continued Operation of the Pantex Plant and Associated...  

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

5: Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components EIS-0225: Continued Operation of the Pantex Plant and Associated Storage of Nuclear...

333

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

334

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

335

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

U.S. Energy Information Administration (EIA) Indexed Site

Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

336

Arkansas Nuclear Profile - Arkansas Nuclear One  

U.S. Energy Information Administration (EIA) Indexed Site

Nuclear One" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

337

Nuclear / Radiological Advisory Team | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

advice for both domestic and international nuclear or radiological incidents. It is led by a Senior Energy Official who runs the NNSA field operation and who coordinates NNSA...

338

Home Office Expenses Submitted by Fluor Federal Services, Inc., on Savannah River Nuclear Solutions, LLC's U.S. Department of Energy Management & Operating (M&O) Contract No. DE-AC09-08SR22470  

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

Home Office Expenses Submitted by Fluor Home Office Expenses Submitted by Fluor Federal Services, Inc., on Savannah River Nuclear Solutions, LLC's U.S. Department of Energy Management & Operating (M&O) Contract No. DE-AC09-08SR22470 OAS-L-13-08 April 2013 Department of Energy Washington, DC 20585 April 19, 2013 MEMORANDUM FOR THE MANAGER, SAVANNAH RIVER OPERATIONS OFFICE FROM: Rickey R. Hass Deputy Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Home Office Expenses Submitted by Fluor Federal Services, Inc., on Savannah River Nuclear Solutions, LLC's U.S. Department of Energy Management & Operating (M&O) Contract No. DE-AC09-08SR22470" BACKGROUND The attached report presents the results of an audit of home office expenses submitted by Fluor

339

Preparation of design specifications and design reports for pumps, valves, piping, and piping supports used in safety-related portions of nuclear power plants  

SciTech Connect

Section III of the ASME Boiler and Pressure Vessel Code requires the preparation of Design Specifications and Design Reports as part of the design process leading to construction of a nuclear power plant, in compliance with provisions of Title 10 of the Code of Federal Regulations (10 CFR). Guidelines for preparing this documentation are contained in nonmandatory Appendixes B and C of the ASME Code. This report gives an in-depth review of the ASME Code requirements and guidance, beginning with the first edition of the Code in 1963 through the 1983 edition, Summer 1985 Addenda. Recommendations for substantial revisions to the Code are presented based on the authors experience in conducting design documentation audits of pumps, valves, piping, and piping supports for nuclear power plants undergoing Nuclear Regulatory Commission (NRC) review for Operating Licenses. It is concluded that adequate Design Specifications and Design Reports are absolutely necessary for the normal operating life of a plant and are vital if plant life extension is planned.

Rodabaugh, E.C.; Moore, S.E.

1987-06-01T23:59:59.000Z

340

Nuclear Nonproliferation Program Offices | National Nuclear Security  

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

Nonproliferation Program Offices | National Nuclear Security Nonproliferation Program Offices | 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 Nuclear Nonproliferation Program Offices Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices Nuclear Nonproliferation Program Offices One of the gravest threats the United States and the international

Note: This page contains sample records for the topic "nuclear operations related" 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

Nuclear Nonproliferation Program Offices | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Nonproliferation Program Offices | National Nuclear Security Nonproliferation Program Offices | 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 Nuclear Nonproliferation Program Offices Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices Nuclear Nonproliferation Program Offices One of the gravest threats the United States and the international

342

Operating Experience Level 1: Improving Department of Energy Capabilities  

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

Operating Experience Level 1: Improving Department of Energy Operating Experience Level 1: Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events, April 2013 Operating Experience Level 1: Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events, April 2013 PURPOSE: The purpose of this Operating Experience (OE) document is to (1) provide results from U.S. Department of Energy (DOE), including the National Nuclear Security Administration, initiatives related to beyond design basis events (BDBEs), and (2) provide direction for enhancing capabilities for mitigating BDBEs at DOE sites. BACKGROUND: After the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to BDBEs. These initiatives

343

Operating Experience Level 1: Improving Department of Energy Capabilities  

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

Operating Experience Level 1: Improving Department of Energy Operating Experience Level 1: Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events Operating Experience Level 1: Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events PURPOSE: The purpose of this Operating Experience (OE) document is to (1) provide results from U.S. Department of Energy (DOE), including the National Nuclear Security Administration, initiatives related to beyond design basis events (BDBEs), and (2) provide direction for enhancing capabilities for mitigating BDBEs at DOE sites. BACKGROUND: After the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to BDBEs. These initiatives

344

Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000  

Science Conference Proceedings (OSTI)

This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

None

2001-03-01T23:59:59.000Z

345

Life Cycle Management Planning at V.C. Summer Nuclear Plant: Main Condenser, Radiation Monitoring System, and Nuclear Safety-Related HVAC Chilled Water  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes very important to keep the plant economically viable throughout its remaining licensed operating term (either a 40-year or 60-year term). This report provides the industry with lessons learned from applying the EPRI LCM planning process to three SSCs at V.C. Summer Generating Station.

2001-12-21T23:59:59.000Z

346

Executive Director for Operations OPTIONS FOR U.S. NUCLEAR REGULATORY COMMISSION INVOLVEMENT WITH THE NAVYS REMEDIATION OF THE  

E-Print Network (OSTI)

To obtain Commission approval on options for the U.S. Nuclear Regulatory Commissions (NRCs) involvement with the Navys remediation of the Hunters Point Naval Shipyard (HPS) site, and recommended actions to inform the U.S. Environmental Protection Agency (EPA), the Navy, and stakeholders about the Commissions decision regarding NRCs involvement. This paper does not address any new commitments. SUMMARY: In July 2007 the Navy requested that NRC clarify the potential for NRC involvement with the remediation of the HPS site in San Francisco, California. The Navy explained that resolving uncertainties about NRC jurisdiction and involvement is important because of the potential impact on the Navys ongoing remediation and expedited schedules needed to support the redevelopment plans of the City of San Francisco for the site. These redevelopment plans and schedules have high visibility and considerable support from elected Federal, State, and local officials. In response to the Navys request, the staff has evaluated three options for NRCs involvement at the HPS and related policy issues. The staff recommends the option of relying CONTACT:

R. W. Borchardt; Robert L. Johnson

2008-01-01T23:59:59.000Z

347

10 CFR Part 830, Nuclear Safety Management  

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

construction such as environmental restoration activities, decontamination and decommissioning activities, specific nuclear explosives operations, or transition...

348

Assessment of Electromagnetic Interference Events in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report presents a study and analysis of reported electromagnetic interference (EMI-) related incidents in nuclear power plants. These incidents were gathered primarily from the total body of incidents reported to the Institute of Nuclear Power Operations (INPO) database, with a few incidents coming from U.S. Nuclear Regulatory Commission (NRC) reports. This report analyzes trends and common factors in these events. The analysis is intended to inform the estimation of risk from EMI and offer suggesti...

2011-12-23T23:59:59.000Z

349

U.S. Nuclear Power Plants: Continued Life or Replacement After 60? (released in AEO2010)  

Reports and Publications (EIA)

Nuclear power plants generate approximately 20 percent of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of GHG regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating.

Information Center

2010-05-11T23:59:59.000Z

350

Proceedings of the eighth symposium on training of nuclear facility personnel  

Science Conference Proceedings (OSTI)

This conference brought together those persons in the nuclear industry who have a vital interest in the training and licensing of nuclear reactor and nuclear fuel processing plant operators, senior operators, and support personnel for the purpose of an exchange of ideas and information related to the various aspects of training, retraining, examination, and licensing. The document contains 64 papers; each paper was abstracted for the data.

Not Available

1989-04-01T23:59:59.000Z

351

REACTOR OPERATIONS AND CONTROL  

E-Print Network (OSTI)

of Neural Networks to the Operations of Nuclear Power Plants," Nucl. Safety, 32, 68 ~1991!. 3. I. PÁZSIT detectors.1 According to the technical specifications of the Ring- hals power plant, in which this work and the "distorted" axial flux shape, and from the latter, *Current address: The Swedish Nuclear Power Inspectorate

Pázsit, Imre

352

Public comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Volume 1  

SciTech Connect

This report documents the Nuclear Regulatory Commission (NRC) staff review of public comments provided in response to the NRC`s proposed amendments to 10 Code of Federal Regulations (CFR) Part 51, which establish new requirements for the environmental review of applications for the renewal of operating licenses of nuclear power plants. The public comments include those submitted in writing, as well as those provided at public meetings that were held with other Federal agencies, State agencies, nuclear industry representatives, public interest groups, and the general public. This report also contains the NRC staff response to the various concerns raised, and highlights the changes made to the final rule and the supporting documents in response to these concerns.

NONE

1996-05-01T23:59:59.000Z

353

Plant Engineering: Performance Diagnostic Test Program for the Nuclear Turbine Cycle at Korea Hydro & Nuclear Power Company  

Science Conference Proceedings (OSTI)

Currently, many power generating companies are challenged to reduce operating costs, and at the same time, the cost of unit unavailability can be significant in today's power markets. In the past decade, management of nuclear power plants, including Korea Hydro & Nuclear Power (KHNP), has been focused on reducing forced outage rates and nuclear-safety-related issues, with less attention paid to thermal performance. But recently, KHNP has been strongly challenged to increase unit thermal performance, as f...

2012-02-28T23:59:59.000Z

354

Operations Directorate (OPS Directorate)  

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

Operations Directorate (OPS Directorate) Operations Directorate (OPS Directorate) Purpose A group chartered by the Associate Laboratory Director for the Advanced Photon Source that includes the responsible Division Directors and other appropriate APS operations personnel. The Operations Directorate collectively coordinates operating decisions that affect the facility as a whole and establishes both long- and short-term schedules, including scheduled maintenance and facility improvement periods. The Operations Directorate is the APS forum in which decisions regarding operations are discussed: These include, but are not limited to: Safety issues related to operations Operational Schedule Global operating parameters within the defined and approved operational and safety envelopes, such as energy, maximum circulating beam

355

Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1  

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

Safety and Security Safety and Security Report to the Secretary on the Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1 February 2011 Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS Table of Contents 1.0 Introduction ......................................................................................................................... 1 2.0 Department-wide Action Plan for the Columbia Accident and Davis-Besse Event ........... 3 3.0 Comprehensive Operating Experience Program ................................................................. 5

356

Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1  

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

Safety and Security Safety and Security Report to the Secretary on the Status and Effectiveness of DOE Efforts to Learn from Internal and External Operating Experience in Accordance with Commitment #20 of the DOE Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2004-1 February 2011 Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS Table of Contents 1.0 Introduction ......................................................................................................................... 1 2.0 Department-wide Action Plan for the Columbia Accident and Davis-Besse Event ........... 3 3.0 Comprehensive Operating Experience Program ................................................................. 5

357

NIF's Operations Support Building awarded LEED certification...  

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

NIF's Operations Support Building awarded LEED certification | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

358

List of currently classified documents relative to Hanford Operations and of potential use in the Columbia River Comprehensive Impact Assessment, January 1, 1973--June 20, 1994  

Science Conference Proceedings (OSTI)

The Columbia River Comprehensive Impact Assessment (CRCIA) Project seeks to estimate the current risk from the Columbia River resulting from past and present Hanford activities. To resolve the question of the current risk, it is necessary for the CRCIA Project to have access to any classified information that may be relevant to this study. The purpose of this report is to present the results of the search for relevant classified information. There are two classified matter control centers operated by two prime contractors at the Hanford Site. One is operated by Pacific Northwest Laboratory (PNL) and the other is operated by Westinghouse Hanford Company (WHC). Only the WHC collection contained information relevant to a study of the Columbia River in the time frame of interest: January 1, 1973 through June 20, 1994. A list of the classified documents in the WHC collection is maintained in the WHC Classified Document Control database. The WHC Classified Document Control database was searched. The search criteria were the dates of interest and the basic keywords used for the CRCIA Project`s data compendium (Eslinger et al. 1994). All Hanford-generated, Hanford-related entries that were applicable to the CRCIA Project and the dates of interest were provided. The resulting list of 477 titles comprises the Appendix of this report. The information give for each title is exactly as it appears in the database. Any inconsistencies are the result of duplicating the database.

Miley, T.B.; Huesties, L.R.

1995-02-01T23:59:59.000Z

359

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

Nuclear Reactor Operational Status Tables (Information and data on nuclear power reactors Generation: by State and Reactor. Annual Energy Review, ...

360

Human Factors Engineering for Managers: Computer-Based Training for Utilities Involved in New Nuclear Power Plant Designs, Construct ion and Operation - 2012  

Science Conference Proceedings (OSTI)

This product provides a computer-based training (CBT) course in human factors engineering (HFE) for managers. The training materials for this course were developed to provide a foundation in HFE for managers at utilities involved in new nuclear power plants (NPPs). This course will help managers who may be expected to manage the interactions with the vendor and U.S. Nuclear Regulatory Commission (USNRC) during new plant design certification, detailed design and implementation, and development of procedur...

2012-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

Office of Nuclear Threat Science | National Nuclear Security Administration  

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

Nuclear Threat Science | National Nuclear Security Administration Nuclear Threat Science | 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 The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

362

Guidance for evaluation of operational emergency plans  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide guidance for development of emergency plans for the USDOE Office of Defense Programs, Office of Energy Research, and Office of Environmental Management facilities. It gathers emergency planning policy and guidance from applicable federal regulations, DOE Orders and related guidance documents. This material, along with recommended good practices, is presented as a checklist against which emergency plans can be reviewed by DOE Headquarters. The Office of Emergency Response (DP-23), Office of Environment, Safety and Health Technical Support (ER-8), and Office of Transportation, Emergency Management and Analytical Services (EM-26) will use this checklist to evaluate plans submitted by DP, ER, and EM field elements. The scope of this document encompasses plans for operational emergencies at DOE facilities, both nuclear and non-nuclear. Operational emergencies, as defined in Attachment 2 to DOE Order 5500.1B (April 30, 1991) are ``significant accidents, incidents, events, or natural phenomena which seriously degrade the safety or security of DOE facilities. Operational Emergencies apply to DOE reactors and other DOE facilities (nuclear and non-nuclear) involved with hazardous materials; DOE-controlled nuclear weapons, components, or test devices; DOE safeguards and security events; and transportation accidents involving hazardous materials under DOE control.``

NONE

1995-03-01T23:59:59.000Z

363

LANL continuity of operations plan  

SciTech Connect

The Los Alamos National Laboratory (LANL) is a premier national security research institution, delivering scientific and engineering solutions for the nation's most crucial and complex problems. Our primary responsibility is to ensure the safety, security, and reliability of the nation's nuclear stockpile. LANL emphasizes worker safety, effective operational safeguards and security, and environmental stewardship, outstanding science remains the foundation of work at the Laboratory. In addition to supporting the Laboratory's core national security mission, our work advances bioscience, chemistry, computer science, earth and environmental sciences, materials science, and physics disciplines. To accomplish LANL's mission, we must ensure that the Laboratory EFs continue to be performed during a continuity event, including localized acts of nature, accidents, technological or attack-related emergencies, and pandemic or epidemic events. The LANL Continuity of Operations (COOP) Plan documents the overall LANL COOP Program and provides the operational framework to implement continuity policies, requirements, and responsibilities at LANL, as required by DOE 0 150.1, Continuity Programs, May 2008. LANL must maintain its ability to perform the nation's PMEFs, which are: (1) maintain the safety and security of nuclear materials in the DOE Complex at fixed sites and in transit; (2) respond to a nuclear incident, both domestically and internationally, caused by terrorist activity, natural disaster, or accident, including mobilizing the resources to support these efforts; and (3) support the nation's energy infrastructure. This plan supports Continuity of Operations for Los Alamos National Laboratory (LANL). This plan issues LANL policy as directed by the DOE 0 150.1, Continuity Programs, and provides direction for the orderly continuation of LANL EFs for 30 days of closure or 60 days for a pandemic/epidemic event. Initiation of COOP operations may be required to support an allhazards event, including a national security emergency, major fire, catastrophic natural disaster, man-made disaster, terrorism event, or technological disaster by rendering LANL buildings, infrastructure, or Technical Areas unsafe, temporarily unusable, or inaccessible.

Senutovitch, Diane M [Los Alamos National Laboratory

2010-12-22T23:59:59.000Z

364

Nuclear Shadowing and Diffraction  

E-Print Network (OSTI)

The relation between diffraction in lepton-proton collisions and shadowing of nuclear structure functions which arises from Gribov inelastic shadowing, is described. A model realizing such relation, which produces a parameter-free description of experimental data on nuclear structure functions at small $x$, is presented. The application to the description of multiplicities in nuclear collisions is discussed and related to other approaches.

J. L. Albacete; N. Armesto; A. Capella; A. B. Kaidalov; C. A. Salgado

2004-10-12T23:59:59.000Z

365

ENDF-related Nuclear Data from the T-2 Group (T-2 Nuclear Information Service) at Los Alamos National Laboratory (LANL)  

DOE Data Explorer (OSTI)

Each of these sections of the website is an index to the contents of the specifically named ENDF/B-VII library of data. Links in each index provide access to more information about the individual materials, including raw and interpreted views of the ENDF file, and PDF plots of the cross sections and distributions. Also provided is a section of information and graphs related to the Energy Balance of ENDF/B-VII and table of neutron Kerma data. [Information taken from http://t2.lanl.gov/data/data.html

None

366

Nuclear Security Enterprise | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Enterprise | National Nuclear Security Administration Enterprise | 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 Nuclear Security Enterprise Home > About Us > Our Programs > Defense Programs > Nuclear Security Enterprise Nuclear Security Enterprise The Nuclear Security Enterprise (NSE) mission is to ensure the Nation sustains a safe, secure, and effective nuclear deterrent through the

367

NNSA Selects Consolidated Nuclear Security, LLC to Manage the...  

National Nuclear Security Administration (NNSA)

Consolidated Nuclear Security, LLC to Manage the Consolidated Contract for Nuclear Production Operations | National Nuclear Security Administration Our Mission Managing the...

368

Welcome to the NNSA Production Office | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Consolidated Nuclear Security, LLC to Manage the Consolidated Contract for Nuclear Production Operations The National Nuclear Security Administration (NNSA) today announced...

369

Energy and Security in Northeast Asia: Proposals for Nuclear Cooperation  

E-Print Network (OSTI)

experience in decommissioning its former nuclear-poweredfor decommissioning and decontamination of nuclear vessels.nuclear technology: design, procurement, equipment manufacturing, construction, installation, start up, operation and decommissioning.

Kaneko, Kumao; Suzuki, Atsuyuki; Choi, Jor-Shan; Fei, Edward

1998-01-01T23:59:59.000Z

370

Nuclear Safety Enforcement Documents | Department of Energy  

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

Enforcement » Nuclear Safety Enforcement Documents Enforcement » Nuclear Safety Enforcement Documents Nuclear Safety Enforcement Documents Documents Available for Download July 22, 2013 Enforcement Letter, NEL-2013-03 Issued to Lawrence Livermore National Security, LLC related to Programmatic Deficiencies in the Software Quality Assurance Program at the Lawrence Livermore National Laboratory February 12, 2013 Enforcement Letter, NEL-2013-02 Issued to Los Alamos National Security, LLC related to a Radiological Contamination Event at the Los Alamos Neutron Science Center at Los Alamos National Laboratory January 7, 2013 Enforcement Letter, NEL-2013-01 Issued to B&W Pantex, LLC related to the Conduct of Nuclear Explosive Operations at the Pantex Plant October 23, 2012 Enforcement Letter, Controlled Power Company - WEL-2012-02

371

NUCLEAR SCIENCE ANNUAL REPORT 1977-1978  

E-Print Network (OSTI)

A Relation Between Nuclear Dynamics and the RenormalizationMultiplicity Distributions in Nuclear Collision M. GyulassyHigh Energy Nuclear Collisions in the Resonance Dominated

Schroeder, L.S.

2011-01-01T23:59:59.000Z

372

Qualification of the Framatome ANP TXS Digital Safety I&C System - Revision to EPRI TR-114017: Compliance with EPRI TR-107330, "Gene ric Requirements Specification for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear P..  

Science Conference Proceedings (OSTI)

As its nuclear power plants age, the electric power industry is focusing on developing cost-effective replacement systems for obsolete instrumentation, control, and safety systems. This report describes the generic qualification of a platform for safety-related applications that incorporates programmable logic controllers (PLCs), a technology with an excellent track record in non-nuclear applications for critical control and safety functions.

2002-07-16T23:59:59.000Z

373

Materials for Nuclear Power: Digital Resource Center -- Articles and ...  

Science Conference Proceedings (OSTI)

... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science, Nuclear Engineering ... BOOK: Safety Related Issues of Spent Nuclear Fuel Storage ... A compilation of reports prepared by the Center for Nuclear Waste Regulatory...

374

NUCLEAR REACTOR CONTROL SYSTEM  

DOE Patents (OSTI)

A control system is described for a nuclear reactor using enriched uranium fuel of the type of the swimming pool and other heterogeneous nuclear reactors. Circuits are included for automatically removing and inserting the control rods during the course of normal operation. Appropriate safety circuits close down the nuclear reactor in the event of emergency.

Epler, E.P.; Hanauer, S.H.; Oakes, L.C.

1959-11-01T23:59:59.000Z

375

Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are collaborating to develop seismic capability evaluation technology for degraded structures and passive components (SPCs) under a multi-year research agreement. To better understand the status and characteristics of degradation of SPCs in nuclear power plants (NPPs), the first step in this multi-year research effort was to identify and evaluate degradation occurrences of SPCs in U.S. NPPs. This was performed by reviewing recent publicly available information sources to identify and evaluate the characteristics of degradation occurrences and then comparing the information to the observations in the past. Ten categories of SPCs that are applicable to Korean NPPs were identified, comprising of anchorage, concrete, containment, exchanger, filter, piping system, reactor pressure vessel, structural steel, tank, and vessel. Software tools were developed to expedite the review process. Results from this review effort were compared to previous data in the literature to characterize the overall degradation trends.

Nie,J.; Braverman, J.; Hofmayer, C.; Choun, Y.-S.; Kim, M.K.; Choi, I.-K.

2009-04-02T23:59:59.000Z

376

The Office of Nuclear Verification | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Nuclear Verification | National Nuclear Security Nuclear Verification | 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 The Office of Nuclear Verification Home > About Us > Our Programs > Nonproliferation > Nonproliferation & International Security > The Office of Nuclear Verification The Office of Nuclear Verification

377

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security Eisenhower Halts Nuclear Weapons Testing | 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 > About Us > Our History > NNSA Timeline > Eisenhower Halts Nuclear Weapons Testing Eisenhower Halts Nuclear Weapons Testing August 22, 1958 Washington, DC Eisenhower Halts Nuclear Weapons Testing

378

Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999  

Science Conference Proceedings (OSTI)

This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board`s Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department`s needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation.

Rutherford, D.

1994-03-01T23:59:59.000Z

379

Table 8.1 Nuclear Energy Overview  

U.S. Energy Information Administration (EIA)

"Operable Nuclear Reactors," at end of section. Nuclear electricity net generation totals may not equal sum of components due to independent rounding.

380

Nuclear Security | National Nuclear Security Administration  

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

| National Nuclear Security Administration | 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 Nuclear Security Home > About Us > Our Programs > Nuclear Security Nuclear Security The Office of Defense Nuclear Security (DNS) is responsible for the development and implementation of security programs for NNSA. In this capacity, DNS is the NNSA line management organization responsible for

Note: This page contains sample records for the topic "nuclear operations related" 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

Nuclear Security 101 | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

101 | National Nuclear Security Administration 101 | 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 > Nuclear Security 101 Fact Sheet Nuclear Security 101 Mar 23, 2012 The goal of United States Government's nuclear security programs is to prevent the illegal possession, use or transfer of nuclear material,

382

Nuclear Security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

| National Nuclear Security Administration | 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 Nuclear Security Home > About Us > Our Programs > Nuclear Security Nuclear Security The Office of Defense Nuclear Security (DNS) is responsible for the development and implementation of security programs for NNSA. In this capacity, DNS is the NNSA line management organization responsible for

383

Nuclear Security 101 | National Nuclear Security Administration  

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

101 | National Nuclear Security Administration 101 | 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 > Nuclear Security 101 Fact Sheet Nuclear Security 101 Mar 23, 2012 The goal of United States Government's nuclear security programs is to prevent the illegal possession, use or transfer of nuclear material,

384

Nuclear reactions and synthesis of new transuranium species  

Science Conference Proceedings (OSTI)

In this short review, I shall describe the special aspects of heavy ion nuclear reaction mechanisms operative in the transuranium region, the role of new techniques, possible nuclear reactions for the production of additional transuranium elements and nuclear species and the importance of work in this region for the development of nuclear models and theoretical concepts. This discussion should make it clear that a continuing supply of leements and isotopes, some fo them relatively short-lived, produced by the HFIR-TRU facilities, will be a requirement for future synthesis of new elements and isotopes.

Seaborg, G.T.

1983-01-01T23:59:59.000Z

385

DE-SOL-0003174 Critical Capabilities for Emergency Operations  

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

3174 Critical Capabilities for Emergency Operations 3174 Critical Capabilities for Emergency Operations Training Academy (EOTA) Support 1. Interested parties shall have experience in: a. Developing training for emergency operations type programs such as response to radiological or nuclear incidents, emergency management and preparation, exercises (full scale through table top), continuity of operations, or other related programs, b. Coordinating consultants and instructional design staff to integrate content provided by the consultants with the course development process employed by instructional designers for technical training development, c. conducting comprehensive analyses such as needs assessments, training effectiveness evaluations, job analyses, functional analyses, task analyses, etc.,

386

Dry cooling tower operating experience in the LOFT reactor  

SciTech Connect

A dry cooling tower has been uniquely utilized to dissipate heat generated in a small experimental pressurized water nuclear reactor. Operational experience revealed that dry cooling towers can be intermittently operated with minimal wind susceptibility and water hammer occurrences by cooling potential steam sources after a reactor scram, by isolating idle tubes from the external atmosphere, and by operating at relatively high pressures. Operating experience has also revealed that tube freezing can be minimized by incorporating the proper heating and heat loss prevention features.

Hunter, J.A.

1980-01-01T23:59:59.000Z

387

Nuclear Power 2010 Program Dominion Virginia Power Cooperative Project U.S. Department of Energy Cooperative Agreement DE-FC07-05ID14635 Construction and Operating License Demonstration Project Final Report  

Science Conference Proceedings (OSTI)

This report serves to summarize the major activities completed as part of Virginia Electric and Power Company's North Anna construction and operating license demonstration project with DOE. Project successes, lessons learned, and suggestions for improvement are discussed. Objectives of the North Anna COL project included preparation and submittal of a COLA to the USNRC incorporating ESBWR technology for a third unit a the North Anna Power Station site, support for the NRC review process and mandatory hearing, obtaining NRC approval of the COLA and issuance of a COL, and development of a business case necessary to support a decision on building a new nuclear power plant at the North Anna site.

Eugene S. Grecheck David P. Batalo

2010-11-30T23:59:59.000Z

388

Task 23 - background report on subsurface environmental issues relating to natural gas sweetening and dehydration operations. Topical report, February 1, 1994--February 28, 1996  

Science Conference Proceedings (OSTI)

This report describes information pertaining to environmental issues, toxicity, environmental transport, and fate of alkanolamines and glycols associated with natural gas sweetening and dehydration operations. Waste management associated with the operations is also discussed.

Sorensen, J.A.

1998-12-31T23:59:59.000Z

389

Public opinion factors regarding nuclear power  

Science Conference Proceedings (OSTI)

This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry`s practices are aligned with public opinion, a more favorable regulatory climate is possible.

Benson, B.

1991-12-31T23:59:59.000Z

390

Public opinion factors regarding nuclear power  

SciTech Connect

This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible.

Benson, B.

1991-01-01T23:59:59.000Z

391

Guidelines for the Qualification of Insulation Systems for Use in Rewinding Nuclear Safety-Related Harsh Environment Motors  

Science Conference Proceedings (OSTI)

This document provides guidance on the selection, procurement, acceptance, and dedication of the insulating materials used during the rewinding of environmentally qualified (EQ) motors located in plant harsh environment areas. This guideline is the third in a series of documents published by EPRI to facilitate the repair of safety-related motors.

1997-01-22T23:59:59.000Z

392

DOE Names Interim Manager for Idaho Operations Office  

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

Interim Manager for Idaho Operations Office Dennis Miotla, the Office of Nuclear Energy's Deputy Assistant Secretary Dennis Miotla for Nuclear Power Deployment, has been named the...

393

Lempke receives Sandia Emergency Operations Center tour | National...  

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

receives Sandia Emergency Operations Center tour | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

394

JGI - Operations  

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

Operations The Operations Department sees to it that JGI has the best possible facilities and support, ensuring that its operations are conducted in accordance with the...

395

Power Operations  

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

Power Operations Outage Coordination Standards of Conduct Transmission Planning You are here: SN Home page > Power Operations Power Operations Western's Sierra Nevada Region...

396

AIRCRAFT NUCLEAR PROPULSION DEPARTMENT NUCLEAR SAFETY GUIDE  

SciTech Connect

The limitations and operating techniques which were in effect at ANPD for the prevention of criticality accidents are summarized. The standards followed by the atomic industry were followed; however, the safe mass of U/sup 235/ moderated with beryllium oxide and hydrogeneous materials was based upon criticality experiments conducted at ANPD. Although the guide was primarily for the use of the ANPD nuclear safety control organization, it may also be of assistance to designers and operating management in maintaining nuclear safety. (auth)

Pryor, W.A.

1961-06-01T23:59:59.000Z

397

Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature. [Once-through Cycle and Plutonium Recycle  

Science Conference Proceedings (OSTI)

The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included.

Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

1982-10-01T23:59:59.000Z

398

Nuclear Regulatory Commission Information Digest 1994 edition. Volume 6  

SciTech Connect

The Nuclear Regulatory Commission Information Digest (digest) provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRCs regulatory responsibility the activities NRC licenses, and general information on domestic and worldwide nuclear energy. The digest, published annually, is a compilation of nuclear-and NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1993, with exceptions noted. Information on generating capacity and average capacity factor for operating US commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the information is reviewed by the NRC for consistency only and no independent validation and/or verification is performed.

Stadler, L.

1994-03-01T23:59:59.000Z

399

Office of Nuclear Threat Science | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Threat Science | National Nuclear Security Administration Threat Science | 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 The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

400

Determination of Basic Structure-Property Relations for Processing and Modeling in Advanced Nuclear Fuel: Microstructure Evolution and Mechanical Properties  

SciTech Connect

The project objective is to study structure-property relations in solid solutions of nitrides and oxides with surrogate elements to simulate the behavior of fuels of inert matrix fuels of interest to the Advanced Fuel Cycle Initiative (AFCI), with emphasis in zirconium-based materials. Work with actual fuels will be carried out in parallel in collaboration with Los Alamos National Laboratory (LANL). Three key aspects will be explored: microstructure characterization through measurement of global texture evolution and local crystallographic variations using Electron Backscattering Diffraction (EBSD); determination of mechanical properties, including fracture toughness, quasi-static compression strength, and hardness, as functions of load and temperature, and, finally, development of structure-property relations to describe mechanical behavior of the fuels based on experimental data. Materials tested will be characterized to identify the mechanisms of deformation and fracture and their relationship to microstructure and its evolution. New aspects of this research are the inclusion of crystallographic information into the evaluation of fuel performance and the incorporation of statistical variations of microstructural variables into simplified models of mechanical behavior of fuels that account explicitly for these variations. The work is expected to provide insight into processing conditions leading to better fuel performance and structural reliability during manufacturing and service, as well as providing a simplified testing model for future fuel production.

Kirk Wheeler; Manuel Parra; Pedro Peralta

2009-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear operations related" 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

DOE/EIS-0373D; Draft Environmental Impact Statement for the Proposed Consolidation of Nuclear Operations Related to Production of Radioisotope Power Systems  

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

vii vii TABLE OF CONTENTS Chapters 1 through 10 Appendices A through H Cover Sheet ..................................................................................................................................................................iii Table of Contents ........................................................................................................................................................vii List of Figures ..........................................................................................................................................................xviii List of Tables...............................................................................................................................................................

402

Nuclear Science Division annual report for 1991  

Science Conference Proceedings (OSTI)

This paper discusses research being conducted under the following programs: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear theory program; nuclear data evaluation program; and 88-inch cyclotron operations.

Myers, W.D. (ed.)

1992-04-01T23:59:59.000Z

403

CRAD, Operating Experience - February 11, 2009 | Department of Energy  

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

CRAD, Operating Experience - February 11, 2009 CRAD, Operating Experience - February 11, 2009 CRAD, Operating Experience - February 11, 2009 February 11, 2009 Operating Experience Inspection Criteria and Approach, DNFSB 2004-1 IP, Commitment 20 (HSS CRAD 64-41, Rev. 0) Provide a plan, including criteria, approaches, and the lines of inquire, to be used for assessing the effectivenss of IP actions relating to learning from internal and external operation experience. The review plan covers all the IP section 5.2, Learning from Internal and External Operating Experience. CRAD, Operating Experience - February 11, 2009 More Documents & Publications CRAD, Federal Assurance Capability Plan - February 11, 2009 Office of Health, Safety and Security Report to the Secretary of Energy - February 2011 CRAD, Nuclear Facility Safety System - September 25, 2009

404

Operational Area Monitoring Plan  

Office of Legacy Management (LM)

' ' SECTION 11.7B Operational Area Monitoring Plan for the Long -Term H yd rol og ical M o n i to ri ng - Program Off The Nevada Test Site S . C. Black Reynolds Electrical & Engineering, Co. and W. G. Phillips, G. G. Martin, D. J. Chaloud, C. A. Fontana, and 0. G. Easterly Environmental Monitoring Systems Laboratory U. S. Environmental Protection Agency October 23, 1991 FOREWORD This is one of a series of Operational Area Monitoring Plans that comprise the overall Environmental Monitoring Plan for the DOE Field Office, Nevada (DOEINV) nuclear and non- nuclear testing activities associated with the Nevada Test Site (NTS). These Operational Area Monitoring Plans are prepared by various DOE support contractors, NTS user organizations, and federal or state agencies supporting DOE NTS operations. These plans and the parent

405

Nuclear reactor apparatus  

DOE Patents (OSTI)

A lifting, rotating and sealing apparatus for nuclear reactors utilizing rotating plugs above the nuclear reactor core. This apparatus permits rotation of the plugs to provide under the plug refueling of a nuclear core. It also provides a means by which positive top core holddown can be utilized. Both of these operations are accomplished by means of the apparatus lifting the top core holddown structure off the nuclear core while stationary, and maintaining this structure in its elevated position during plug rotation. During both of these operations, the interface between the rotating member and its supporting member is sealingly maintained.

Wade, Elman E. (Ruffs Dale, PA)

1978-01-01T23:59:59.000Z

406

Qualification of Siemens Power Corporation TELEPERM XS Safety System: Compliance with EPRI TR-107330 "Generic Requirements Specifica tion for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants"  

Science Conference Proceedings (OSTI)

As its nuclear power plants age, the electric power industry is focusing on the development of cost-effective replacement systems for obsolete instrumentation, control, and safety systems. This report describes the generic qualification of a platform for safety-related applications that incorporates programmable logic controllers (PLCs), a technology with an excellent track record in non-nuclear applications for critical control and safety functions.

1999-11-23T23:59:59.000Z

407

ARM - SGP Operations  

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

Operations Operations SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts SGP Operations Routine Operations SGP central facility offices. SGP central facility offices. The overwhelming majority of the measurements with the highest priority, on which the existing experimental designs are based, are regular routine observations, as specified in the ARM Program Plan, 1990 (U.S. Department of Energy 1990). Scientifically and logistically, routine operations also serve as the basis and background for all nonroutine operations, including

408

Human Performance - Fossil Operations  

Science Conference Proceedings (OSTI)

All humans make errors. Industrial human errors can result in a loss of life and can significantly impact the productivity and cost effectiveness of any facility or company. Several industries in which human error has had a significant impact (for example, airline, medical, military, nuclear power, aviation, and chemical) have implemented human performance programs with excellent results. Human errors by fossil plant operators can easily challenge plant safety and production. In the fossil operations are...

2007-02-28T23:59:59.000Z

409

Westinghouse TRU Solutions LLC Assumes WIPP Operations  

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

Manager of WTS. A retired U.S. Navy Rear Admiral, Herrera has more than 27 years of nuclear operations and radioactive waste management experience. He spent 24 years in nuclear...

410

Critical assessment of seismic and geomechanics literature related to a high-level nuclear waste underground repository  

SciTech Connect

A comprehensive literature assessment has been conducted to determine the nature and scope of technical information available to characterize the seismic performance of an underground repository and associated facilities. Significant deficiencies were identified in current practices for prediction of seismic response of underground excavations in jointed rock. Conventional analytical methods are based on a continuum representation of the host rock mass. Field observations and laboratory experiments indicate that, in jointed rock, the behavior of the joints controls the overall performance of underground excavations. Further, under repetitive seismic loading, shear displacement develops progressively at block boundaries. Field observations correlating seismicity and groundwater conditions have provided significant information on hydrological response to seismic events. However, lack of a comprehensive model of geohydrological response to seismicity has limited the transportability conclusions from field observations. Based on the literature study, matters requiring further research in relation to the Yucca Mountain repository are identified. The report focuses on understanding seismic processes in fractured tuff, and provides a basis for work on the geohydrologic response of a seismically disturbed rock mass. 220 refs., 43 figs., 11 tabs.

Kana, D.D.; Vanzant, B.W.; Nair, P.K. [Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses; Brady, B.H.G. [ITASCA Consulting Group, Inc., Minneapolis, MN (USA)

1991-06-01T23:59:59.000Z

411

HAZARDS AND SAFETY MEASURES RELATED TO NUCLEAR-POWERED MERCHANT SHIPS: AN ANNOTATED BIBLIOGRAPHY OF DECLASSIFIED LITERATURE  

SciTech Connect

This compilation contains 202 abstracts of reports and documents on subjects related to maritime reactor safety; the abstracts are indexed in thc AEC Abstracts of Classified Reports'' (ACR). These ACR references were listed as unclassified or declassified in TID-4021, TID-40.35, and TID-4035, Supplement 1. The abstracts were selected as a part of the preparation of the classified bibliography (ALI-50, printed August 30, 1958) on this same subject. (See also SO-6200, Septcmber 15, 1957, unclassified.) The abstracts are grouped according to the category of information they present; within each category, the most recent abstracts are given first. Subject, author, and report number indices are provided. A report number code key is not included. The report numbers used by the AEC Technical Information Service can be found in TID-85 (1st Rev.). The abstracts are those indexed through ACR Vol. 13 (1957). Because of the lag in abstracting, reports issued in late 1957 are not likely to be included. (auth)

White, M.K. comp.

1959-03-30T23:59:59.000Z

412

NUCLEAR REACTOR  

DOE Patents (OSTI)

This patent relates to a combination useful in a nuclear reactor and is comprised of a casing, a mass of graphite irapregnated with U compounds in the casing, and at least one coolant tube extending through the casing. The coolant tube is spaced from the mass, and He is irtroduced irto the space between the mass and the coolant tube. (AEC)

Starr, C.

1963-01-01T23:59:59.000Z

413

Tritium activities in Canada supporting CANDU{sup R} nuclear power reactors  

Science Conference Proceedings (OSTI)

An overview of the various Canadian tritium research and operational activities supporting the development, refurbishment and operation of CANDU{sup R} nuclear power reactors is presented. These activities encompass tritium health and safety, tritium in the environment, tritium interaction with materials, and tritium processing, and relate to both supporting R and D advances as well as operational best practices. The collective results of these activities contribute to our goals of improving worker and public safety, and operational efficiency. (authors)

Miller, J. M. [AECL, Chalk River Laboratories, Chalk River, ON K0J 1J0 (Canada)

2008-07-15T23:59:59.000Z

414

Nuclear and Radiological Engineering and Medical Physics Programs  

E-Print Network (OSTI)

Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

Weber, Rodney

415

Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement  

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

Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and several related enforcement issues. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues More Documents & Publications Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 00-03: Specific Issues on Applicability of

416

Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement  

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

Guidance Supplement 01-01: Nuclear Weapon Program Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities. This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and several related enforcement issues. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues More Documents & Publications Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 00-03: Specific Issues on Applicability of

417

Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement  

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

Guidance Supplement 01-01: Nuclear Weapon Program Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Section 1.3 of the Operational Procedures for Enforcement, published in June 1998, provides the opportunity for the Office of Price-Anderson Enforcement (OE) to periodically issue clarifying guidance regarding the processes used in its enforcement activities.This enforcement guidance focuses on the applicability of 10 CFR Part 830 to nuclear weapon programs and several related enforcement issues. Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues More Documents & Publications Enforcement Guidance Supplement 01-01: Nuclear Weapon Program Enforcement Issues Enforcement Guidance Supplement 00-03: Specific Issues on Applicability of

418

Time-Limited Aging Analysis Report for the Edwin I. Hatch Nuclear Power Plant  

Science Conference Proceedings (OSTI)

The option to operate a nuclear power plant beyond its initial license term of 40 years is an important factor in financial decisions and long-term planning for utility asset management and capital improvement. Southern Company has submitted an application for the renewal of its operating licenses for the E. I. Hatch Nuclear Power Plant. As part of the application preparation process, Southern Company has reviewed its design and licensing basis for Plant Hatch for time-limited, aging-related assumptions....

2000-04-11T23:59:59.000Z

419

Nuclear Regulatory Commission Information Digest, 1991 edition  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, and the areas NRC licenses. This digest is a compilation of NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1990, with exceptions noted. For operating US commercial nuclear power reactors, information on generating capacity and average capacity factor is obtained from Monthly Operating Reports submitted to the NRC directly by the licensee. This information is reviewed for consistency only. No independent validation and/or verification is performed by the NRC. For detailed and complete information about tables and figures, refer to the source publications. This digest is published annually for the general use of the NRC staff and is available to the public. 30 figs., 12 tabs.

Olive, K L

1991-03-01T23:59:59.000Z

420

Nuclear Safety Regulatory Framework  

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

Department of Energy Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting DOE Directives & Manuals DOE Standards Central Technical Authorities (CTA) Office of Health, Safety, and Security (HSS) Line Management SSO/ FAC Reps 48 CFR 970 48 CFR 952 Federal Acquisition Regulations External Oversight *Defense Nuclear Facility

Note: This page contains sample records for the topic "nuclear operations related" 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

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

U.S. Energy Information Administration (EIA) Indexed Site

Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

422

California Nuclear Profile - San Onofre Nuclear Generating Station  

U.S. Energy Information Administration (EIA) Indexed Site

San Onofre Nuclear Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

423

New York Nuclear Profile - Nine Mile Point Nuclear Station  

U.S. Energy Information Administration (EIA) Indexed Site

Nine Mile Point Nuclear Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

424

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

U.S. Energy Information Administration (EIA) Indexed Site

R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License...

425

Nuclear Safety Information Dashboard QuickStart Guide  

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

Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard QuickStart Guide September 2012 Office of Analysis (HS-24) Office of Environmental Protection, Sustainability Support and Corporate Safety Analysis Office of Health, Safety and Security (HSS) Purpose of Nuclear Safety Information (NSI) Dashboard * The NSI Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. * ORPS reporting criteria associated with events at nuclear facilities have pre-assigned weighting factors according to their relative importance and are placed into groups. * This information can be evaluated to identify trends and, using insights from current events and nature of operations, enable

426

Internal conversion of nuclear transition in the ${}^{235m}U@C_{60-n}X_n$ molecules and related compounds  

E-Print Network (OSTI)

The internal conversion of nuclear transition in the ${}^{235}U$ atom is considered. The low-energy $\\gamma-$quanta ($E_{\\gamma} \\approx$ 76.8 $eV$) are emitted during the $E3-$transition from the excited state ($I = (\\frac12)^+$) of the ${}^{235}U$ nucleus to its ground state ($I = (\\frac72)^-$). The decay rate of this ${}^{235m}U$ isomer ($E \\approx 76.8$ $eV$) noticeably depends upon the chemical composition and actual physical conditions (i.e. temperature $T$ and pressure $p$). By varying such a composition and physical conditions one can change the life-time of the ${}^{235m}U$ isomer to relatively large/small values. A specific attention is given to the fullerene molecules containing the central ${}^{235}U$ atom. It is shown that the decay rate $\\lambda$ of the ${}^{235m}U$ isomer in the ${}^{235m}U@C_{60-n}X_n$ molecules and related compounds can differ significantly from the values obtained for isolated ${}^{235}U$ atoms. Some applications of this effect are considered.

Alexei M. Frolov

2010-01-19T23:59:59.000Z

427

Powering the Nuclear Navy | National Nuclear Security Administration  

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

Powering the Nuclear Navy Powering the Nuclear Navy Home > About Us > Our Programs > Powering the Nuclear Navy Powering the Nuclear Navy The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived operation. This mission requires the combination of fully trained U.S. Navy men and women with ships that excel in endurance, stealth, speed, and independence from supply chains. NNSA's Navy Reactors Program provides the design, development and operational support required to provide militarily effective nuclear propulsion plants and ensure their safe, reliable and long-lived operation. This budget requests more than $1 billion to power a modern nuclear Navy: Continuation of design and development work for the OHIO-class

428

CRAD, Conduct of Operations - Y-12 Enriched Uranium Operations Oxide  

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

Conduct of Operations - Y-12 Enriched Uranium Operations Conduct of Operations - Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Conduct of Operations - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a January, 2005 assessment of Conduct of Operations program at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Conduct of Operations - Y-12 Enriched Uranium Operations Oxide Conversion Facility More Documents & Publications CRAD, DOE Oversight - Y-12 Enriched Uranium Operations Oxide Conversion

429

Nuclear criticality safety guide  

Science Conference Proceedings (OSTI)

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

430

Nuclear Safety Information Dashboard  

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

provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into...

431

Nuclear & Particle Physics Directorate  

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

Brookhaven National Laboratory Nuclear and Particle Physics Program Advisory Committee Meeting 7-8 June 2012 Agenda Related Documents: PHENIX Beam Use Proposal, STAR Beam Use...

432

LANL continuity of operations plan  

SciTech Connect

The Los Alamos National Laboratory (LANL) is a premier national security research institution, delivering scientific and engineering solutions for the nation's most crucial and complex problems. Our primary responsibility is to ensure the safety, security, and reliability of the nation's nuclear stockpile. LANL emphasizes worker safety, effective operational safeguards and security, and environmental stewardship, outstanding science remains the foundation of work at the Laboratory. In addition to supporting the Laboratory's core national security mission, our work advances bioscience, chemistry, computer science, earth and environmental sciences, materials science, and physics disciplines. To accomplish LANL's mission, we must ensure that the Laboratory EFs continue to be performed during a continuity event, including localized acts of nature, accidents, technological or attack-related emergencies, and pandemic or epidemic events. The LANL Continuity of Operations (COOP) Plan documents the overall LANL COOP Program and provides the operational framework to implement continuity policies, requirements, and responsibilities at LANL, as required by DOE 0 150.1, Continuity Programs, May 2008. LANL must maintain its ability to perform the nation's PMEFs, which are: (1) maintain the safety and security of nuclear materials in the DOE Complex at fixed sites and in transit; (2) respond to a nuclear incident, both domestically and internationally, caused by terrorist activity, natural disaster, or accident, including mobilizing the resources to support these efforts; and (3) support the nation's energy infrastructure. This plan supports Continuity of Operations for Los Alamos National Laboratory (LANL). This plan issues LANL policy as directed by the DOE 0 150.1, Continuity Programs, and provides direction for the orderly continuation of LANL EFs for 30 days of closure or 60 days for a pandemic/epidemic event. Initiation of COOP operations may be required to support an allhazards event, including a national security emergency, major fire, catastrophic natural disaster, man-made disaster, terrorism event, or technological disaster by rendering LANL buildings, infrastructure, or Technical Areas unsafe, temporarily unusable, or inaccessible.

Senutovitch, Diane M [Los Alamos National Laboratory

2010-12-22T23:59:59.000Z

433

EIA - AEO2010 - U.S. nuclear power plants: Continued life or replacement  

Gasoline and Diesel Fuel Update (EIA)

U.S. nuclear power plants: continued life or replacement after 60? U.S. nuclear power plants: continued life or replacement after 60? Annual Energy Outlook 2010 with Projections to 2035 U.S. nuclear power plants: Continued life or replacement after 60? Background Nuclear power plants generate approximately 20 percent of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of GHG regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating. The nuclear industry has expressed strong interest in continuing the operation of existing nuclear facilities, and no particular technical issues have been identified that would impede their continued operation. Recent AEOs had assumed that existing nuclear units would be retired after 60 years of operation (the initial 40-year license plus one 20-year license renewal). Maintaining the same assumption in AEO2010, with the projection horizon extended to 2035, would result in the retirement of more than one-third of existing U.S. nuclear capacity between 2029 and 2035. Given the uncertainty about when existing nuclear capacity actually will be retired, EIA revisited the assumption for the development of AEO2010 and modified it to allow the continued operation of all existing U.S. nuclear power plants through 2035 in the Reference case.

434

The Office of Nuclear Safeguards and Security | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Safeguards and Security | National Nuclear Security Safeguards and Security | 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 The Office of Nuclear Safeguards and Security Home > About Us > Our Programs > Nonproliferation > Nonproliferation & International Security > The Office of Nuclear Safeguards and Security The Office of Nuclear Safeguards and Security

435

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

436

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

437

Nuclear data for nuclear transmutation  

Science Conference Proceedings (OSTI)

Current status on nuclear data for the study of nuclear transmutation of radioactive wastes is reviewed

Hideo Harada

2009-01-01T23:59:59.000Z

438

Amended NOI to Prepare an EIS for the Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components  

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

61 61 Federal Register / Vol. 60, No. 121 / Friday, June 23, 1995 / Notices operating facilities primarily or inherently devoted to religious instruction or worship, or engaging in any form of religious proselytization; and (7) providing a direct benefit to (a) a business organized for profit, (b) a labor union, (c) a partisan political organization, (d) a nonprofit organization that fails to comply with the restrictions contained in section 501(c) of the Internal Revenue Code of 1986, or (e) an organization engaged in the religious activities described in paragraph (6) above, unless Corporation assistance is not used to support those religious activities. Eligible Applicants Governors may apply on behalf of the following eligible entities: non-profit organizations, states, subdivisions of

439

Operations & Maintenance  

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

Rates Operations & Maintenance Operations OASIS: WACM (Note: this site is not hosted by Western and requires a digital certificate and login for full access.) wesTTrans Common...

440

International | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

International | National Nuclear Security Administration International | 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 Home > About Us > Our Programs > Nuclear Security > Nuclear Materials Management & Safeguards System > International International U.S. Department of Energy / U.S. Nuclear Regulatory Commission

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


441

IMPROVEMENTS RELATING TO NUCLEAR REACTORS  

SciTech Connect

In order to reduce the pumping power for the coolant in a steam-cooled reactor, in which the steam being passed through successive sections of the reactor core and being superheated there, the sections are connected in series with one another, while a plurality of de-superheaters is provided such that steam flowing from one section to the next passes through a de-superheater. The condensed steam returning to the reactor from the means utilizing the steam heat content is divided into a number of separate streams. The first stream going to the first section in the reactor core is raised at least to saturated steam outside the reactor, while the remaining streams of condensed steam are conveyed to the de-superheaters to be mixed with steam passing therethrough between successive sections of the reactor, cooling in this manner said steam and being themselves converted into steam. Increasing amounts of condensate are added in successive de-superheaters until the steam returning to the reactor from the final desuperheater is equivalent to the full mass flow of steam circulating to the heat utilizing means. (NPO)

1960-08-01T23:59:59.000Z

442

TANK OPERATIONS CONTRACT CONSTRUCTION MANAGEMENT METHODOLOGY UTILIZING THE AGENCY METHOD OF CONSTRUCTION MANAGEMENT TO SAFELY AND EFFECTIVELY COMPLETE NUCLEAR CONSTRUCTION WORK  

SciTech Connect

Washington River Protection Solutions, LLC (WRPS) has faced significant project management challenges in managing Davis-Bacon construction work that meets contractually required small business goals. The unique challenge is to provide contracting opportunities to multiple small business construction subcontractors while performing high hazard work in a safe and productive manner. Previous to the Washington River Protection Solutions, LLC contract, Construction work at the Hanford Tank Farms was contracted to large companies, while current Department of Energy (DOE) Contracts typically emphasize small business awards. As an integral part of Nuclear Project Management at Hanford Tank Farms, construction involves removal of old equipment and structures and installation of new infrastructure to support waste retrieval and waste feed delivery to the Waste Treatment Plant. Utilizing the optimum construction approach ensures that the contractors responsible for this work are successful in meeting safety, quality, cost and schedule objectives while working in a very hazardous environment. This paper describes the successful transition from a traditional project delivery method that utilized a large business general contractor and subcontractors to a new project construction management model that is more oriented to small businesses. Construction has selected the Agency Construction Management Method. This method was implemented in the first quarter of Fiscal Year (FY) 2009, where Construction Management is performed by substantially home office resources from the URS Northwest Office in Richland, Washington. The Agency Method has allowed WRPS to provide proven Construction Managers and Field Leads to mentor and direct small business contractors, thus providing expertise and assurance of a successful project. Construction execution contracts are subcontracted directly by WRPS to small or disadvantaged contractors that are mentored and supported by DRS personnel. Each small contractor is mentored and supported utilizing the principles of the Construction Industry Institute (CII) Partnering process. Some of the key mentoring and partnering areas that are explored in this paper are, internal and external safety professional support, subcontractor safety teams and the interface with project and site safety teams, quality assurance program support to facilitate compliance with NQA-1, construction, team roles and responsibilities, work definition for successful fixed price contracts, scheduling and interface with project schedules and cost projection/accruals. The practical application of the CII Partnering principles, with the Construction Management expertise of URS, has led to a highly successful construction model that also meets small business contracting goals.

LESO KF; HAMILTON HM; FARNER M; HEATH T

2010-01-14T23:59:59.000Z

443

Figure 9.1 Nuclear Generating Units - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Figure 9.1 Nuclear Generating Units Operable Units,1 1957-2011 Nuclear Net Summer Capacity Change, 1950-2011 Status of All Nuclear Generating Units, ...

444

Nuclear Deployment Scorecards | Department of Energy  

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

Initiatives » Nuclear Reactor Technologies » Nuclear Deployment Initiatives » Nuclear Reactor Technologies » Nuclear Deployment Scorecards Nuclear Deployment Scorecards October 31, 2013 Quarterly Nuclear Deployment Scorecard - October 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, new plant construction progress, and expected operation dates. August 8, 2013 Quarterly Nuclear Deployment Scorecard - July 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, new plant construction progress, and expected operation dates. May 1, 2013 Quarterly Nuclear Power Deployment Scorecard - April 2013 The scorecard includes news updates, regulatory status, reactor design certification, early site permits, and new plant construction progress.

445

Technology Evaluations Related to Mercury, Technetium, and Chloride in Treatment of Wastes at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory  

SciTech Connect

The Idaho High-Level Waste and Facility Disposition Environmental Impact Statement defines alternative for treating and disposing of wastes stored at the Idaho Nuclear Technology and Engineering Center. Development is required for several technologies under consideration for treatment of these wastes. This report contains evaluations of whether specific treatment is needed and if so, by what methods, to remove mercury, technetium, and chlorides in proposed Environmental Impact Statement treatment processes. The evaluations of mercury include a review of regulatory requirements that would apply to mercury wastes in separations processes, an evaluation of the sensitivity of mercury flowrates and concentrations to changes in separations processing schemes and conditions, test results from laboratory-scale experiments of precipitation of mercury by sulfide precipitation agents from the TRUEX carbonate wash effluent, and evaluations of methods to remove mercury from New Waste Calcining Facility liquid and gaseous streams. The evaluation of technetium relates to the need for technetium removal and alternative methods to remove technetium from streams in separations processes. The need for removal of chlorides from New Waste Calcining Facility scrub solution is also evaluated.

C. M. Barnes; D. D. Taylor; S. C. Ashworth; J. B. Bosley; D. R. Haefner

1999-10-01T23:59:59.000Z

446

Documents and related materials associated with the contents and the origin of the Los Alamos technical series and the national nuclear energy series  

SciTech Connect

The rationale for preparing this document arose from the fact that the author (who worked in D-Building during WWII) was asked to contribute a short article on {open_quotes}Plutonium Metallurgy at Los Alamos During the War{close_quotes} for inclusion in the 50th anniversary book, {open_quotes}Behind Tall Fences,{close_quotes} published in 1993 by the J.R. Oppenheimer Memorial Committee. I agreed, believing that all of the source material needed was readily available in the Los Alamos Technical Series, a detailed account of all of the R&D carried out at Los Alamos from 1943 to 1945. The obvious place to start was the LANL Report Library. As will be seen by the perusing the following memoranda and reports (which were assembled one at a time by following up successive leads), it finally turned out that, of all six chapters of Vol. 10, {open_quotes}Metallurgy,{close_quotes} of which Cyril S. Smith was the general editor, the only one {open_quotes}not yet issued{close_quotes} was Chapter I on {open_quotes}Plutonium Metallurgy,{close_quotes} which had been assigned to Eric R. Jette, the wartime Group Leader of the Plutonium Metallurgy Group. Jette left Los Alamos at the end of August 1956 to join the Union Carbide Research Institute in Tarrytown, New York, where he was director until June 1962 when he retired to his valley home in Pojoaque. In February 1963, he was awarded the US Atomic Energy Commission citation for meritorious contributions to the Nuclear Energy Program; shortly thereafter he died. Before accepting the fact that Chapter I did not exist, the present author undertook to find out as much as possible about the Los Alamos Technical Series, including the circumstances relating to its preparation. The related memos, etc., once retrieved, seemed worth preserving in a single report-hence this document.

Hammel, E.F.

1996-04-01T23:59:59.000Z

447

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents (OSTI)

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, E.

1984-01-27T23:59:59.000Z

448

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents (OSTI)

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

449

Strategic Nuclear Research Collaboration - FY99 Annual Report  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) has created the Strategic Nuclear Research Collaboration. The SNRC brings together some of America's finest laboratory and university nuclear researchers in a carefully focused research program intended to produce ''breakthrough'' solutions to the difficult issues of nuclear economics, safety, non-proliferation, and nuclear waste. This integrated program aims to address obstacles that stand in the way of nuclear power development in the US These include fuel cycle concerns related to waste and proliferation, the need for more efficient regulatory practices, and the high cost of constructing and operating nuclear power plants. Funded at an FY99 level of $2.58M, the SNRC is focusing the efforts of scientists and engineers from the INEEL and the Massachusetts Institute of Technology to solve complex nuclear energy challenges in a carefully chosen, integrated portfolio of research topics. The result of this collaboration will be research that serves as a catalyst for future direct-funded nuclear research and technology development and which preserves and enhances the INEEL's role as America's leading national laboratory for nuclear power research. In its first year, the SNRC has focused on four research projects each of which address one or more of the four issues facing further nuclear power development (economics, safety, waste disposition and proliferation-resistance). This Annual Report describes technical work and accomplishments during the first year of the SNRC's existence.

T. J. Leahy

1999-07-01T23:59:59.000Z

450