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Note: This page contains sample records for the topic "nuclear plant closure" 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

Power Plant Closure Guidebook  

Science Conference Proceedings (OSTI)

Organizations that are planning to decommission an aged power plant face a host of issues that must be addressed and many tasks that must be properly executed in order to ensure a successful closure of the facility.

2010-10-20T23:59:59.000Z

2

Closure head for a nuclear reactor  

DOE Patents (OSTI)

A closure head for a nuclear reactor includes a stationary outer ring integral with the reactor vessel with a first rotatable plug disposed within the stationary outer ring and supported from the stationary outer ring by a bearing assembly. A sealing system is associated with the bearing assembly to seal the annulus defined between the first rotatable plug and the stationary outer ring. The sealing system comprises tubular seal elements disposed in the annulus with load springs contacting the tubular seal elements so as to force the tubular seal elements against the annulus in a manner to seal the annulus. The sealing system also comprises a sealing fluid which is pumped through the annulus and over the tubular seal elements causing the load springs to compress thereby reducing the friction between the tubular seal elements and the rotatable components while maintaining a gas-tight seal therebetween.

Wade, Elman E. (South Huntingdon, PA)

1980-01-01T23:59:59.000Z

3

Groundwater Closure Strategy for Former Manufactured Gas Plant Sites  

Science Conference Proceedings (OSTI)

Utilities responsible for Manufactured Gas Plant (MGP) remediation must navigate numerous challenges in order to attain regulatory closure. Typically, the first strategic focus is on source remediation: to locate, treat or remove MGP residuals that constitute ongoing sources of impacts to receptors (e.g., direct contact, soil vapor, or groundwater). Often the last compliance piece that must fall into place is compliance with regulatory criteria for groundwater. The state-specific regulatory closure ...

2012-12-12T23:59:59.000Z

4

Hanford Facility Dangerous Waste Closure Plan - Plutonium Finishing Plant Treatment Unit Glovebox HA-20MB  

Science Conference Proceedings (OSTI)

This closure plan describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) glovebox HA-20MB that housed an interim status ''Resource Conservation and Recovery Act'' (RCRA) of 1976 treatment unit. This closure plan is certified and submitted to Ecology for incorporation into the Hanford Facility RCRA Permit (HF RCRA Permit) in accordance with Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement; TPA) Milestone M-83-30 requiring submittal of a certified closure plan for ''glovebox HA-20MB'' by July 31, 2003. Glovebox HA-20MB is located within the 231-5Z Building in the 200 West Area of the Hanford Facility. Currently glovebox HA-20MB is being used for non-RCRA analytical purposes. The schedule of closure activities under this plan supports completion of TPA Milestone M-83-44 to deactivate and prepare for dismantlement the above grade portions of the 234-5Z and ZA, 243-Z, and 291-Z and 291-Z-1 stack buildings by September 30, 2015. Under this closure plan, glovebox HA-20MB will undergo clean closure to the performance standards of Washington Administrative Code (WAC) 173-303-610 with respect to all dangerous waste contamination from glovebox HA-20MB RCRA operations. Because the intention is to clean close the PFP treatment unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. Any information on radionuclides is provided only for general knowledge. Clearance form only sent to RHA.

PRIGNANO, A.L.

2003-06-25T23:59:59.000Z

5

Closure Mechanism and Method for Spent Nuclear Fuel Canisters  

DOE Patents (OSTI)

A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Doman, Marvin J.

2004-11-23T23:59:59.000Z

6

Closure mechanism and method for spent nuclear fuel canisters  

DOE Patents (OSTI)

A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Doman, Marvin J. (Monroeville, PA)

2004-11-23T23:59:59.000Z

7

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

8

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

9

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

10

Evolution of the N = 28 shell closure: a test bench for nuclear forces  

E-Print Network (OSTI)

Evolution of the N = 28 shell closure: a test bench for nuclear forces O. Sorlin1 and M.-G. Porquet;The N = 28 shell closure: a test bench for nuclear forces 2 reach a value of 4.8 MeV. This effect has and 90). More generally, questions related to the evolution of nuclear forces towards the drip

Paris-Sud XI, Université de

11

Georgia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

12

Arkansas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

13

Iowa Nuclear Profile - Power Plants  

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

Iowa nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

14

Ohio Nuclear Profile - Power Plants  

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

Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

15

Vermont Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

16

Florida Nuclear Profile - Power Plants  

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

Florida nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

17

Virginia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

18

Missouri Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

19

Nebraska Nuclear Profile - Power Plants  

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

Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

20

Tennessee Nuclear Profile - Power Plants  

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

Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

Note: This page contains sample records for the topic "nuclear plant closure" 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

Minnesota Nuclear Profile - Power Plants  

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

Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

22

Arizona Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

23

Massachusetts Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

24

Kansas Nuclear Profile - Power Plants  

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

Kansas nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

25

Alabama Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

26

Wisconsin Nuclear Profile - Power Plants  

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

Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

27

Texas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

28

Michigan Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

29

NUCLEAR POWER PLANT  

DOE Patents (OSTI)

A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

1963-05-14T23:59:59.000Z

30

Maryland Nuclear Profile - Power Plants  

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

of State nuclear net generation (percent)","Owner" "Calvert Cliffs Nuclear Power Plant Unit 1, Unit 2","1,705","13,994",100.0,"Calvert Cliffs Nuclear PP Inc" "1 Plant 2...

31

Eddy Current Examination of Spent Nuclear Fuel Canister Closure Welds  

SciTech Connect

The National Spent Nuclear Fuel Program (NSNFP) has developed standardized DOE SNF canisters for handling and interim storage of SNF at various DOE sites as well as SNF transport to and SNF handling and disposal at the repository. The final closure weld of the canister will be produced remotely in a hot cell after loading and must meet American Society of Mechanical Engineers (ASME) Section III, Division 3 code requirements thereby requiring volumetric and surface nondestructive evaluation to verify integrity. This paper discusses the use of eddy current testing (ET) to perform surface examination of the completed welds and repair cavities. Descriptions of integrated remote welding/inspection system and how the equipment is intended function will also be discussed.

Arthur D. Watkins; Dennis C. Kunerth; Timothy R. McJunkin

2006-04-01T23:59:59.000Z

32

Nuclear Plant Decommissioning  

Science Conference Proceedings (OSTI)

In the 1990s several nuclear utilities proceeded with full decommissioning of their nuclear power plants based on perceived economics. This major shift to immediate decommissioning presented a significant challenge to the industry in terms of the development of a decommissioning process and a comprehensive updated regulatory framework. EPRI responded by undertaking the formation of the Decommissioning Support Program. The initial work involved conducting a series of topical workshops directed to specific...

2010-11-24T23:59:59.000Z

33

Washington Nuclear Profile - Power Plants  

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

Washington nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

34

Connecticut Nuclear Profile - Power Plants  

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

Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

35

California Nuclear Profile - Power Plants  

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

California nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

36

Mississippi Nuclear Profile - Power Plants  

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

Mississippi nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

37

Louisiana Nuclear Profile - Power Plants  

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

Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant NameTotal Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

38

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...

39

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...

40

Illinois Nuclear Profile - Power Plants  

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

Illinois nuclear power plants, summer capacity and net generation, 2010" Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Braidwood Generation Station Unit 1, Unit 2","2,330","19,200",20.0,"Exelon Nuclear" "Byron Generating Station Unit 1, Unit 2","2,300","19,856",20.6,"Exelon Nuclear" "Clinton Power Station Unit 1","1,065","8,612",9.0,"Exelon Nuclear" "Dresden Generating Station Unit 2, Unit 3","1,734","14,593",15.2,"Exelon Nuclear" "LaSalle Generating Station

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


41

Nuclear power plant design analysis  

SciTech Connect

Information concerning the engineering aspects of the design of commercial nuclear power plants is presented. Topics discussed include: electric utility economics; nuclear plant cconomics; thermal-transport systems and core design; nuclear analysis methods; safcty requirements; fuel-system analysis; dcsign considerations; and optimization approaches. (DCC)

Sesonske, A.

1973-01-01T23:59:59.000Z

42

Automated closure system for nuclear reactor fuel assemblies  

DOE Patents (OSTI)

A welder for automated closure of fuel pins by a pulsed magnetic process in which the open end of a length of cladding is positioned within a complementary tube surrounded by a pulsed magnetic welder. Seals are provided at each end of the tube, which can be evacuated or can receive tag gas for direct introduction to the cladding interior. Loading of magnetic rings and end caps is accomplished automatically in conjunction with the welding steps carried out within the tube.

Christiansen, David W. (Kennewick, WA); Brown, William F. (West Richland, WA)

1985-01-01T23:59:59.000Z

43

Owners of nuclear power plants  

Science Conference Proceedings (OSTI)

Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

Hudson, C.R.; White, V.S.

1996-11-01T23:59:59.000Z

44

Pennsylvania Nuclear Profile - Power Plants  

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

Pennsylvania nuclear power plants, summer capacity and net generation, 2010" Pennsylvania nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Beaver Valley Unit 1, Unit 2","1,777","14,994",19.3,"FirstEnergy Nuclear Operating Company" "Limerick Unit 1, Unit 2","2,264","18,926",24.3,"Exelon Nuclear" "PPL Susquehanna Unit 1, Unit 2","2,450","18,516",23.8,"PPL Susquehanna LLC" "Peach Bottom Unit 2, Unit 3","2,244","18,759",24.1,"Exelon Nuclear" "Three Mile Island Unit 1",805,"6,634",8.5,"Exelon Nuclear"

45

Naval Nuclear Propulsion Plants | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Naval Nuclear Propulsion Plants In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor core produces heat. Because the fission process also produces...

46

North Carolina Nuclear Profile - Power Plants  

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

Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

47

New Hampshire Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net...

48

New Jersey Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

49

Connecticut Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2ct Millstone Unit 2, Unit 3 2,103 16,750 100.0 Dominion Nuclear Conn Inc 1 Plant 2 Reactors Owner Note: Totals may not equal sum of components due to independent ...

50

Arkansas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2ar Arkansas Nuclear One Unit 1, Unit 2 1,835 15,023 100.0 Entergy Arkansas Inc 1 Plant 2 Reactors Owner Note: Totals may not equal sum of ...

51

Recovery from Unemplyment in Latina Women After a Plant Closure  

E-Print Network (OSTI)

California Economic and Social Impact of Plant Closings onsomatization), (10) Social Impact of Job Loss, and (11)

Castro, Felipe G.; Romero, Gloria J.

1987-01-01T23:59:59.000Z

52

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

U.S. Energy Information Administration (EIA)

snpt3wi4046 506 3,954 89.2 PWR 512 4,336 96.7 1,018 8,291 93.0 Point Beach Nuclear Plant Unit Type Data for 2010 PWR = Pressurized Light Water Reactor. Note: Totals ...

53

ALARA at nuclear power plants  

SciTech Connect

Implementation of the As Low As Reasonably Achievable (ALARA) principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed though a variety of dose reduction techniques. It is planned that this report will include material on historical aspects, management, valuation of dose reduction, quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report. 30 refs., 1 fig., 6 tabs.

Baum, J.W.

1990-01-01T23:59:59.000Z

54

Developing and Qualifying Parameters for Closure Welding Overpacks Containing Research Reactor Spent Nuclear Fuel at Hanford  

SciTech Connect

Fluor engineers developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrated requisite weld quality, and successfully closure-welded packaged spent nuclear fuel (SNF) overpacks at the Hanford Site. This paper reviews weld development and qualification activities associated with the overpack closure-welding and provides a summary of the production campaign. The primary requirement of the closure weld is to provide leak-tight confinement of the packaged material against release to the environment during interim storage (40-year design term). Required weld quality, in this case, was established through up-front development and qualification, and then verification of parameter compliance during production welding. This approach was implemented to allow for a simpler overpack design and more efficient production operations than possible with approaches using routine post-weld testing and nondestructive examination (NDE). A series of welding trials were conducted to establish the desired welding technique and parameters. Qualification of the process included statistical evaluation and American Society of Mechanical Engineers (ASME) Section IX testing. In addition, pull testing with a weighted mockup, and thermal calculation/physical testing to identify the maximum temperature the packaged contents would be subject to during welding, was performed. Thirteen overpacks were successfully packaged and placed into interim storage. The closure-welding development activities (including pull testing and thermal analysis) provided the needed confidence that the packaged SNF overpacks could be safely handled and placed into interim storage, and remain leak-tight for the duration of the storage term. (author)

Cannell, G.R.; Goldmann, L.H.; McCormack, R.L. [Hanford Site, Richland, WA (United States)

2008-07-01T23:59:59.000Z

55

DEVELOPING AND QUANTIFYING PARAMETERS FOR CLOSURE WELDING OVERPACKS CONTAINING RESEARCH REACTOR SPENT NUCLEAR FUEL AT HANFORD  

SciTech Connect

Fluor engineers developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrated requisite weld quality and successfully closure-welded packaged spent nuclear fuel (SNF) overpacks at the Hanford Site. This paper reviews weld development and qualification activities associated with the overpack closure-welding and provides a summary of the production campaign. The primary requirement of the closure weld is to provide leaktight confinement of the packaged material against release to the environment during interim storage (40-year design term). Required weld quality, in this case, was established through up-front development and qualification, and then verification of parameter compliance during production welding. This approach was implemented to allow for a simpler overpack design and more efficient production operations than possible with approaches using routine post-weld testing and nondestructive examination (NDE). . A series of welding trials were conducted to establish the desired welding technique and parameters. Qualification of the process included statistical evaluation and American Society of Mechanical Engineers (ASME) Section IX testing. In addition, pull testing with a weighted mockup, and thermal calculation/physical testing to identify the maximum temperature the packaged contents would be subject to during welding, was performed. Thirteen overpacks were successfully packaged and placed into interim storage. The closure-welding development activities (including pull testing and thermal analysis) provided the needed confidence that the packaged SNF overpacks could be safely handled and placed into interim storage, and remain leaktight for the duration of the storage term.

CANNELL GR

2007-11-07T23:59:59.000Z

56

Performance of nuclear plant RTDs  

SciTech Connect

Resistance temperature detectors (RTDs) are used for safety-related measurements in nuclear power plants and must therefore be accurate and respond to temperature changes in a timely fashion. Experience has shown that RTD calibration shift and response-time degradation can occur with aging. Therefore, periodic testing is performed to ensure that acceptable performance limits are not exceeded. A new method called the loop current step response (LCSR) test is used for periodic response-time testing of nuclear plant RTDs. This method permits testing the RTD as installed in an operating plant (in situ testing). The LCSR test is based on heating the RTD sensing element with a small electric current applied remotely through the sensor lead wires.

Hashemian, H.M.; Petersen, K.M.

1987-01-01T23:59:59.000Z

57

The Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

Dr. David A. Petti

2009-01-01T23:59:59.000Z

58

Nuclear power plants: structure and function  

SciTech Connect

Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and reactor safety.

Hendrie, J.M.

1983-01-01T23:59:59.000Z

59

Advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

60

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

Note: This page contains sample records for the topic "nuclear plant closure" 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

Sabotage at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

Purvis, James W.

1999-07-21T23:59:59.000Z

62

New York Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Indian Point Unit 2, Unit 3","2,063","16,321",39.0,"Entergy Nuclear Indian Point" "James A Fitzpatrick Unit 1",855,"6,361",15.2,"Entergy Nuc Fitzpatrick LLC" "Nine Mile Point Nuclear Station Unit 1, Unit 2","1,773","14,239",34.0,"Nine Mile Point Nuclear Sta LLC" "R E Ginna Nuclear Power Plant Unit 1",581,"4,948",11.8,"R.E. Ginna Nuclear Power Plant, LLC" "4 Plants

63

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

SciTech Connect

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

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

64

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...

65

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...

66

Organizational learning at nuclear power plants  

E-Print Network (OSTI)

The Nuclear Power Plant Advisory Panel on Organizational Learning provides channels of communications between the management and organization research projects of the MIT International Program for Enhanced Nuclear Power ...

Carroll, John S.

1991-01-01T23:59:59.000Z

67

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

DOE Green Energy (OSTI)

The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

Steven R. Sherman

2007-06-01T23:59:59.000Z

68

Balance of Plant Corrosion Issues in Aging Nuclear Power Plants  

Science Conference Proceedings (OSTI)

... number of times, can be used to forecast the most probable number of leaks. ... Conditions for Long Term Operation of Nuclear Power Plants in Sweden.

69

Nuclear power plant construction activity, 1988  

SciTech Connect

Nuclear Power Plant Construction Activity 1988 presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1988. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

1989-06-14T23:59:59.000Z

70

Materials in Nuclear Power Plant Construction - TMS  

Science Conference Proceedings (OSTI)

139th Annual Meeting & Exhibition. February 14 - 18, 2010, Washington State Convention Center, Seattle, Washington USA. Materials in Nuclear Power. Plant ...

71

Steam Reheat in Nuclear Power Plants.  

E-Print Network (OSTI)

??In this work, reheating steam from a commercial nuclear power plant is explored in order to increase efficiency and power output. A thermal source in (more)

Marotta, Paul John

2012-01-01T23:59:59.000Z

72

First- and Second-Order Closure Models for Wind in a Plant Canopy  

Science Conference Proceedings (OSTI)

Katul and Chang recently compared the performance of two second-order closure models with observations of wind and turbulence in the Duke Forest canopy, noting that such models alleviate some of the theoretical objections to first-order closure....

J. D. Jean-Paul Pinard; John D. Wilson

2001-10-01T23:59:59.000Z

73

Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The nuclear power industry has entered into a voluntary initiative to implement groundwater monitoring programs at all nuclear power plant sites. This EPRI guideline provides essential technical guidance to nuclear power utilities on the necessary elements of a sound groundwater protection program.

2008-01-10T23:59:59.000Z

74

PROPOSED AMENDMENT TO THE NUCLEAR POWER PLANT  

E-Print Network (OSTI)

NOTE TO EDITORS: The Nuclear Regulatory Commission has received two reports from its independent Advisory Committee on Reactor Safeguards. The attached reports, in the form of letters, comment on a proposed amendment to the NRC's rule on license renewal for nuclear power plants and a proposed revision to the decommissioning rule for nuclear power reactors. Attachments:

T. S. Kress

1995-01-01T23:59:59.000Z

75

Pantex Plant | National Nuclear Security Administration  

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

Plant | National Nuclear Security Administration Plant | 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 Locations > Pantex Plant Pantex Plant http://www.pantex.com/ Field Office: The NNSA Production Office is responsible for contract management and oversight of the Pantex Plant in Amarillo, Texas and the Y-12 National Security Complex in Oak Ridge, Tenn. The Pantex Plant is

76

Nuclear Power Plant Concrete Structures  

Science Conference Proceedings (OSTI)

A nuclear power plant (NPP) involves complex engineering structures that are significant items of the structures, systems and components (SSC) important to the safe and reliable operation of the NPP. Concrete is the commonly used civil engineering construction material in the nuclear industry because of a number of advantageous properties. The NPP concrete structures underwent a great degree of evolution, since the commissioning of first NPP in early 1960. The increasing concern with time related to safety of the public and environment, and degradation of concrete structures due to ageing related phenomena are the driving forces for such evolution. The concrete technology underwent rapid development with the advent of chemical admixtures of plasticizer/super plasticizer category as well as viscosity modifiers and mineral admixtures like fly ash and silica fume. Application of high performance concrete (HPC) developed with chemical and mineral admixtures has been witnessed in the construction of NPP structures. Along with the beneficial effect, the use of admixtures in concrete has posed a number of challenges as well in design and construction. This along with the prospect of continuing operation beyond design life, especially after 60 years, the impact of extreme natural events ( as in the case of Fukushima NPP accident) and human induced events (e.g. commercial aircraft crash like the event of September 11th 2001) has led to further development in the area of NPP concrete structures. The present paper aims at providing an account of evolution of NPP concrete structures in last two decades by summarizing the development in the areas of concrete technology, design methodology and construction techniques, maintenance and ageing management of concrete structures.

Basu, Prabir [International Atomic Energy Agency (IAEA)] [International Atomic Energy Agency (IAEA); Labbe, Pierre [Electricity of France (EDF)] [Electricity of France (EDF); Naus, Dan [Oak Ridge National Laboratory (ORNL)] [Oak Ridge National Laboratory (ORNL)

2013-01-01T23:59:59.000Z

77

Plutonium Processing Plant Deactivated | National Nuclear Security  

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

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | 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 > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

78

Plutonium Processing Plant Deactivated | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | 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 > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

79

DOE Announces Loan Guarantee Applications for Nuclear Power Plant...  

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

Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis...

80

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

U.S. Energy Information Administration (EIA)

snpt3ny6122 581 4,948 97.2 PWR R E Ginna Nuclear Power Plant Unit Summer Capacity (MW) Net Generation (Thousand MWh) Summer Capacity Factor (Percent) Type

Note: This page contains sample records for the topic "nuclear plant closure" 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 Power Plant NDE Challenges Past, Present, and Future  

Science Conference Proceedings (OSTI)

The operating fleet of U.S. nuclear power plants was built to fossil plant standards (of workmanship

S. R. Doctor

2007-01-01T23:59:59.000Z

82

Plant Support Engineering: Elastomer Handbook for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

On a daily basis, engineers and maintenance personnel make judgments regarding the capabilities, degradation, and longevity of elastomeric material and its compatibility with other materials. Although most applications of elastomers in nuclear power plants are not unique to the industry, there is an extra emphasis in certain applications with regard to reliability, quality, and resistance to nuclear-plant-specific environments. Existing resources on elastomers are extensive, but they are not tailored to ...

2007-08-20T23:59:59.000Z

83

Kansas City Plant | 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 Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

84

Kansas City Plant | 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 Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

85

Project Prioritization for Nuclear Plant Investments  

Science Conference Proceedings (OSTI)

Evaluating investments, sometimes called project prioritization, is a central business process in a plant's or fleet's management of their nuclear assets. To date, a variety of project prioritization approaches have been used in the nuclear industry. Many nuclear utilities use an approach that can be characterized as an engineering work grading process. Project prioritization is related closely to long-range planning. Long-range plans help to avoid surprises from increased expenditures and reduced levels...

2008-12-23T23:59:59.000Z

86

Nuclear power plant construction activity, 1986  

SciTech Connect

Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

1987-07-24T23:59:59.000Z

87

The Politically Correct Nuclear Energy Plant  

E-Print Network (OSTI)

- and downstream processes Risks due to power plant emissions Coal Lignite Gas CC Nuclear PV (amorph) Wind Hydro-proliferation and waste. Then BUILD one! #12;Modular Pebble Bed Reactor Thermal Power 250 MW Core Height 10.0 m Core Product Barrier · Core Physics · Safety · Balance of Plant Design · Modularity Design · Core Power

88

Nuclear power plant construction activity 1987  

SciTech Connect

This annual report published by the Energy Information Administration (EIA) presents data on nuclear power plant construction activity. The previous report, Nuclear Power Plant Construction Activity 1986, included data for units that, as of December 31, 1986, were (1) in the construction pipeline, (2) canceled, or (3) commercial operation as of December 31, 1986. The data in this report, which were collected on Form EIA-254, ''Semiannual Report on Status of Reactor Construction,'' update the data in the previous report to be current as of December 31, 1987. Three types of information are included: plant characteristics and ownership; construction costs; and construction schedules and milestone dates.

1988-06-09T23:59:59.000Z

89

South Carolina Nuclear Profile - Power Plants  

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

South Carolina nuclear power plants, summer capacity and net generation, 2010" South Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Catawba Unit 1, Unit 2","2,258","18,964",36.5,"Duke Energy Carolinas, LLC" "H B Robinson Unit 2",724,"3,594",6.9,"Progress Energy Carolinas Inc" "Oconee Unit 1, Unit 2, Unit 3","2,538","20,943",40.3,"Duke Energy Carolinas, LLC" "V C Summer Unit 1",966,"8,487",16.3,"South Carolina Electric&Gas Co" "4 Plants 7 Reactors","6,486","51,988",100.0

90

Nuclear Power Plant Design Project  

E-Print Network (OSTI)

................................................. 22 5.1.16 Decommissioning: AP600, HTGR, ALWR ............................................................................................................... 35 7.3.4 Decommissioning Cost #12;9 decommissioning. The long delayed nuclear waste disposal facility at Yucca Mountain is becoming

91

Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond  

SciTech Connect

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

2009-11-09T23:59:59.000Z

92

ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND  

Science Conference Proceedings (OSTI)

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

Farfan, E.

2009-09-30T23:59:59.000Z

93

Missouri Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2mo Callaway Unit 1 1,190 8,996 100.0 Union Electric Co 1 Plant 1 Reactor Owner Note: Totals may not equal sum of components due to independent rounding.

94

Texas Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2tx Comanche Peak Unit 1, Unit 2 2,406 20,208 48.9 Luminant Generation Company LLC South Texas Project Unit 1, Unit 2 2,560 21,127 51.1 STP Nuclear Operating Co

95

Nuclear plant cancellations: causes, costs, and consequences  

Science Conference Proceedings (OSTI)

This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested.

Not Available

1983-04-01T23:59:59.000Z

96

The Integration of the 241-Z Building Decontamination and Decommissioning Under Cercla with RCRA Closure at the Plutonium Finishing Plant  

SciTech Connect

The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA) and Washington State Hazardous Waste Management Act, RCW 70.105, , have been deactivated and are being actively decommissioned under the provisions of the Hanford Federal Facility Agreement and Consent Order (HFFACO), RCRA and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 42 U.S.C. 9601 et seq. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4, D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building. The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground piping from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions will address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the Hanford Facility Dangerous Waste Closure Plan, 241-Z Treatment and Storage Tanks. Under the RCRA closure plan, the 241-Z TSD unit is anticipated to undergo clean closure to the performance standards of the State of Washington with respect to dangerous waste contamination from RCRA operations. The TSD unit will be clean closed if physical closure activities identified in the plan achieve clean closure standards for all 241-Z locations. Clean closed 241-Z treatment and storage tanks, equipment and/or structures will remain after RCRA clean closure for future disposition in conjunction with PFP decommissioning activities which are integrated with CERCLA. (authors)

Mattlin, E.; Charboneau, S. [U.S. Department of Energy, Richland Operations Office, Richland WA (United States); Johnston, G.; Hopkins, A.; Bloom, R.; Skeels, B.; Klos, D.B. [Fluor Hanford, Inc., Richland WA (United States)

2007-07-01T23:59:59.000Z

97

Seismic Isolation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

With increasing public concern for seismic safety in general and research findings that indicate that seismic hazards may be larger than expected in many parts of the world, it would be prudent for the nuclear industry to consider more fully the potential benefits, costs, and impediments associated with applying seismic isolation more widely and to identify actions needed to develop practical and cost-effective guidelines for the application of seismic isolation to nuclear power plants (NPPs) and ...

2013-10-28T23:59:59.000Z

98

Virtual environments for nuclear power plant design  

SciTech Connect

In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

1996-03-01T23:59:59.000Z

99

Holdup measurement for nuclear fuel manufacturing plants  

Science Conference Proceedings (OSTI)

The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

1981-07-13T23:59:59.000Z

100

Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report  

SciTech Connect

This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

1990-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Nuclear plant construction and investment risk  

SciTech Connect

Escalated cost estimations, delays and cancellations in nuclear construction have caused a preoccupation with the risks of nuclear power plant construction that dominates utility stock investment, overshadowing increased earnings per share and recent growth in production. The issue will be resolved when increased power demand requires new construction, but the effect has so far been to erode the economic advantage of nuclear power and threaten the ability of utilities to get rate increases high enough to cover their costs. Projected delays and cost escalations and their effects must go into an economic appraisal of the investment risks.

Studness, C.M.

1984-07-05T23:59:59.000Z

102

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

U.S. Energy Information Administration (EIA)

snpt3md6011 855 6,755 90.2 PWR 850 7,239 97.2 1,705 13,994 93.7 Calvert Cliffs Nuclear Power Plant Unit Type Data for 2010 PWR = Pressurized Light Water Reactor.

103

Addendum to the post-closure permit application for the Bear Creek hydrogeologic regime at the Y-12 plant: Walk-in pits  

SciTech Connect

In June 1987, the Resource Conservation and Recovery Act (RCRA) Closure/Post-Closure Plan for the Bear Creek Burial Grounds (BCBG) located at the Y-12 Plant on the Oak Ridge Reservation in Oak Ridge, Tennessee was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review and approval.The Closure Plan has been modified and revised several times. This document is an addendum to the Post-Closure Permit Application submitted to TDEC in June, 1994. This addendum contains information on the Walk-In Pits of the BCBG which is meant to supplement the information provided in the Post-Closure Permit Application submitted for the BCBG. This document is not intended to be a stand-alone document.

NONE

1995-04-01T23:59:59.000Z

104

Overview of Trends in Nuclear Power Plant Sensors and Instrumentation  

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

Trends in Nuclear Power Plant Sensors and Instrumentation SASAN BAKTIARI Nuclear Engineering Division Argonne National Laboratory Ph: (630) 252-8982 bakhtiati@anl.gov Abstract -...

105

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

U.S. Energy Information Administration (EIA)

... (kWh). There were 65 nuclear power plants with 104 operating nuclear reactors that generated a total of 790 billion kilowatt-hours (kWh), ...

106

Groundwater Monitoring Guidance for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Recent experience has shown that the initial design of nuclear power plant groundwater characterization programs can have a significant impact upon the resources needed to demonstrate regulatory compliance. This document provides technical experience and lessons learned in designing an optimized groundwater investigation program.

2005-09-06T23:59:59.000Z

107

International Cooperation on Safety of Nuclear Plants - Nuclear...  

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...

108

Evaluation of Site Investigation/Closure Requirements and Their Applicability to Residuals from Former Manufactured Gas Plants  

Science Conference Proceedings (OSTI)

Free product is defined as the concentration of non-aqueous phase liquid (NAPL) that is present in concentrations greater than the residual saturation point of the site media at a contaminated location. Identifying free product is important for the management of former Manufactured Gas Plant (MGP) sites because the free product is mobile and has the potential to migrate off site. The report provides a review of the regulatory programs for six states in the mid-west and northeast with regard to closure re...

2009-01-15T23:59:59.000Z

109

Trojan Nuclear Power Plant Reactor Vessel and Internals Removal: Trojan Nuclear Plant Decommissioning Experience  

Science Conference Proceedings (OSTI)

One goal of the EPRI Decommissioning Technology Program is to capture the growing utility experience in nuclear plant decommissioning activities for the benefit of other utilities facing similar challenges in the future. This report provides historical information on the background, scope, organization, schedule, cost, contracts, and support activities associated with the Trojan Nuclear Plant Reactor Vessel and Internals Removal (RVAIR) Project. Also discussed are problems, successes, and lessons learned...

2000-10-16T23:59:59.000Z

110

SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS  

E-Print Network (OSTI)

SIGNAL GROUPING FOR CONDITION MONITORING OF NUCLEAR POWER PLANT COMPONENTS Piero Baraldi between those used to monitor the reactor coolant pump of a Pressurized Water Reactor (PWR) is considered Monitoring, Empirical Modeling, Power Plants, Safety Critical Nuclear Instrumentation, Autoassociative models

111

Extended outages at several nuclear plants led to high outage ...  

U.S. Energy Information Administration (EIA)

Outages at U.S. nuclear power plants so far in 2012 are generally higher than in recent years because of extended forced outages at four nuclear power plants.

112

Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant  

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

NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

113

Engineering Fundamentals - Nuclear Power Plant Materials, Version 2.0  

Science Conference Proceedings (OSTI)

The Engineering Fundamentals - Nuclear Power Plant Materials (EF-Materials) Version 2.0 computer-based training module provides new-hire engineering personnel with an overview of the basic concepts of nuclear power plant materials. Graphics and interactive features are used to enhance learning.EF-Materials covers the basic terms and concepts related to nuclear power plant materials and provides information about the significance of material degradation issues in nuclear power plants. ...

2012-11-30T23:59:59.000Z

114

Advanced nuclear plant control room complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

115

THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM  

Science Conference Proceedings (OSTI)

Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphites thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical nuclear grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

William E. Windes; Timothy D. Burchell; Robert L. Bratton

2008-09-01T23:59:59.000Z

116

Nuclear Plant Life Cycle Management Implementation Guide  

Science Conference Proceedings (OSTI)

The day-to-day pressures of operation, limited budgets, and regulatory scrutiny of nuclear power plants focus on the present or short term, and may preempt cost-beneficial activities with long-term pay-off. This guide to implementing life-cycle management (LCM) fosters long-range thinking and decision making focused on profitability in the new competitive era of electricity production.

1998-11-19T23:59:59.000Z

117

Balance of Plant Requirements for a Nuclear Hydrogen Plant  

DOE Green Energy (OSTI)

This document describes the requirements for the components and systems that support the hydrogen production portion of a 600 megawatt thermal (MWt) Next Generation Nuclear Plant (NGNP). These systems, defined as the "balance-of-plant" (BOP), are essential to operate an effective hydrogen production plant. Examples of BOP items are: heat recovery and heat rejection equipment, process material transport systems (pumps, valves, piping, etc.), control systems, safety systems, waste collection and disposal systems, maintenance and repair equipment, heating, ventilation, and air conditioning (HVAC), electrical supply and distribution, and others. The requirements in this document are applicable to the two hydrogen production processes currently under consideration in the DOE Nuclear Hydrogen Initiative. These processes are the sulfur iodide (S-I) process and the high temperature electrolysis (HTE) process. At present, the other two hydrogen production process - the hybrid sulfur-iodide electrolytic process (SE) and the calcium-bromide process (Ca-Br) -are under flow sheet development and not included in this report. While some features of the balance-of-plant requirements are common to all hydrogen production processes, some details will apply only to the specific needs of individual processes.

Bradley Ward

2006-04-01T23:59:59.000Z

118

Nuclear power plant performance assessment pertaining to plant aging in France and the United States  

E-Print Network (OSTI)

The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant ...

Guyer, Brittany (Brittany Leigh)

2013-01-01T23:59:59.000Z

119

Korea Hydro & Nuclear Power Co., Ltd. Nuclear Power Plants: Construction and Technology Experience  

Science Conference Proceedings (OSTI)

The Korean nuclear power industry has grown rapidly since Kori Unit 1, the first Korean nuclear power plant (NPP), which began operation in April 1978. Following the technology developments of the nuclear power industry in 1980s, the first standard Korean nuclear plants (Ulchin Units 3 and 4) were constructed in the 1990s. At present, 20 NPP units operate in Korea16 pressurized water reactor (PWR) plants and four pressurized heavy water reactor (PHWR) plants; eight PWR units are under construction. This ...

2011-09-21T23:59:59.000Z

120

Analysis of nuclear power plant construction costs  

SciTech Connect

The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Secretary Chu Visits Vogtle Nuclear Power Plant | Department of Energy  

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

Vogtle Nuclear Power Plant Vogtle Nuclear Power Plant Secretary Chu Visits Vogtle Nuclear Power Plant February 15, 2012 - 3:54pm Addthis Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in the United States in three decades. | Image credit: Southern Company. Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in the United States in three decades. | Image credit: Southern Company. Niketa Kumar Niketa Kumar Public Affairs Specialist, Office of Public Affairs Just over 60 years ago, scientists in Arco, Idaho, successfully used nuclear energy to power four light bulbs, laying the foundation for U.S.

122

Nuclear Plant Analyzer: Installation manual. Volume 1  

SciTech Connect

This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays.

Snider, D.M.; Wagner, K.L.; Grush, W.H.; Jones, K.R. [Idaho National Engineering Lab., Idaho Falls, ID (United States)]|[Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-01-01T23:59:59.000Z

123

Sources of Stress in Latino Women Experiencing Unemployment After a Plant Closure  

E-Print Network (OSTI)

1985 Economic and social impact of plant closings and jobsomatization), (10) Social Impact of Job Loss, and (11)

Castro, Felipe; Romero, Gloria; Cervantes, Richard C.

1986-01-01T23:59:59.000Z

124

Recent Progress in U.S. Nuclear Power Plant Safety  

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

Recent Progress in U.S. Nuclear Power Plant Safety Speaker(s): Robert Budnitz Date: April 15, 2010 - 12:00pm Location: 90-3122 The U.S. commercial nuclear-power industry consists...

125

Electromagnetic Compatibility in Nuclear Power Plants  

SciTech Connect

Electromagnetic compatibility (EMC) has long been a key element of qualification for mission critical instrumentation and control (I&C) systems used by the U.S. military. The potential for disruption of safety-related I&C systems by electromagnetic interference (EMI), radio-frequency interference (RFI), or power surges is also an issue of concern for the nuclear industry. Experimental investigations of the potential vulnerability of advanced safety systems to EMI/RFI, coupled with studies of reported events at nuclear power plants (NPPs) that are attributed to EMI/RFI, confirm the safety significance of EMC for both analog and digital technology. As a result, Oak Ridge National Laboratory has been engaged in the development of the technical basis for guidance that addresses EMC for safety-related I&C systems in NPPs. This research has involved the identification of engineering practices to minimize the potential impact of EMI/RFI and power surges and an evaluation of the ambient electromagnetic environment at NPPs to tailor those practices for use by the nuclear industry. Recommendations for EMC guidance have been derived from these research findings and are summarized in this paper.

Ewing, P.D.; Kercel, S.W.; Korsah, K.; Wood, R.T.

1999-08-29T23:59:59.000Z

126

Sensitivity analysis for the outages of nuclear power plants  

E-Print Network (OSTI)

Feb 17, 2012 ... Abstract: Nuclear power plants must be regularly shut down in order to perform refueling and maintenance operations. The scheduling of the...

127

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

U.S. Energy Information Administration (EIA)

How much electricity does a typical nuclear power plant generate? ... tariff, and demand charge data? How is electricity used in U.S. homes?

128

Need for process/radiochemists at nuclear power plants  

SciTech Connect

Viewgraphs are presented concerning the operating requirements for chemists at nuclear power plants. The number of positions available, job duties, and training requirements are reviewed.

Wymer, R.G.; Skrable, K.W.; Alexander, E.L.

1984-01-01T23:59:59.000Z

129

Guideline for Online Monitoring of Nuclear Power Plants: Volume 2  

Science Conference Proceedings (OSTI)

This report continues a series of guidelines that assist member utilities in developing an online monitoring (OLM) program for equipment condition assessment at nuclear power plants.

2011-12-16T23:59:59.000Z

130

MANAGING MODERNIZATION OF NUCLEAR POWER PLANT INSTRUMENTATION AND CONTROL SYSTEMS  

E-Print Network (OSTI)

Managing modernization of nuclear power plant instrumentation and control systems February 2004The originating Section of this publication in the IAEA was:

unknown authors

2003-01-01T23:59:59.000Z

131

Risk-informed incident management for nuclear power plants  

E-Print Network (OSTI)

Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

Smith, Curtis Lee, 1966-

2002-01-01T23:59:59.000Z

132

Tools for Closure Project and Contract Management: Development of the Rocky Flats Integrated Closure Project Baseline  

Science Conference Proceedings (OSTI)

This paper details the development of the Rocky Flats Integrated Closure Project Baseline - an innovative project management effort undertaken to ensure proactive management of the Rocky Flats Closure Contract in support of the Department's goal for achieving the safe closure of the Rocky Flats Environmental Technology Site (RFETS) in December 2006. The accelerated closure of RFETS is one of the most prominent projects within the Department of Energy (DOE) Environmental Management program. As the first major former weapons plant to be remediated and closed, it is a first-of-kind effort requiring the resolution of multiple complex technical and institutional challenges. Most significantly, the closure of RFETS is dependent upon the shipment of all special nuclear material and wastes to other DOE sites. The Department is actively working to strengthen project management across programs, and there is increasing external interest in this progress. The development of the Rocky Flats Integrated Closure Project Baseline represents a groundbreaking and cooperative effort to formalize the management of such a complex project across multiple sites and organizations. It is original in both scope and process, however it provides a useful precedent for the other ongoing project management efforts within the Environmental Management program.

Gelles, C. M.; Sheppard, F. R.

2002-02-26T23:59:59.000Z

133

Inspection of Nuclear Power Plant Containment Structures  

SciTech Connect

Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

Graves, H.L.; Naus, D.J.; Norris, W.E.

1998-12-01T23:59:59.000Z

134

Pantex Plant | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Locations > Pantex Plant Pantex Plant http:www.pantex.com Field Office: The NNSA Production Office is responsible for contract management and oversight of the Pantex Plant in...

135

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01T23:59:59.000Z

136

Nuclear Power Plant Fire-Modeling Applications Guide  

Science Conference Proceedings (OSTI)

This report replaces EPRI 1002981, Fire Modeling Guide for Nuclear Power Plant Applications, August 2002, as guidance for fire-modeling practitioners in nuclear power plants (NPPs). The report has benefited from insights gained since 2002 on the predictive capability of selected fire models to improve confidence in the use of fire modeling in NPP decision-making.

2009-12-22T23:59:59.000Z

137

Welding and Fabrication Critical Factors for New Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Welding and fabrication processes employed for manufacture of critical nuclear power plant components may adversely affect material performance and can potentially increase susceptibility to known degradation mechanisms. This report identifies important welding and fabrication processes for specific materials, assesses their effects on potential degradation mechanisms, and identifies process enhancements that can improve long-term asset management of new nuclear plant components.

2009-12-08T23:59:59.000Z

138

Groundwater Sampling and Analysis Sourcebook for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This sourcebook provides technical guidance and best practices for groundwater sampling and analysis at nuclear power plants. Robust sampling and analysis protocols are required to ensure accurate characterization of radionuclides in groundwater.BackgroundNuclear power plants implement groundwater protection programs to minimize contamination of on-site soil and groundwater, and to prevent the off-site migration of licensed material through groundwater ...

2012-09-25T23:59:59.000Z

139

Review of Polyimide Insulated Wire in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Because of its toughness and other desirable properties, Kapton insulated wire has been test-qualified for use in nuclear power plants; however, failures of this material in military aircraft have raised safety questions. This report identifies the conditions of proper use and handling that will ensure reliable functioning of the wire under nuclear plant operating and accident conditions.

1991-03-01T23:59:59.000Z

140

Nevada Test Site closure program  

SciTech Connect

This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada Test Site. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use.

Shenk, D.P.

1994-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

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

142

Financial and ratepayer impacts of nuclear power plant regulatory reform  

SciTech Connect

Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports.

Turpin, A.G.

1985-01-01T23:59:59.000Z

143

Some aspects of the decommissioning of nuclear power plants  

SciTech Connect

The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

Khvostova, M. S., E-mail: marinakhvostova@list.ru [St. Petersburg State Maritime Technical University (Sevmashvtuz), Severodvinsk Branch (Russian Federation)

2012-03-15T23:59:59.000Z

144

Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants |  

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

Feasibility Study of Hydrogen Production at Existing Nuclear Power Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants A funding opportunity announcement of the cost shared feasibility studies of nuclear energy based production of hydrogen using available technology. The objective of this activity is to select and conduct project(s) that will utilize hydrogen production equipment and nuclear energy as necessary to produce data and analysis on the economics of hydrogen production with nuclear energy. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants More Documents & Publications https://e-center.doe.gov/iips/faopor.nsf/UNID/E67E46185A67EBE68 Microsoft Word - FOA cover sheet.doc Microsoft Word - hDE-FOA-0000092.rtf

145

Program Change Management During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear power plant is a complex project, which involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As plants meet certain project Milestones, the evolution of such plant programs and regulations can help optimize project execution and cost. This report provides information about these Milestones and the plant departments and programs that change throughout a decommissioning project.

2009-12-11T23:59:59.000Z

146

Guidelines for Nuclear Plant Response to an Earthquake  

Science Conference Proceedings (OSTI)

Guidelines for nuclear plant response to earthquakes enable utilities to evaluate in a timely manner the need for post-earthquake plant shutdown and to provide procedures for evaluation of earthquake effects on the plant, as well as criteria for plant restart. The procedures enable the responding team of operators and engineers to identify and assess any earthquake effects and, if shutdown is necessary, to return the plant to safe operation as rapidly as possible. The guidelines presented herein ...

2013-10-15T23:59:59.000Z

147

Guidelines for Nuclear Plant Response to an Earthquake  

Science Conference Proceedings (OSTI)

Guidelines for nuclear plant response to earthquakes enable utilities to evaluate in a timely manner the need for post-earthquake plant shutdown and to provide procedures for evaluation of earthquake effects on the plant, as well as criteria for plant restart. The procedures enable the responding team of operators and engineers to identify and assess any earthquake effects and, if shutdown is necessary, to return the plant to safe operation as rapidly as possible. The guidelines presented herein ...

2012-10-11T23:59:59.000Z

148

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plants: Industry Recommendations for Design  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries. Good initial and continued performance is vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

149

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

Nuclear power provides about 20 % of the total electricity generated in the United States. In 2005, this was about 782 Billion kWh of the total electricity generation (EIA 2006). 2 As with fossil-fueled electricity generating plants, electricity in a nuclear power plant is produced by heated steam that drives a turbine generator. In a nuclear power plant, however, nuclear fission reactions in the core produce heat that is absorbed by a liquid that flows through the system and is converted to steam. Nuclear power plants are highly efficient and have become more so over the last 25 years. Operational efficiency (also referred to as plant performance or electricity production) can be measured by the capacity factor. The capacity factor is the ratio of the actual amount of electricity generated to the maximum possible amount that could be generated in a given period of time usually a year. Today, nuclear power plants operate at an average 90 % capacity factor (compared to 56 % in 1980) (EIA 2006a). Thus, although nuclear generating capacity has remained roughly constant since 1990, at about 99 gigawatts (or about 10 % of the total U.S. electric generating capacity), the amount of electricity produced has increased 33 % since that time because of increased capacity utilization. Nuclear plants have the highest capacity factors of

unknown authors

2006-01-01T23:59:59.000Z

150

A Dynamical Systems Model for Nuclear Power Plant Risk Management  

Science Conference Proceedings (OSTI)

This report provides a mathematical dynamical systems model of the effect of plant processes and programs on nuclear plant safety. That is, it models the safety risk management process. Responses of this model to postulated changes in performance and coupling parameters were verified to be in accordance with experience from years of commercial nuclear power plant operation. A preliminary analysis of the model was performed using the techniques of dynamical systems theory to determine regions of operation...

2003-10-31T23:59:59.000Z

151

Tenth Nuclear Plant Performance Improvement (NPPI) Seminar Proceedings  

Science Conference Proceedings (OSTI)

This report contains information presented at the Tenth Nuclear Plant Performance Improvement (NPPI) Seminar held July 15-16, 2002, in Saratoga Springs, New York. The biannual seminar -- sponsored by EPRI Plant Support Engineering (PSE), EPRI Plant Performance Enhancement Program (P2EP), and Rochester Gas and Electric -- provided an opportunity for participants to exchange technical information and experience regarding the achievement of the highest possible megawatt electric (MWe) output from nuclear po...

2002-08-15T23:59:59.000Z

152

Tank Closure  

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

Topics 3 Overview of SRS Tank Closure Program Two Tank Farms - F Area and H Area Permitted by SC as Industrial Wastewater Facilities under the Pollution Control...

153

Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents  

Science Conference Proceedings (OSTI)

Nuclear power plants report the amount of radioactivity released through permitted effluent pathways in their plant annual reports. This report provides users with a method for calculating the amount of carbon-14 (14C) generated in a light water reactor (LWR) core and released through plant gaseous effluent pathways.

2010-12-21T23:59:59.000Z

154

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

155

Groundwater Protection Guidelines for Nuclear Power Plants: Revision 1  

Science Conference Proceedings (OSTI)

The United States nuclear power industry has undertaken a Groundwater Protection Initiative [NEI 07-07] at the direction of the Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC). International nuclear power plants implement groundwater protection programs to ensure appropriate management of on-site groundwater and protection of the public and environment. This Electric Power Research Institute (EPRI) guideline provides essential technical guidance to utilities on the ...

2013-10-29T23:59:59.000Z

156

Plant Engineering: Advanced Nuclear Plant Cable System Design and Installation Concepts to Assure Longevity  

Science Conference Proceedings (OSTI)

Although the electrical cable systems for existing nuclear power plants have functioned well for up to 40 years, the desired service life for new plants is 60 or more years. Experience with existing plants indicates that relatively small changes during the design and construction of nuclear plants will lead to longer cable system lives and greater ease of testing and assessment of cables to verify their remaining service life. This report describes those changes and provides recommendations for their imp...

2012-04-16T23:59:59.000Z

157

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

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

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

158

DOE Announces Loan Guarantee Applications for Nuclear Power Plant  

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

DOE Announces Loan Guarantee Applications for Nuclear Power Plant DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it has received 19 Part I applications from 17 electric power companies for federal loan guarantees to support the construction of 14 nuclear power plants in response to its June 30, 2008 solicitation. The applications reflect the intentions of those companies to build 21 new reactors, with some applications covering two reactors at the same site. All five reactor designs that have been certified, or are currently under review for possible certification, by the Nuclear Regulatory Commission (NRC) are

159

Guidance for Deployment of Mobile Technologies for Nuclear Power Plant  

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

Guidance for Deployment of Mobile Technologies for Nuclear Power Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers This report is a guidance document prepared for the benefit of commercial nuclear power plants' (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making,

160

DOE Announces Loan Guarantee Applications for Nuclear Power Plant  

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

Loan Guarantee Applications for Nuclear Power Plant Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it has received 19 Part I applications from 17 electric power companies for federal loan guarantees to support the construction of 14 nuclear power plants in response to its June 30, 2008 solicitation. The applications reflect the intentions of those companies to build 21 new reactors, with some applications covering two reactors at the same site. All five reactor designs that have been certified, or are currently under review for possible certification, by the Nuclear Regulatory Commission (NRC) are represented in the Part I applications. DOE also has received Part I

Note: This page contains sample records for the topic "nuclear plant closure" 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

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

Industry Participation Sought for Design of Next Generation Nuclear Industry Participation Sought for Design of Next Generation Nuclear Plant Industry Participation Sought for Design of Next Generation Nuclear Plant June 29, 2006 - 2:41pm Addthis Gen IV Reactor Capable of Producing Electricity and/or Hydrogen WASHINGTON, DC - The U.S. Department of Energy (DOE) is seeking expressions of interest from prospective industry teams interested in participating in the development and conceptual design for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled nuclear reactor prototype with the capability to produce process heat, electricity and/or hydrogen. The very high temperature reactor is based on research and development activities supported by DOE's Generation IV nuclear energy systems initiative.

162

Mesoscale to plant-scale models of nuclear waste reprocessing.  

Science Conference Proceedings (OSTI)

Imported oil exacerabates our trade deficit and funds anti-American regimes. Nuclear Energy (NE) is a demonstrated technology with high efficiency. NE's two biggest political detriments are possible accidents and nuclear waste disposal. For NE policy, proliferation is the biggest obstacle. Nuclear waste can be reduced through reprocessing, where fuel rods are separated into various streams, some of which can be reused in reactors. Current process developed in the 1950s is dirty and expensive, U/Pu separation is the most critical. Fuel rods are sheared and dissolved in acid to extract fissile material in a centrifugal contactor. Plants have many contacts in series with other separations. We have taken a science and simulation-based approach to develop a modern reprocessing plant. Models of reprocessing plants are needed to support nuclear materials accountancy, nonproliferation, plant design, and plant scale-up.

Noble, David Frederick; O'Hern, Timothy John; Moffat, Harry K.; Nemer, Martin B.; Domino, Stefan Paul; Rao, Rekha Ranjana; Cipiti, Benjamin B.; Brotherton, Christopher M.; Jove-Colon, Carlos F.; Pawlowski, Roger Patrick

2010-09-01T23:59:59.000Z

163

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  

E-Print Network (OSTI)

Generating Plant. The enclosed report documents the inspection findings which were discussed on February 22, 2001, with you and other members of your staff. This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, the inspectors identified two issues of very low safety significance (Green). One of these issues was determined to involve a violation of NRC requirements. However, because of its very low safety significance and because it has been entered into your corrective action program, the NRC is treating the issue as a non-cited violation, in accordance with Section VI.A.1 of the NRCs Enforcement Policy. If you deny the non-cited violation, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator,

Dear Mr. Sorensen; Roger D. Lanksbury

2001-01-01T23:59:59.000Z

164

Tank Closure  

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

Closure Closure Sherri Ross Waste Removal and Tank Closure Waste Disposition Project Programs Division Savannah River Operations Office Presentation to the DOE HLW Corporate Board 2  Overview and Status of SRS Tank Closure Program  Issues/Challenges  Communications  Schedule Performance  Ceasing Waste Removal  Compliance with SC Water Protection Standards  Questions? Topics 3 Overview of SRS Tank Closure Program  Two Tank Farms - F Area and H Area  Permitted by SC as Industrial Wastewater Facilities under the Pollution Control Act  Three agency Federal Facility Agreement (FFA)  DOE, SCDHEC, and EPA  51 Tanks  24 old style tanks (Types I, II and IV)  Do not have full secondary containment  FFA commitments to close by 2022  2 closed in 1997

165

Loss of benefits resulting from mandated nuclear plant shutdowns  

SciTech Connect

This paper identifies and discusses some of the important consequences of nuclear power plant unavailability, and quantifies a number of technical measures of loss of benefits that result from regulatory actions such as licensing delays and mandated nuclear plant outages. The loss of benefits that accompany such regulatory actions include increased costs of systems generation, increased demand for nonnuclear and often scarce fuels, and reduced system reliability. This paper is based on a series of case studies, supplemented by sensitivity studies, on hypothetical nuclear plant shutdowns. These studies were developed by Argonne in cooperation with four electric utilities.

Peerenboom, J.P.; Buehring, W.A.

1982-01-01T23:59:59.000Z

166

New Jersey Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2nj Oyster Creek Unit 1 615 4,601 14.0 Exelon Nuclear PSEG Hope Creek Generating Station Unit 1 1,161 9,439 28.8 PSEG Nuclear LLC PSEG Salem Generating Station

167

A CCA-compliant nuclear power plant simulator kernel  

Science Conference Proceedings (OSTI)

This paper presents a parallel, component-oriented nuclear power plant simulator kernel. It is based on the high-performance computing oriented Common Component Architecture. The approach takes advantage of both the component paradigm and the parallel ...

Manuel Daz; Daniel Garrido; Sergio Romero; Bartolom Rubio; Enrique Soler; Jos M. Troya

2005-05-01T23:59:59.000Z

168

Mapping complexity sources in nuclear power plant domains  

E-Print Network (OSTI)

Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical for ensuring safe performance of both operators and the entire system. New ...

Sasangohar, Farzan

169

Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants  

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

Federal Risk Insurance for Nuclear Power Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy August 4, 2006 - 8:42am Addthis ATLANTA, GA - After touring Georgia Power and speaking to its employees, U.S. Department of Energy (DOE) Secretary Samuel W. Bodman today announced completion of the final rule that establishes the process for utility companies building the next six new nuclear power plants in the United States to qualify for a portion of $2 billion in federal risk insurance. The rule will be available on DOE's web site soon. "Providing federal risk insurance is an important step in speeding the nuclear renaissance in this country," Secretary Bodman said. "Companies

170

Closure report for N Reactor  

SciTech Connect

This report has been prepared to satisfy Section 3156(b) of Public Law 101-189 (Reports in Connection with Permanent Closures of Department of Energy Defense Nuclear Facilities), which requires submittal of a Closure Report to Congress by the Secretary of Energy upon the permanent cessation of production operations at a US Department of Energy (DOE) defense nuclear facility (Watkins 1991). This closure report provides: (1) A complete survey of the environmental problems at the facility; (2) Budget quality data indicating the cost of environmental restoration and other remediation and cleanup efforts at the facility; (3) A proposed cleanup schedule.

Not Available

1994-01-01T23:59:59.000Z

171

Training Module for Cyber Security in Nuclear Plant Digital Modifications  

Science Conference Proceedings (OSTI)

Nuclear power plants face increasing regulatory requirements from the U.S. Nuclear Regulatory Commission (NRC) and the Federal Energy Regulatory Commission (FERC) for cyber security of digital devices, components, and systems. The focus of these cyber security requirements is to protect plant digital computer systems, communications systems, and networks from cyber attacks that would affect reactor safety or generation reliability. This Electric Power Research Institute (EPRI) computer-based training mod...

2011-04-28T23:59:59.000Z

172

Advanced Sensor Diagnostics in Nuclear Power Plant Applications  

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

Sensor Diagnostics in Nuclear Power Plant Applications Sensor Diagnostics in Nuclear Power Plant Applications R.B. Vilim Argonne National Laboratory Sensor degradation occurs routinely during nuclear power plant operation and can contribute to reduced power production and less efficient plant operation. Mechanisms include drift of sensor electronics and mechanical components, fouling and erosion of flow meter orifice plates, and general degradation of thermocouples. One solution to this problem is the use of higher quality instrumentation and of physical redundancy. This, however, increases plant cost and does not address the degradation problem in a fundamental way. An alternative approach is to use signal processing algorithms to detect a degraded sensor and to construct a replacement value using an

173

Y-12 PLANT NUCLEAR SAFETY HANDBOOK  

SciTech Connect

Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

Wachter, J.W. ed.; Bailey, M.L.; Cagle, T.J.; Mee, W.T.; Pletz, R.H.; Welfare, F.G.; Youngblood, B.J. comps

1963-03-27T23:59:59.000Z

174

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

175

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

176

Qinshan: China`s first nuclear power plant  

SciTech Connect

Plant design, startup, and operation of the Qinshan-1 nuclear power plant in China are outlined in this article. Qinshan-1 is a 300 MW(e) pressurized water reactor designed and constructed in China. Approximately 70 percent of the equipment was also made in China. Findings of a preoperational safety inspection by the International Atomic Energy Agency are summarized.

NONE

1992-08-01T23:59:59.000Z

177

Life Expectancy of Motors in Mild Nuclear Plant Environments  

Science Conference Proceedings (OSTI)

Predicted life expectancies of commercial-grade motors used in the milder environments of nuclear power plants indicate that those motors can last for the life of the plant if properly maintained. This report details methods by which utilities can make such predictions and supplies the extensive data on which the analytic techniques are based.

1985-02-21T23:59:59.000Z

178

Data Mining for Monitoring Loose Parts in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Monitoring the mechanical impact of a loose (detached or drifting) part in the reactor coolant system of a nuclear power plant is one of the essential functions for operation and maintenance of the plant.Large data tables are generated during this monitoring ...

J. W. Guan; David A. Bell

2000-10-01T23:59:59.000Z

179

Atmospheric Deposition of Tritium at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Tritium source terms at nuclear power plants consist of several sources that include plant vents and cooling impoundments, cooling towers, and treatment ponds. Cooling lakes and reservoirs can be sources of airborne tritium. Methods are presented for estimating these source terms and predicting resulting deposition of tritium using metrological models and for estimating infiltration of tritium using hydrogeological models.

2010-12-16T23:59:59.000Z

180

Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The nuclear power industry has undertaken a Groundwater Protection Initiative at the Direction of the NEI Nuclear Strategic Issues Advisory Committee (NSIAC). This EPRI guideline provides essential technical guidance to utilities on the necessary elements of a sound groundwater protection program.

2007-11-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Calibration of Radiation Monitors at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Radiation monitors are installed in nuclear power plants to indicate to operators the levels of radioactivity in various processes and at specific plant locations. Plant personnel depend on radiation monitors for accurate and precise data in order to make informed decisions and take appropriate actions during normal, abnormal, and design basis events. As with all electronic measurement systems, error can be introduced by changing environmental conditions, aging components, and replaced parts. The radiati...

2005-12-22T23:59:59.000Z

182

Use of expert systems in nuclear power plants  

SciTech Connect

The application of technologies, particularly expert systems, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which expert systems can increase the efficiency and effectiveness of overall plant and corporate operations. This document presents a number of potential applications of expert systems in the nuclear power field. 36 refs., 2 tabs.

Uhrig, R.E.

1989-01-01T23:59:59.000Z

183

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant,  

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

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts associated with the U.S. Department of Energy proposed action to conduct a lead test assembly program to confirm the viability of using a commercial light water reactor to produce tritium. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 22, 1997 EA-1210: Finding of No Significant Impact Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington July 22, 1997 EA-1210: Final Environmental Assessment

184

Nuclear plant owners move closer to life extension  

Science Conference Proceedings (OSTI)

A major debate is now underway about the safety of 40-year-old nuclear power plants. Under the Atomic Energy Act of 1954 a nuclear power plant's license is limited to a maximum of 40 years. Although the act permits the renewal of an operating license, it does not outline any standards or procedures for determining when or under what conditions a plant's operating license should be renewed. This paper reports that the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) are co-sponsors of a program to demonstrate the license renewal process for two nuclear power plants - Yankee Atomic Electric's 175-MW Yankee PWR plant and Northern States Power's 536-MW Monticello BWR plant. The demonstration is known as the lead plant project. Yankee Atomic has already analyzed the plant's condition and evaluated aging using computer-based expert systems and the plant's operating experience. During these tests Yankee Atomic found embrittlement of the reactor vessel.

Smith, D.J.

1991-10-01T23:59:59.000Z

185

How many nuclear power plants are in the U.S. and where are they ...  

U.S. Energy Information Administration (EIA)

How many nuclear power plants are in the U.S. and where are they located? There are currently 65 commercially operating nuclear power plants with 104 nuclear reactors ...

186

Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant  

Science Conference Proceedings (OSTI)

Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low.

RECHARD,ROBERT P.; SANCHEZ,LAWRENCE C.; STOCKMAN,CHRISTINE T.; TRELLUE,HOLLY R.

2000-04-01T23:59:59.000Z

187

The Next Generation Nuclear Plant (NGNP) Project  

DOE Green Energy (OSTI)

The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOEs project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10 CFR 52, for the purpose of demonstrating the suitability of high-temperature gas-cooled reactors for commercial electric power and hydrogen production. Products that will support the licensing of the NGNP include the environmental impact statement, the preliminary safety analysis report, the NRC construction permit, the final safety analysis report, and the NRC operating license. The fuel development and qualification program consists of five elements: development of improved fuel manufacturing technologies, fuel and materials irradiations, safety testing and post-irradiation examinations, fuel performance modeling, and fission product transport and source term modeling. Two basic approaches will be explored for using the heat from the high-temperature helium coolant to produce hydrogen. The first technology of interest is the thermochemical splitting of water into hydrogen and oxygen. The most promising processes for thermochemical splitting of water are sulfur-based and include the sulfur-iodine, hybrid sulfur-electrolysis, and sulfur-bromine processes. The second technology of interest is thermally assisted electrolysis of water. The efficiency of this process can be substantially improved by heating the water to high-temperature steam before applying electrolysis.

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

188

Nuclear dual-purpose plants for industrial energy  

SciTech Connect

One of the major obstacles to extensive application of nuclear power to industrial heat is the difference between the relatively small energy requirements of individual industrial plants and the large thermal capacity of current power reactors. A practical way of overcoming this obstacle would be to operate a centrally located dual-purpose power plant that would furnish process steam to a cluster of industrial plants, in addition to generating electrical power. The present study indicates that even relatively remote industrial plants could be served by the power plant, since it might be possible to convey steam economically as much as ten miles or more. A survey of five major industries indicates a major potential market for industrial steam from large nuclear power stations.

Klepper, O.H.

1976-01-01T23:59:59.000Z

189

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

190

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

191

Advanced Cooling Options for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Alternative power plant cooling systems exist that offer significant opportunity for reducing the amount of water used in power plant cooling. These systems include direct dry cooling using air-cooled condensers, indirect dry cooling using air-cooled heat exchangers paired with water-cooled surface condensers, and a variety of hybrid systems incorporating both dry and wet cooling elements. The water savings afforded by the use of these systems, however, comes at a price in the form of more expensive ...

2013-11-27T23:59:59.000Z

192

Advanced Nuclear Technology: Equipment Reliability for New Nuclear Plant Projects: Industry Recommendations for Storage, Construction, and Testing  

Science Conference Proceedings (OSTI)

The initial and continued good operating performance of the current build of new nuclear plants is critical to the rebirth of the nuclear option in many countries and vital to the companies making the large investments required for new nuclear plants. One of the foundations of good performance is a sound process for establishing and sustaining plant equipment reliability (ER).

2010-08-26T23:59:59.000Z

193

Nuclear Power Plant Containment Pressure Boundary Research  

SciTech Connect

Research to address aging of the containment pressure boundary in light-water reactor plants is summarized. This research is aimed at understanding the significant factors relating occurrence of corrosion, efficacy of inspection, and structural capacity reduction of steel containment and liners of concrete containment. This understanding will lead to improvements in risk-informed regulatory decision making. Containment pressure boundary components are described and potential aging factors identified. Quantitative tools for condition assessments of aging structures to maintain an acceptable level of reliability over the service life of the plant are discussed. Finally, the impact of aging (i.e., loss of shell thickness due to corrosion) on steel containment fragility for a pressurized water reactor ice-condenser plant is presented.

Cherry, J.L.; Chokshi, N.C.; Costello, J.F.; Ellingwood, B.R.; Naus, D.J.

1999-09-15T23:59:59.000Z

194

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This Technology Update documents the Next Generation Nuclear Plant (NGNP) project, which will demonstrate the design, licensing, construction, and operation of a new nuclear energy source using high-temperature gas-cooled reactor (HTGR) technology. This new non-emitting energy source is applicable to a broad range of uses, from generating electricity to providing high-temperature industrial process heat to producing hydrogen. The NGNP project is sponsored as part of the Energy Policy Act of 2005 and envi...

2008-12-15T23:59:59.000Z

195

Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG)  

Science Conference Proceedings (OSTI)

There is a movement to introduce risk-informed and performance-based (RI/PB) analyses into fire protection engineering practice, both domestically and worldwide. This movement exists in both the general fire protection and the nuclear power plant (NPP) fire protection communities. The U.S. Nuclear Regulatory Commission (NRC) has used risk-informed insights as a part of its regulatory decision making since the 1990s.In 2001, the National Fire Protection Association (NFPA) ...

2012-11-30T23:59:59.000Z

196

Materials Handbook for Nuclear Plant Pressure Boundary Applications (2013)  

Science Conference Proceedings (OSTI)

Utility engineers require accurate structural materials properties and performance data to make decisions regarding the adequacy of materials for nuclear power applications. To meet this need, the Electric Power Research Institute (EPRI) publishes the Materials Handbook for Nuclear Plant Pressure Boundary Applications, which has been updated and revised since its initial publication in 1998. The primary focus of the handbook is on pressure boundary materials such as those used for piping ...

2013-03-28T23:59:59.000Z

197

Effect of Nuclear Power Plant Decommissioning Costs on Plant Life Cycle Decisions  

Science Conference Proceedings (OSTI)

Nuclear utilities implementing Life Cycle Management (LCM) Programs and facing run-relicense-retire decisions need to evaluate the financial cost/benefit of such decisions. Decommissioning costs are one element of these evaluations. This report includes a decommissioning cost estimate for Calvert Cliffs Nuclear Power Plant (CCNPP) that can be used as a reference source by nuclear utilities involved in LCM and license renewal (LR) decisions.

1995-07-01T23:59:59.000Z

198

Plant Engineering: Predicting Nuclear Plant Output from Performance Losses and Gains  

Science Conference Proceedings (OSTI)

The marginal costs of generating electricity, together with the strong emphasis on maximizing production at today's nuclear power generating units, have increased the need for nuclear plant thermal performance engineers (TPEs) to determine the gap between the station's actual performance and its ultimate capability. This report from the Electric Power Research Institute (EPRI) outlines the various items that influence the performance of a nuclear unit and gives the TPE methods to employ in estimating the...

2011-12-15T23:59:59.000Z

199

Toshiba's developments on construction techniques of nuclear power plants  

SciTech Connect

Reliable and economic energy supplies are fundamental requirements of energy policies in Japan. To accomplish these needs, nuclear power plants are being increased in Japan. In recent years, construction cost increases and schedule extensions have affected the capital cost of nuclear energy, compared with fossil power plants, due to lower costs of oil and coal. On the other hand, several severe regulations have been applied to nuclear power plant designs. High-quality and cooperative engineering and harmonized design of equipment and parts are strongly required. Therefore, reduced construction costs and scheduling, as well as higher quality and reliability, are the most important items for nuclear industry. Toshiba has developed new construction techniques, as well as design and engineering tools for control and management, that demonstrate the positive results achieved in the shorter construction period of 1100-MW(electric) nuclear power plants. The normal construction period so far is 64 months, whereas the current construction period is 52 months. (New construction techniques are partially applied). In future years, the construction period will be lowered to 48 months. (New construction techniques are fully applied). A construction period is defined as time from the start of rock inspection to the start of commercial operation.

Hayashi, Y.; Itoh, N.

1987-01-01T23:59:59.000Z

200

Report on aging of nuclear power plant reinforced concrete structures  

Science Conference Proceedings (OSTI)

The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1996-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Fire models for assessment of nuclear power plant fires  

SciTech Connect

This paper reviews the state-of-the-art in available fire models for the assessment of nuclear power plants fires. The advantages and disadvantages of three basic types of fire models (zone, field, and control volume) and Sandia's experience with these models will be discussed. It is shown that the type of fire model selected to solve a particular problem should be based on the information that is required. Areas of concern which relate to all nuclear power plant fire models are identified. 17 refs., 6 figs.

Nicolette, V.F.; Nowlen, S.P.

1989-01-01T23:59:59.000Z

202

A methodology for evaluating ``new`` technologies in nuclear power plants  

SciTech Connect

As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing.

Korsah, K.; Clark, R.L.; Holcomb, D.E.

1994-06-01T23:59:59.000Z

203

Next Generation Nuclear Plant Materials Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

204

Liquid metal cooled nuclear reactor plant system  

DOE Patents (OSTI)

A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

1993-01-01T23:59:59.000Z

205

Radiation Protection Program Resource Optimization Project; Brunswick Nuclear Plant  

Science Conference Proceedings (OSTI)

Radiation protection (RP) managers face challenges in providing a necessary service that complies with stringent regulations, while simultaneously reducing operations and maintenance (O&M) costs. The results of this pilot project, hosted by Brunswick Nuclear Plant (BNP), will assist utilities in targeting resource commitments and cost effectiveness while optimizing overall performance. This report identifies specific program cost reduction and process performance enhancements for the host plant, and esta...

2002-11-18T23:59:59.000Z

206

Optimization of Auxiliaries Consumption in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Operators of nuclear power plants face significant challenges to produce power more cost-effectively. One approach to producing power more cost-effectively is to reduce power consumption by auxiliary systems in the plant, leading to more power available for the grid. This report provides guidance for assessing auxiliary system performance and recommends approaches to reduce their power consumption. The report also presents results from questionnaires on auxiliary system consumption and, in some cases, ac...

2005-02-08T23:59:59.000Z

207

Carbon-14 Dose Calculation Methods at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Carbon-14 (C-14) is a naturally occurring isotope of carbon produced by cosmic radiation interactions in the upper atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. C-14 is released through permitted effluent pathways of a nuclear power plant. This report provides the current industry best...

2012-04-26T23:59:59.000Z

208

Enhancing Cross-Correlation Analysis with Artificial Neural Networks for Nuclear Power Plant Feedwater Flow Measurement  

Science Conference Proceedings (OSTI)

One of the primary cost-saving objectives of the power plant industry, including the nuclear industry, has long been the efficient operation of plant systems. Since the maximum operating thermal power of any nuclear plant is bounded by the specific licensing ... Keywords: flow measurement, neural networks, nuclear power plant

Davide Roverso; Da Ruan

2004-05-01T23:59:59.000Z

209

Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants  

SciTech Connect

Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which are experienced, being implemented or evaluated by several IAEA Member States. Operating experience with nuclear desalination using a liquid-metal reactor BN-350 in Kazakhstan and several Pressurized Water Reactor units in Japan is discussed. Results of economic analyses of nuclear desalination are also presented in order to illustrate the competitiveness of this technology with other conventional desalination operations. (authors)

Faibish, R.S.; Konishi, T.; Gasparini, M. [International Atomic Energy Agency - IAEA, P.O. Box 100, Wagramer Strasse 5, A-1400 Vienna (Austria)

2002-07-01T23:59:59.000Z

210

Aging assessment of large electric motors in nuclear power plants  

Science Conference Proceedings (OSTI)

Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry`s large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs.

Villaran, M.; Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)

1996-03-01T23:59:59.000Z

211

Plant Support Engineering: Guidance for Replacing Feedwater Heaters at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities continue to pursue license renewal applications and power uprates, and these initiatives are being undertaken in an aging fleet of nuclear plants. Many plants are facing the necessity of replacing feedwater heaters to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant construction8212there are fewer qualified vendors and equipment manufacturers, materials might have changed, and licensees are typically not staffed for these m...

2007-07-26T23:59:59.000Z

212

Plant Support Engineering: Guidance for Replacing Inverters and Battery Chargers at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities are continuing to pursue license renewal applications and power uprates, and these initiatives are being undertaken on an aging fleet of nuclear plants. Many plants must replace inverters and battery chargers to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant constructionthere are fewer qualified vendors and equipment manufacturers, materials have changed in many cases, and licensees are typically not currently staffed for...

2008-10-29T23:59:59.000Z

213

Plant Support Engineering: Guidance for Planned Replacement of Large Power Transformers at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Utilities continue to pursue license renewal applications and power uprates, and these initiatives are being undertaken on an aging fleet of nuclear plants. Many plants are facing the necessity of replacing large power transformers to support these initiatives. However, industry expertise to support such activities has diminished since the days of plant construction8212there are fewer qualified vendors and equipment manufacturers, materials and standards might have changed, and licensees are typically no...

2007-11-02T23:59:59.000Z

214

Peach Bottom and Vermont Yankee Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A dramatic and extraordinary instance of state and local government control of nuclear power, the purchase by New York of the Shoreham plant is nonetheless indicative of the political demands that some states confront for additional involvement in the regulation of the radiological hazards associated with commercial nuclear power plants. Although the Supreme Court has appeared to expand, in the eight years since PG&E and Silkwood, the acceptable extent of state regulation, some states, in addition to New York, have acquired, with the acquiescence of the NRC, a degree of involvement that exceeds the role for state and local governments provided by the Court. For example, the Commonwealth of Pennsylvania concluded with the Philadelphia Electric Company (PECO) in June 1989 an agreement that commits PECO to various initiatives, not otherwise required under NRC regulations, for the safe operation of the Peach Bottom nuclear power plant in Pennsylvania. In July 1991 the State of Vermont and Vermont Yankee Nuclear Power Corporation (Vermont Yankee) concluded an agreement similar to that concluded between Pennsylvania and PECO. The agreement also commits Vermont Yankee to certain initiatives, not otherwise required under NRC regulations, related to its operation of the Vermont Yankee nuclear power plant in Vermont. The agreement was precipitated by a challenge to an application, submitted to the NRC by Vermont Yankee in April 1989, to amend the Vermont Yankee plant license to extend its expiration date from December 11, 2007 to March 21, 2012. The amendment would allow the Vermont Yankee plant to operate for forty full years.

NONE

1992-12-31T23:59:59.000Z

215

PM-1 NUCLEAR POWER PLANT PROGRAM PARAMETRIC STUDY REPORT  

SciTech Connect

The study deals with narrowing the range of parameters prior to preliminary design of the PM-1, a factory prepackaged, air-transportable, pressurized water nuclear power plant. The plant is to produce 1000 kw of net electrical power and 7 x 10/sup 6/ Btu/hr of space heat that is suitable for use with a central heating system. The data and conclusions resulting from the parametric study will provide the basis for the preliminary design of the PM-1 power plant. (W.D.M.)

Sieg, J.S.

1959-09-01T23:59:59.000Z

216

Radioactive Effluents from Nuclear Power Plants Annual Report 2008  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

217

Radioactive Effluents from Nuclear Power Plants Annual Report 2007  

SciTech Connect

This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

2010-12-10T23:59:59.000Z

218

Is natural background or radiation from nuclear power plants leukemogenic  

SciTech Connect

The objective in this review is to provide some facts about normal hemopoietic cell proliferation relevant to leukemogenesis, physical, chemical, and biological facts about radiation effects with the hope that each person will be able to decide for themselves whether background radiation or emissions from nuclear power plants and facilities significantly add to the spontaneous leukemia incidence. 23 refs., 1 tab.

Cronkite, E.P.

1989-01-01T23:59:59.000Z

219

Delays in nuclear power plant construction. Volume II. Final report  

SciTech Connect

The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity.

Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

1977-12-14T23:59:59.000Z

220

Radiation Data for Design and Qualification of Nuclear Plant Equipment  

Science Conference Proceedings (OSTI)

Graphic summaries in this report represent the most comprehensive collection to date of data on the degrading effects of radiation on organic materials used in nuclear plant equipment. The data, which can help designers in selecting radiation-resistant materials, can also help in qualifying equipment at minimum cost.

1985-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Nuclear Plant Reliability: Data Collection and Usage Guide  

Science Conference Proceedings (OSTI)

Most nuclear utility programs and regulatory compliance actions involve several organizations within a utility and often have overlapping elements. Nearly all of these programs need extensive data. This report discusses some issues associated with the identification, collection, and effective use of plant data in support of such utility programs.

1992-07-14T23:59:59.000Z

222

April 29, 2004: Fernald Closure Site  

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

April 29, 2004Demolition crews bring down the Pilot Plant at DOE's Fernald Closure Site in Ohio. The plant was the last to be torn down of ten former uranium production complexes that produced high...

223

Reprocessing of nuclear fuels at the Savannah River Plant  

Science Conference Proceedings (OSTI)

For more than 30 years, the Savannah River Plant (SRP) has been a major supplier of nuclear materials such as plutonium-239 and tritium-3 for nuclear and thermonuclear weapons, plutonium-238 for space exploration, and isotopes of americium, curium, and californium for use in the nuclear research community. SRP is a complete nuclear park, providing most of the processes in the nuclear fuel cycle. Key processes involve fabrication and cladding of the nuclear fuel, target, and control assemblies; rework of heavy water for use as reactor moderator; reactor loading, operation, and unloading; chemical recovery of the reactor transmutation products and spent fuels; and management of the gaseous, liquid, and solid nuclear and chemical wastes; plus a host of support operations. The site's history and the key processes from fabrication of reactor fuels and targets to finishing of virgin plutonium for use in the nuclear weapons complex are reviewed. Emphasis has been given to the chemistry of the recovery and purification of weapons grade plutonium from irradiated reactor targets.

Gray, L.W.

1986-10-04T23:59:59.000Z

224

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

~ ties Surrounding Nuclear Power Plants. LBlr5921, Lawrencein U. S. Commercial Nuclear Power Plants. WASH-1400. Octoberand Content of for Nuclear Power Plants. Regulatory Guide

Yen, W.W.S.

2010-01-01T23:59:59.000Z

225

Online Monitoring of Plant Assets in the Nuclear Industry  

SciTech Connect

Todays online monitoring technologies provide opportunities to perform predictive and proactive health management of assets within many different industries, in particular the defense and aerospace industries. The nuclear industry can leverage these technologies to enhance safety, productivity, and reliability of the aging fleet of existing nuclear power plants. The U.S. Department of Energys Light Water Reactor Sustainability Program is collaborating with the Electric Power Research Institutes (EPRIs) Long-Term Operations program to implement online monitoring in existing nuclear power plants. Proactive online monitoring in the nuclear industry is being explored using EPRIs Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software, a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. This paper focuses on development of asset fault signatures used to assess the health status of generator step-up transformers and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. Fault signatures are developed based on the results of detailed technical research and on the knowledge and experience of technical experts. The Diagnostic Advisor of the FW-PHM Suite software matches developed fault signatures with operational data to provide early identification of critical faults and troubleshooting advice that could be used to distinguish between faults with similar symptoms. This research is important as it will support the automation of predictive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

Nancy Lybeck; Vivek Agarwal; Binh Pham; Richard Rusaw; Randy Bickford

2013-10-01T23:59:59.000Z

226

Closure of the 242-F system  

Science Conference Proceedings (OSTI)

This paper describes the closure preparation and proposed closure process of the 242-F Evaporator System at the Savannah River Site. The closure of this system will be a first-of-a-kind for the DOE and is applicable across the Department of Energy (DOE complex and the nuclear industry. The 242-F Evaporator System is part of a nuclear waste storage and management process comprised of tanks and supporting facilities permitted by the South Carolina Pollution Control Act as wastewater treatment facilities. The system has been emptied of residuals to the maximum extent practical given funding levels and has been isolated from all process interfaces. The remaining activities are contingent upon satisfying emergent regulatory requirements. Closure of the 242-F Evaporator System is part of the DOE's stewardship of federally owned and operated facilities. Protecting workers and the general public during and after closure is part of that stewardship that requires careful and methodical planning and execution of closure processes. (authors)

Dixon, G. [East Carolina Univ., Dept. of Engineering, Greenville, NC (United States)

2007-07-01T23:59:59.000Z

227

Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.  

SciTech Connect

This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

2006-12-11T23:59:59.000Z

228

Survey of nuclear power plant construction costs, 1983  

SciTech Connect

This report presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in the construction pipeline, collected on Form EIA-254. The information on US nuclear power plants in the construction pipeline is reported voluntarily each quarter by the electric utilities. This report presents the data collected in the first quarter of 1983 on the 71 nuclear units in the construction pipeline. Historical data on 73 units, totalling 57,287 net megawatts (MWe) of design capacity, in commercial operation as of March 31, 1983, are also given. Three types of information are included: plant characteristics and ownership, construction costs, and construction schedule or chronology. Summary statistics are presented on direct component costs and construction leadtimes for a sample of operating units and units in the construction pipeline. The reactor-specific cost data included in Chapter 4 are the estimated final nuclear production plant costs and, for units in the construction pipeline, the disbursed and sunk costs as of March 31, 1983. 7 figures, 5 tables.

1983-12-01T23:59:59.000Z

229

DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants  

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

Outlines Five Steps for New Nuclear Plant Sponsors to Enter Into a Conditional Agreement for Risk Insurance

230

Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants  

SciTech Connect

OAK-B135 Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

O' Connell, J. Michael

2002-01-01T23:59:59.000Z

231

INFORMATION INTEGRATION IN CONTROL ROOMS AND TECHNICAL OFFICES IN NUCLEAR POWER PLANTS  

E-Print Network (OSTI)

Information integration in control rooms and technical offices in nuclear power plants Report prepared within the framework of the

unknown authors

2001-01-01T23:59:59.000Z

232

Indicator system for advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

233

Plant Support Engineering: Aging Management Program Guidance for Medium- Voltage Cable Systems for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants has been increasing for 510 years. The staff of the U.S. Nuclear Regulatory Commission (NRC) are concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. Utility managers are concerned that cables may fail, causing adverse safety consequences ...

2010-06-02T23:59:59.000Z

234

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

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

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

235

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants  

E-Print Network (OSTI)

Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 of Nuclear Reactor and Chemical Separation Plants ANL-AFCI-168 by G. Palmiotti, J. Cahalan, P. Pfeiffer, T;2 ANL-AFCI-168 Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separation Plants G

Anitescu, Mihai

236

Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices  

E-Print Network (OSTI)

Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices Marko threats to a nuclear power plant in the year 1991 and after the 9/11 events in 2001. The methodology which strength and injuries of human beings with nuclear power plant models used in probabilistic safety

Cizelj, Leon

237

Advanced Nuclear Technology: Supplier Quality Management for New Nuclear Plant Construction Projects  

Science Conference Proceedings (OSTI)

This report provides guidance for new nuclear power plant construction projects on supplier quality-related risks associated with the procurement of materials, equipment, and services intended for use in a safety-related plant application. This guidance takes an in-depth look into the procurement-related challenges that new construction projects face and at measures for overcoming these challenges. A methodology is provided for identifying, managing, evaluating, and mitigating quality-related risks ...

2013-06-26T23:59:59.000Z

238

Nuclear Maintenance Applications Center: Passive Component Maintenance Guide for Nuclear Power Plant Personnel  

Science Conference Proceedings (OSTI)

The information contained in this report represents a significant collection of technical and human performance information, including techniques and good practices, related to the design, maintenance, and operation of passive components common at most domestic nuclear power plants. Assemblage of this information provides a single point of reference for plant engineering and maintenance personnel, both in the present and in the future. Through the use of this guideline, in close conjunction with the indu...

2011-11-16T23:59:59.000Z

239

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

240

Plant Engineering: Electrical Cable Test Applicability Matrix for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

When assessing cable degradation or failure assessment, using the correct test and assessment methodology is critical to obtaining the correct answer. Many in-plant and laboratory tests exist. Some apply to the cable types used in nuclear plants. Some apply only to distribution cables. Most have pertinence to only one issue or even one cable design. This report provides a correlation between specific cable problems and the appropriate tests that may be used to resolve the issue. The report starts with su...

2011-12-23T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Design and construction of the Qinshan nuclear power plant  

Science Conference Proceedings (OSTI)

The construction work of China's first prototype nuclear power plant Qinshan NPP has already begun. This plant is located on the northern shore of Hangzhou Bay. It is designed to have a capacity of 300 MW electricity. The thermal power of the reactor is 966 MW. The primary circuit consists of 2 coolant loops and 16 auxiliary systems for normal operation. Safety is always the priority in design consideration. Preliminary safety analyses have been done and satisfactory results have been obtained. Excavation and clean out work has been finished.

Yu, O.

1985-01-01T23:59:59.000Z

242

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

243

Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.  

Science Conference Proceedings (OSTI)

This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.

OHara,J.; Higgins, J.; Brown, W.; Fink, R.

2008-02-14T23:59:59.000Z

244

Optimization of Fire Protection Impairments at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

In recent years, risk-informed and performance-based (RI/PB) fire protection is gaining further acceptance by the Nuclear Regulatory Commission (NRC) and the industry. In addition, fire risk assessment methods are gaining some level of maturity since the first industrywide experience with individual plant examination for external events (IPEEE). RI/PB methods can reduce the cost of operating fire protection programs and maintaining fire safety.

2006-08-07T23:59:59.000Z

245

Predictive Maintenance Self-Assessment Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

There is a need at nuclear power plants for optimization and continuous improvement in the predictive maintenance (PdM) process. This need is based upon increased reliance on PdM to contribute to low unplanned capability loss factors, prevent significant equipment failures, reduce resources for maintenance, manage assets in support of license renewal and aging control, incorporate new technologies and advanced information management, and manage the risk associated with maintenance activities. This docume...

2000-11-28T23:59:59.000Z

246

Introduction to Nuclear Plant Steam Turbine Control Systems  

Science Conference Proceedings (OSTI)

Since Nuclear Power Plants produce their power through the use of Steam Turbine Generators, any problems associated with the Turbine Control System has a direct effect on power generation. Although considerable effort has been expended in improving control system reliability, failures resulting in lost generation and high maintenance cost still plague the industry. On an individual basis, improvements have been made through maintenance techniques, modifications and upgrades. Unfortunately, this informati...

1995-03-02T23:59:59.000Z

247

Understanding seismic design criteria for Japanese nuclear power plants  

SciTech Connect

This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with US criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

Park, Y.J.; Hofmayer, C.H. [Brookhaven National Lab., Upton, NY (United States); Costello, J.F. [US Nuclear Regulatory Commission, Washington, DC (United States)

1994-12-31T23:59:59.000Z

248

Hydrogen Production from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

249

Conceivable new recycling of nuclear waste by nuclear power companies in their plants  

E-Print Network (OSTI)

We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

Ruggero Maria Santilli

1997-04-09T23:59:59.000Z

250

The Acceptance Strategy for Nuclear Power Plant In Indonesia  

SciTech Connect

Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R and D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

Suhaemi, Tjipta [Centre for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency of Indonesia (Indonesia); Syaukat, Achmad [Centre for Nuclear Technology Business, National Nuclear Energy Agency of Indonesia, Kawasan PUSPIPTEK, Serpong-Tangerang Selatan (Indonesia)

2010-06-22T23:59:59.000Z

251

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

population growth surrounding a nuclear power plant once thegrowth by requiring that certification of nuclear power plant

Yen, W.W.S.

2010-01-01T23:59:59.000Z

252

Validation of seismic probabilistic risk assessments of nuclear power plants  

SciTech Connect

A seismic probabilistic risk assessment (PRA) of a nuclear plant requires identification and information regarding the seismic hazard at the plant site, dominant accident sequences leading to core damage, and structure and equipment fragilities. Uncertainties are associated with each of these ingredients of a PRA. Sources of uncertainty due to seismic hazard and assumptions underlying the component fragility modeling may be significant contributors to uncertainty in estimates of core damage probability. Design and construction errors also may be important in some instances. When these uncertainties are propagated through the PRA, the frequency distribution of core damage probability may span three orders of magnitude or more. This large variability brings into question the credibility of PRA methods and the usefulness of insights to be gained from a PRA. The sensitivity of accident sequence probabilities and high-confidence, low probability of failure (HCLPF) plant fragilities to seismic hazard and fragility modeling assumptions was examined for three nuclear power plants. Mean accident sequence probabilities were found to be relatively insensitive (by a factor of two or less) to: uncertainty in the coefficient of variation (logarithmic standard deviation) describing inherent randomness in component fragility; truncation of lower tail of fragility; uncertainty in random (non-seismic) equipment failures (e.g., diesel generators); correlation between component capacities; and functional form of fragility family. On the other hand, the accident sequence probabilities, expressed in the form of a frequency distribution, are affected significantly by the seismic hazard modeling, including slopes of seismic hazard curves and likelihoods assigned to those curves.

Ellingwood, B. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

1994-01-01T23:59:59.000Z

253

AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT  

SciTech Connect

An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)

Churchill, J.R.; Renard, J.

1960-03-15T23:59:59.000Z

254

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

Mark Holbrook

2010-09-01T23:59:59.000Z

255

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

256

Aging management guideline for commercial nuclear power plants-pumps  

SciTech Connect

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D. [MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01T23:59:59.000Z

257

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

258

APPARATUS AND METHOD FOR WELDING END CLOSURE TO CONTAINER  

DOE Patents (OSTI)

A semi-automatic apparatus is described for welding a closure to the open end of a can containing a nuclear fuel slug. An arc is struck at the center of the closure and is shifted to a region near its periphery. Then the assembly of closure, can, and fuel slug is rotated so that the peripheral region of the closure is preheated. Next the arc is shifted to the periphery itself of the closure, and the assembly is rotated so that the closure is welded to the can.

Frantz, C.E.; Correy, T.B.

1959-08-01T23:59:59.000Z

259

Incentive regulation of nuclear power plants by state regulators  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission (NRC) monitors incentive programs established by state regulators in order to obtain current information and to consider the potential safety effects of the incentive programs as applied to nuclear units. The current report is an update of NUREG/CR-5509, Incentive Regulation of Nuclear Power Plants by State Public Utility Commissions, published in December 1989. The information in this report was obtained from interviews conducted with each state regulator and each utility with a minimum entitlement of 10%. The agreements, orders, and settlements from which each incentive program was implemented were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program. The programs currently in effect represent the adoption of an existing nuclear performance incentive program proposal and one new program. In addition, since 1989 a number of nuclear units have been included in one existing program; while one program was discontinued and another one concluded. 6 refs., 27 tabs.

Martin, R.L.; Baker, K.; Olson, J. (Battelle Human Affairs Research Center, Seattle, WA (USA))

1991-02-01T23:59:59.000Z

260

The Need for Near-Term Deployment of New Nuclear Power Plants Position Statement  

E-Print Network (OSTI)

The American Nuclear Society (ANS) supports and encourages the near-term deployment of new nuclear power plants. Nuclear energy, the second-largest power source, contributes 20 % of the electricity production in the United States. 1 Nuclear power can be competitive with gas and coal plants. Like solar, wind, and hydropower, nuclear energy has near-zero emissions of greenhouse gases and air pollutants. The more than one hundred nuclear power plants currently operating in the United States have an excellent safety record and are proven reliable sources of power.

unknown authors

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

(Safety and reliability of nuclear power plant technology)  

SciTech Connect

The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

Dickson, T.L.

1990-10-22T23:59:59.000Z

262

Guidelines for inservice testing at nuclear power plants  

Science Conference Proceedings (OSTI)

The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

Campbell, P.

1995-04-01T23:59:59.000Z

263

COMMERCIAL UTILITY PERSPECTIVES ON NUCLEAR POWER PLANT CONTROL ROOM MODERNIZATION  

SciTech Connect

Commercial nuclear power plants (NPPs) in the United States need to modernize their main control rooms (MCR). Many NPPs have done partial upgrades with some success and with some challenges. The Department of Energys (DOE) Light Water Reactor Sustainability (LWRS) Program, and in particular the Advanced Instrumentation and Controls (I&C) and Information Systems Technologies Research and Development (R&D) Pathway within LWRS, is designed to assist commercial nuclear power industry with their MCR modernization efforts. As part of this framework, a survey was issued to utility representatives of the LWRS Program Advanced Instrumentation, Information, and Control Systems/Technologies (II&C) Utility Working Group to obtain their views on a range of issues related to MCR modernization, including: drivers, barriers, and technology options, and the effects these aspects will have on concepts of operations, modernization strategies, and staffing. This paper summarizes the key survey results and discusses their implications.

Jeffrey C. Joe; Ronald L. Boring; Julius J. Persensky

2012-07-01T23:59:59.000Z

264

Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program  

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

fficials from the U.S. Department of Energys (DOE) Office of Nuclear Energy today (April 8, 2010) participated in a ceremony in Ukraine to mark the insertion of Westinghouse-produced nuclear fuel into a nuclear power plant in Ukraine.

265

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

Powell, J.G.

1993-11-16T23:59:59.000Z

266

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

Powell, James G. (Clifton Park, NY)

1993-01-01T23:59:59.000Z

267

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

268

Seismic Margin Assessment of the Edwin I. Hatch Nuclear Plant, Unit 1  

Science Conference Proceedings (OSTI)

A seismic margin assessment of the Georgia Power Company Edwin I. Hatch, unit 1 nuclear power plant showed the practicality of an EPRI methodology for assessing the ability of nuclear plants to withstand large earthquakes. The assessment, performed by the utility, established that the plant can withstand an earthquake at least twice the magnitude for which it was designed.

1991-08-01T23:59:59.000Z

269

Nuclear Maintenance Applications Center: Considerations for Developing a Critical Parts Program at a Nuclear Power Plant  

Science Conference Proceedings (OSTI)

In 2003, Plant Support Engineering (PSE) of the Electric Power Research Institute (EPRI) published the report Critical Component Identification Process8212Licensee Examples: Scoping and Identification of Critical Components in Support of INPO AP-913 (1007935). That report was the initial output from a project to assist utilities that were implementing Institute of Nuclear Power Operations (INPO) AP-913, Equipment Reliability Process Description. Two of the key aspects of INPO AP-913 are the accurate scop...

2007-11-30T23:59:59.000Z

270

Comparison of Options for a Pilot Plant Fusion Nuclear Mission  

Science Conference Proceedings (OSTI)

A fusion pilot plant study was initiated to clarify the development needs in moving from ITER to a first of a kind fusion power plant, following a path similar to the approach adopted for the commercialization of fission. The pilot plant mission encompassed component test and fusion nuclear science missions plus the requirement to produce net electricity with high availability in a device designed to be prototypical of the commercial device. Three magnetic configuration options were developed around this mission: the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS). With the completion of the study and separate documentation of each design option a question can now be posed; how do the different designs compare with each other as candidates for meeting the pilot plant mission? In a pro/con format this paper will examine the key arguments for and against the AT, ST and CS magnetic configurations. Key topics addressed include: plasma parameters, device configurations, size and weight comparisons, diagnostic issues, maintenance schemes, availability influences and possible test cell arrangement schemes.

Brown, T; Goldston, R J; El-Guebaly, L; Kessel, C; Neilson, G H; Malang, S; Menard, J E; Prager, S; Waganer, L; Titus, P

2012-08-27T23:59:59.000Z

271

Plant Support Engineering: Nuclear Power Plant Equipment Qualification Reference Manual, Revision 1  

Science Conference Proceedings (OSTI)

This reference manual compiles information on technology, requirements, and experience pertaining to the qualification of safety-related equipment for use in nuclear power plants under normal operating conditions and under adverse environments such as steam line breaks and earthquakes. The manual covers both environmental and seismic qualification of all safety-related electrical and mechanical equipment, but places emphasis on environmental qualification of Class 1E electrical equipment subject to harsh...

2010-09-16T23:59:59.000Z

272

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESSPlanning for Nuclear Power Plants Determination of Accidentnuclear power plants . . . . . . . . . . . . . .2.2.4.3.

Yen, W.W.S.

2010-01-01T23:59:59.000Z

273

Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B  

SciTech Connect

The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.

Kasza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U. [and others

1996-12-01T23:59:59.000Z

274

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

275

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

276

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

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

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

277

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in  

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

Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Nuclear power plants in the United States currently produce about 20 percent of the nation's electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit greenhouse gases. Continued and expanded reliance on nuclear energy is one key to meeting future demand for electricity in the U.S. and is called for in the National Energy Policy. Nevertheless, no new nuclear plants have been built in the U.S. in many years, and none are currently slated for construction. The U.S. Department of Energy (DOE) has been working with the nuclear

278

An examination of the pursuit of nuclear power plant construction projects in the United States  

E-Print Network (OSTI)

The recent serious reconsideration of nuclear power as a means for U.S. electric utilities to increase their generation capacity provokes many questions regarding the achievable success of future nuclear power plant ...

Guyer, Brittany (Brittany Leigh)

2011-01-01T23:59:59.000Z

279

Fire Events Database and Generic Ignition Frequency Model for U.S. Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report contains a revision of the EPRI Fire Events Database for U.S. Nuclear Power Plants last published in EPRI Report 1000894 in October 2000. This report also contains a revision of the generic fire ignition frequency models that were published in NSAC-178L, "Fire Events Database of U.S. Nuclear Power Plants" (January 1993) and EPRI TR-105929, "Fire Ignition Frequency Model at Shutdown for U.S. Nuclear Power Plants" (December 1995).

2001-11-09T23:59:59.000Z

280

Advanced design nuclear power plants: Competitive, economical electricity. An analysis of the cost of electricity from coal, gas and nuclear power plants  

SciTech Connect

This report presents an updated analysis of the projected cost of electricity from new baseload power plants beginning operation around the year 2000. Included in the study are: (1) advanced-design, standardized nuclear power plants; (2) low emissions coal-fired power plants; (3) gasified coal-fired power plants; and (4) natural gas-fired power plants. This analysis shows that electricity from advanced-design, standardized nuclear power plants will be economically competitive with all other baseload electric generating system alternatives. This does not mean that any one source of electric power is always preferable to another. Rather, what this analysis indicates is that, as utilities and others begin planning for future baseload power plants, advanced-design nuclear plants should be considered an economically viable option to be included in their detailed studies of alternatives. Even with aggressive and successful conservation, efficiency and demand-side management programs, some new baseload electric supply will be needed during the 1990s and into the future. The baseload generating plants required in the 1990s are currently being designed and constructed. For those required shortly after 2000, the planning and alternatives assessment process must start now. It takes up to ten years to plan, design, license and construct a new coal-fired or nuclear fueled baseload electric generating plant and about six years for a natural gas-fired plant. This study indicates that for 600-megawatt blocks of capacity, advanced-design nuclear plants could supply electricity at an average of 4.5 cents per kilowatt-hour versus 4.8 cents per kilowatt-hour for an advanced pulverized-coal plant, 5.0 cents per kilowatt-hour for a gasified-coal combined cycle plant, and 4.3 cents per kilowatt-hour for a gas-fired combined cycle combustion turbine plant.

1992-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Success of the first nuclear power plant built on China`s self-reliance  

Science Conference Proceedings (OSTI)

Having overcome a series of difficulties and hard points, the first Chinese indigenous nuclear power plant, Qinshan Nuclear Power Plant of PWR type with the capacity of 300MW(e) is now in steady operation. Through tremendous works done for this project great achievements and experience as well as lessons learned have been obtained for systematic acquisition of nuclear power technology. The sound fact has demonstrated that China has the ability to develop nuclear power mainly depending on self-reliance.

Yu, O.

1994-12-31T23:59:59.000Z

282

Compilation of Results and Feedback Regarding Turbine Upgrades at Nuclear and Fossil Power Plants  

Science Conference Proceedings (OSTI)

This report compiles results and feedback and draws a number of conclusions and lessons learned regarding steam turbine generator upgrades at nuclear and fossil power plants.

2008-11-24T23:59:59.000Z

283

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

284

Guideline for On-Line Monitoring of Nuclear Power Plant Instrument Channel Performance  

Science Conference Proceedings (OSTI)

This report provides a guideline for a utility to develop an on-line monitoring (OLM) program for evaluating instrument channel performance at nuclear power plants (NPPs).

2011-11-08T23:59:59.000Z

285

Survey on the Use of Configuration Risk and Safety Management Tools at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A joint project of Electricite de France (EDF) and EPRI, this project analyzed use of configuration safety and risk management tools at nuclear power plants.

1998-09-24T23:59:59.000Z

286

Bayesian Analysis for the Site-Specific Dose Modeling in Nuclear Power Plant Decommissioning.  

E-Print Network (OSTI)

??Decommissioning is the process of closing down a facility. In nuclear power plant decommissioning, it must be determined that that any remaining radioactivity at a (more)

Ling, Xianbing

2001-01-01T23:59:59.000Z

287

A review of the methods of economic analysis of nuclear power plants.  

E-Print Network (OSTI)

??Nuclear power plants across the United States are reaching the end of their current operating licenses, forcing decision makers to think about the way forward. (more)

Cavender, Brittainy Anne

2011-01-01T23:59:59.000Z

288

Long term control of 3D engineering data for nuclear power plants  

Science Conference Proceedings (OSTI)

The engineering of the next generation of nuclear power plants requires to take into account the whole plant lifecycle: engineering, building, operating, maintaining and decommissioning. Satisfying stronger and stronger safety regulations requires the ...

Thomas Paviot; Christophe Mouton; Samir Lamouri

2013-06-01T23:59:59.000Z

289

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01T23:59:59.000Z

290

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, ...

291

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

Uncertainty can be either an opportunity or a risk. Every construction project begins with the expectation of project performance. To meet the expectation, construction projects need to be managed through sound risk assessment and management beginning with the front-end of the project life cycle to check the feasibility of a project. The Construction Industry Institutes (CII) International Project Risk Assessment (IPRA) tool has been developed, successfully used for a variety of heavy industry sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks associated with NPP projects, the goal of this thesis is to develop tailored risk framework for NPP projects that leverages and modifies the existing IPRA process. The IPRA has 82 elements to assess the risks associated with international construction projects. The modified IPRA adds five major issues (elements) to consider the unique risk factors of typical NPP projects based upon a review of the literature and an evaluation of the performance of previous nuclear-related facilities. The modified IPRA considers the sequence of NPP design that ultimately impacts the risks associated with plant safety and operations. Historically, financial risks have been a major chronic problem with the construction of NPPs. This research suggests that unstable regulations and the lack of design controls and oversight are significant risk issues. This thesis includes a consistency test to initially validate whether the asserted risks exist in actual conditions. Also, an overall risk assessment is performed based on the proposed risk framework for NPP and the list of assessed risk is proposed through a possible scenario. After the assessment, possible mitigation strategies are also provided against the major risks as a part of this thesis. This study reports on the preliminary findings for developing a new risk framework for constructing nuclear power plants. Future research is needed for advanced verification of the proposed elements. Follow-on efforts should include verification and validation of the proposed framework by industry experts and methods to quantify and evaluate the performance and risks associated with the multitude of previous NPP projects.

Yeon, Jaeheum 1981-

2012-12-01T23:59:59.000Z

292

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

None

2005-01-01T23:59:59.000Z

293

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

294

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

295

Idaho Site Nuclear Facilities  

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

Site Nuclear Facilities Idaho Idaho National Laboratorys (INL) Idaho Closure Project (ICP) This page was last updated on May 16...

296

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

SciTech Connect

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

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

297

Prognostics and Life Beyond 60 for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Safe, secure, reliable and sustainable energy supply is vital for advanced and industrialized life styles. To meet growing energy demand there is interest in longer term operation (LTO) for the existing nuclear power plant fleet and enhancing capabilities in new build. There is increasing use of condition based maintenance (CBM) for active components and periodic in service inspection (ISI) for passive systems: there is growing interest in deploying on-line monitoring. Opportunities exist to move beyond monitoring and diagnosis based on pattern recognition and anomaly detection to and prognostics with the ability to provide an estimate of remaining useful life (RUL). The adoption of digital I&C systems provides a framework within which added functionality including on-line monitoring can be deployed, and used to maintain and even potentially enhance safety, while at the same time improving planning and reducing both operations and maintenance costs.

Leonard J. Bond; Pradeep Ramuhalli; Magdy S. Tawfik; Nancy J. Lybeck

2011-06-01T23:59:59.000Z

298

Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant  

SciTech Connect

The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

2006-07-01T23:59:59.000Z

299

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

300

License Stewardship Approach to Commercial Nuclear Power Plant Decommissioning  

SciTech Connect

The paper explores both the conceptual approach to decommissioning commercial nuclear facilities using a license stewardship approach as well as the first commercial application of this approach. The license stewardship approach involves a decommissioning company taking control of a site and the 10 CFR 50 License in order to complete the work utilizing the established trust fund. In conclusion: The license stewardship approach is a novel way to approach the decommissioning of a retired nuclear power plant that offers several key advantages to all parties. For the owner and regulators, it provides assurance that the station will be decommissioned in a safe, timely manner. Ratepayers are assured that the work will be completed for the price they already have paid, with the decommissioning contractor assuming the financial risk of decommissioning. The contractor gains control of the assets and liabilities, the license, and the decommissioning fund. This enables the decommissioning contractor to control their work and eliminates redundant layers of management, while bringing more focus on achieving the desired end state - a restored site. (authors)

Daly, P.T.; Hlopak, W.J. [Commercial Services Group, EnergySolutions 1009 Commerce Park, Oak Ridge, TN (United States)

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Capturing Historical Knowledge for Decommissioning of Nuclear Power Plants: Summary of Historical Site Assessments at Eight Decommis sioning Plants  

Science Conference Proceedings (OSTI)

This report describes approaches utilized and experience gained in the development of early characterization activities by a number of nuclear power plants undergoing decommissioning. In particular, the report provides experience and lessons of performing the Historical Site Assessment, or HSA.

2004-04-01T23:59:59.000Z

302

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.

303

Advisory system for the diagnosis of lost electric output in nuclear power plants  

Science Conference Proceedings (OSTI)

The enhancement of efficiency is world-wide trend to survive under intense competition. In recent years, the efficiency in the power industry is also one of the important topics. In case of nuclear power plants(NPPs), the period and quality of maintenance ... Keywords: Advisory system, Bayesian network, Diagnosis, Nuclear power plant, Regression, Turbine cycle

Gyunyoung Heo; Soon Heung Chang; Seong Soo Choi; Gwang Hee Choi; Moon Hak Jee

2005-11-01T23:59:59.000Z

304

The Decommissioning of the Trino Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of BNFL decommissioning experience and knowledge to develop a strategy, methodology and cost for the decommissioning of NPPs. Over the past year, a prompt decommissioning strategy for Trino has been developed. The strategy has been based on the principles of minimizing waste products that require long term storage, maximizing 'free release' materials and utilizing existing and regulatory approved technologies.

Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

2002-02-27T23:59:59.000Z

305

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 58, NO. 1, FEBRUARY 2011 277 Anomaly Detection in Nuclear Power Plants via  

E-Print Network (OSTI)

applications (e.g., nuclear power reactor plants, petroleum industry and micro-gravity flow systems and Seungjin Kim Department of Mechanical and Nuclear Engineering, The Pennsylvania State University sensing. The underlying algorithm is built upon the recently reported theory of a statistical pattern

Ray, Asok

306

Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown  

SciTech Connect

The dismantlement of the reactor core materials and surrounding structural components is a major technical concern for those planning closure and decontamination and decommissioning of the Chernobyl Nuclear Power Plant (NPP). Specific issues include when and how dismantlement should be accomplished and what the radwaste classification of the dismantled system would be at the time it is disassembled. Whereas radiation levels and residual radiological characteristics of the majority of the plant systems are directly measured using standard radiation survey and radiochemical analysis techniques, actual measurements of reactor zone materials are not practical due to high radiation levels and inaccessibility. For these reasons, neutron transport analysis was used to estimate induced radioactivity and radiation levels in the Chernobyl NPP Unit 1 reactor core materials and structures.Analysis results suggest that the optimum period of safe storage is 90 to 100 yr for the Unit 1 reactor. For all of the reactor components except the fuel channel pipes (or pressure tubes), this will provide sufficient decay time to allow unlimited worker access during dismantlement, minimize the need for expensive remote dismantlement, and allow for the dismantled reactor components to be classified as low- or medium-level radioactive waste. The fuel channel pipes will remain classified as high-activity waste requiring remote dismantlement for hundreds of years due to the high concentration of induced {sup 63}Ni in the Zircaloy pipes.

Bylkin, Boris K. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Davydova, Galina B. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Zverkov, Yuri A. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Krayushkin, Alexander V. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Neretin, Yuri A. [Chernobyl Nuclear Power Plant (Ukraine); Nosovsky, Anatoly V. [Slavutych Division of the International Chernobyl Center (Ukraine); Seyda, Valery A. [Chernobyl Nuclear Power Plant (Ukraine); Short, Steven M. [Pacific Northwest National Laboratory (United States)

2001-10-15T23:59:59.000Z

307

Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants  

DOE Green Energy (OSTI)

Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 Produce Data and Analyses Task 2 Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 Commercial-Scale Hydrogen Production Task 4 Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study include a process model and a N2H2 economic assessment model (both developed by the Idaho National Laboratory). Both models are described in this report. The N2H2 model closely tracked and provided similar results as the H2A model and was instrumental in assessing the effects of plant availability on price when operated in the shoulder mode for electrical pricing. Differences between the H2A and N2H2 model are included in this report.

Stephen Schey

2009-07-01T23:59:59.000Z

308

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

P. E. MacDonald

2005-01-01T23:59:59.000Z

309

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

310

CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 528: POLYCHLORINATED BIPHENYLS CONTAMINATION NEVADA TEST SITE, NEVADA  

SciTech Connect

This Closure Report (CR) describes the closure activities performed at CAU 528, Polychlorinated Biphenyls Contamination, as presented in the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) (US. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSAINSO], 2005). The approved closure alternative was closure in place with administrative controls. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical data to confirm that the remediation goals were met.

BECHTEL NEVADA

2006-09-01T23:59:59.000Z

311

A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:  

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

A Roadmap to Deploy New Nuclear Power Plants in the United States A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that can be in operation in the U.S. by 2010. This document identifies the technological, regulatory, and institutional gaps and issues that need to be addressed for new nuclear plants to be deployed in the U.S. in this timeframe. It also identifies specific designs that could be deployed by 2010, along with the actions and resource requirements that are needed to ensure their

312

A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:  

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

A Roadmap to Deploy New Nuclear Power Plants in the United States A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that can be in operation in the U.S. by 2010. This document identifies the technological, regulatory, and institutional gaps and issues that need to be addressed for new nuclear plants to be deployed in the U.S. in this timeframe. It also identifies specific designs that could be deployed by 2010, along with the actions and resource requirements that are needed to ensure their

313

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

314

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

315

Activities in support of continuing the service of nuclear power plant concrete structures  

SciTech Connect

In general, nuclear power plant concrete structure s performance has been very good; however, aging of concrete structures occurs with the passage of time that can potentially result in degradation if is effects are not controlled. Safety-related nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The interaction of the license renewal process and concrete structures is noted. A summary of operating experience related to aging of nuclear power plant concrete structures is provided. Several candidate areas are identified where additional research would be beneficial for aging management of nuclear power plant concrete structures. Finally, an update on recent activities at Oak Ridge National Laboratory related to aging management of nuclear power plant concrete structures is provided.

Naus, Dan J [ORNL

2012-01-01T23:59:59.000Z

316

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago  

E-Print Network (OSTI)

than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor nuclear reactors, but critics argue it could be at least 50 years before a commercially viable reactorThirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago Representatives of more

317

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

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

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

318

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |  

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

New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United States Seismic Source Characterization for Nuclear Facilities model and report is the culmination of a four-year effort among the participating organizations and replaces previous seismic source models used by industry and government since the late 1980s. The NRC is requesting U.S. nuclear power plants to reevaluate seismic

319

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Summary of Nuclear Power Plant Operating Experience forResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, A.V.

2010-01-01T23:59:59.000Z

320

Process Data Network Architecture Plan for the Browns Ferry Nuclear Plants  

Science Conference Proceedings (OSTI)

Computer networks are essential in efficiently managing the large volumes of data used in power plant operation. Nuclear plants, however, have been cautious in applying computer technology because of their unique safety, security, and regulatory requirements. This report describes a strategic plan developed to manage the evolution of the network that processes real-time operating data for Tennessee Valley Authority's Browns Ferry nuclear plants.

1994-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

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

322

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

323

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

324

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Response Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

325

Extended nuclear plant outages raise Southern California wholesale ...  

U.S. Energy Information Administration (EIA)

Tools; Glossary All Reports ... weather; gasoline; capacity; exports; nuclear; forecast; View All Tags ...

326

Safeguards Issues at Nuclear Reactors and Enrichment Plants  

SciTech Connect

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

Boyer, Brian D [Los Alamos National Laboratory

2012-08-15T23:59:59.000Z

327

Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report  

Science Conference Proceedings (OSTI)

The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

Ritterbusch, S.E.

2000-08-01T23:59:59.000Z

328

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01T23:59:59.000Z

329

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2007-01-01T23:59:59.000Z

330

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the highly ranked phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01T23:59:59.000Z

331

Thermal-Fluid Characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Technical Paper / Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics

In Cheol Bang; Ji Hyun Kim

332

DOE Seeks Additional Input on Next Generation Nuclear Plant | Department of  

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

Seeks Additional Input on Next Generation Nuclear Plant Seeks Additional Input on Next Generation Nuclear Plant DOE Seeks Additional Input on Next Generation Nuclear Plant April 17, 2008 - 10:49am Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) today announced it is seeking public and industry input on how to best achieve the goals and meet the requirements for the Next Generation Nuclear Plant (NGNP) demonstration project work at DOE's Idaho National Laboratory. DOE today issued a Request for Information and Expressions of Interest from prospective participants and interested parties on utilizing cutting-edge high temperature gas reactor technology in the effort to reduce greenhouse gas emissions by enabling nuclear energy to replace fossil fuels used by industry for process heat. "This is an opportunity to advance the development of safe, reliable, and

333

Letter to NEAC to Review the Next Generation Nuclear Plant Activities |  

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

to NEAC to Review the Next Generation Nuclear Plant to NEAC to Review the Next Generation Nuclear Plant Activities Letter to NEAC to Review the Next Generation Nuclear Plant Activities The Next Generation Nuclear Plant (NGNP) project was established under the Energy Policy Act in August 2005 (EPACT-2005). EPACT-2005 defined an overall plan and timetable for NGNP research, design, licensing, construction and operation by the end of FY 2021. At the time that EPACT-2005 was passed, it was envisioned that key aspects of the project included: NGNP is based on R&D activities supported by the Gen-IV Nuclear Energy initiative;  NGNP is to be used to generate electricity, to produce hydrogen or (to do) both;  The Idaho National Laboratory (INL) will be the lead national lab for the project;  NGNP will be sited at the INL in

334

Department of Energy to Co-Sponsor Workshop on Nuclear Power Plant Life Extension R&D  

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

The U.S. Department of Energy (DOE), U.S. Nuclear Regulatory Commission (NRC), and the Nuclear Energy Institute (NEI) will co-sponsor a Second Workshop on U.S. Nuclear Power Plant Life Extension Research and Development.

335

Information Foraging in Nuclear Power Plant Control Rooms  

SciTech Connect

nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

R.L. Boring

2011-09-01T23:59:59.000Z

336

Small break LOCA analysis for Maanshan nuclear power plant  

SciTech Connect

Since 1990, Taiwan Power Company has conducted a LWR LOCA technology transfer program on RELAP5YA computer code from Yankee Atomic Electric Company (YAEC). One objective of this program is to acquire the RELAP5YA computer code from YAEC for Taipower in-house licensing analysis. The RELAP5YA is a computer program developed at YAEC for analysing the dynamic behaviour of thermal-hydraulic systems, and it can cover most of the postulated accidents and transients in light water reactor systems. In this paper, Taipower`s engineers have performed a small break loss of coolant accidents analysis for Maanshan nuclear power plant. Thais action is used to perform the licensing actions for increasing the operation margin on the steam generator tube plugging. The result is shown that the steam generator tube can be plugged slightly without a reduction in safety margins. This analysis covers a spectrum of break size for a small break LOCA. For a complete spectrum of the transient and accident analysis, the large break LOCA and the non-LOCA analysis were performed by the fuel vendor for the reload safety evaluation.

Jer-Cherng Kang; Shou-Chuan Chiang; Lang-Chen Wang [Taiwan Power Company, Taipei (China)

1994-12-31T23:59:59.000Z

337

Aging assessment of surge protective devices in nuclear power plants  

SciTech Connect

An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.

Davis, J.F.; Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)] [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States)] [Florida Univ., Gainesville, FL (United States)

1996-01-01T23:59:59.000Z

338

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability  

SciTech Connect

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01T23:59:59.000Z

339

Proceedings: EPRI/NEI Technical Information Workshop - Nuclear Plant Groundwater Monitoring  

Science Conference Proceedings (OSTI)

The EPRI Groundwater Protection Workshop focused on the subject of groundwater monitoring related to nuclear plant sites. This subject is very important to both decommissioning and operating plants. The Workshop provided information to assist operating plants in the development of technically sound plant site groundwater monitoring programs. Presentations provided the latest information on groundwater assessments, such as related tools, strategies, technologies and experience. The program included inform...

2007-07-19T23:59:59.000Z

340

Future AI and Robotics Technology for Nuclear Plants Decommissioning  

E-Print Network (OSTI)

Robotics Program The Robotics Program within the Nuclear Engineering Division is developing new technologies. Currently, we are exploring opportunities in applications for nuclear reactor operation, maintenance of remote energy installations, decontamination and decommissioning, and minimally invasive surgery

Hu, Huosheng

Note: This page contains sample records for the topic "nuclear plant closure" 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

Washington Closure Hanford, LLC  

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

CERTIFIED MAIL RETURN RECEIPT REQUESTED Mr. Neil Brosee President Washington Closure Hanford, LLC 2620 Fermi Avenue Richland, Washington 99354 WEA-201 0-02 Dear Mr. Brosee: This...

342

Assessment of next generation nuclear plant intermediate heat exchanger design.  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on shell and straight tube and printed circuit heat exchangers.

Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

2008-10-17T23:59:59.000Z

343

A Study of Outage Management Practices at Selected U.S. Nuclear Plants  

SciTech Connect

This paper presents insights gained from a study of the outage management practices at a number of U.S. nuclear plants. The objective of the study was to conduct an in-depth review of the current practices of outage management at these selected plants and identify important factors that have contributed to the recent success of their outage performance. Two BWR-4, three BWR-6, and two 3-loop Westinghouse PWR plants were selected for this survey. The results of this study can be used to formulate outage improvement efforts for nuclear plants in other countries. (author)

Lin, James C. [ABSG Consulting Inc., Irvine, CA (United States)

2002-07-01T23:59:59.000Z

344

Mathematical model of steam generator feed system at power unit of nuclear plant  

Science Conference Proceedings (OSTI)

A mathematical model of a steam generator feed system at a power unit of a nuclear plant with variable values of transfer function coefficients is presented. The model is realized in the MATLAB/Simulink/Stateflow event-driven simulation.

E. M. Raskin; L. A. Denisova; V. P. Sinitsyn; Yu. V. Nesterov

2011-05-01T23:59:59.000Z

345

A holistic investigation of complexity sources in nuclear power plant control rooms  

E-Print Network (OSTI)

The nuclear power community in the United States is moving to modernize aging power plant control rooms as well as develop control rooms for new reactors. New generation control rooms, along with modernized control rooms, ...

Sasangohar, Farzan

2011-01-01T23:59:59.000Z

346

Guidelines for the Technical Evaluation of Replacement Items in Nuclear Power Plants (NCIG-11)  

Science Conference Proceedings (OSTI)

Using a systematic technical evaluation process, utilities can ensure that replacement parts for nuclear power plants are equivalent to the originals. Guidelines developed by EPRI and NCIG provide practical information and a systematic approach to procurement.

1990-01-08T23:59:59.000Z

347

Probabilistic methods in seismic risk assessment for nuclear power plants: proceedings  

SciTech Connect

The state-of-the-art in seismic risk analysis applied to the design and siting of nuclear power plants was addressed in this meeting. Presentations were entered individually into the date base. (ACR)

Not Available

1983-01-01T23:59:59.000Z

348

Losses of Offsite Power at U.S. Nuclear Power Plants - 2011  

Science Conference Proceedings (OSTI)

This report describes the loss of offsite power experience at U.S. nuclear power plants during the year 2011 and provides insights into the causes of offsite power losses during the period 20022011.

2012-06-11T23:59:59.000Z

349

DC power transmission from the Leningradskaya Nuclear Power Plant to Vyborg  

SciTech Connect

DC power transmission from the Leningradskaya Nuclear Power Plant (LAES) to city of Vyborg is proposed. This will provide a comprehensive solution to several important problems in the development and control of the unified power system (EES) of Russia.

Koshcheev, L. A. [JSC 'NIIPT' (Russian Federation); Shul'ginov, N. G. [JSC 'SO EES' (Russian Federation)

2011-05-15T23:59:59.000Z

350

How much spent (used) fuel is stored at U.S. nuclear power plants ...  

U.S. Energy Information Administration (EIA)

How much spent (used) fuel is stored at U.S. nuclear power plants? In 2002, the most recent year for which EIA has data, there were 161,662 fuel assemblies, or 46,268 ...

351

A Software Configuration Management System for the Maintenance of Nuclear Power Plant Simulators  

Science Conference Proceedings (OSTI)

This paper reports on the KSG experiencies to introduce a configuration management system for the maintenance of nuclear power plant simulator software. After a discussion on the KSG specific requirements on a computer based software configuration management ...

Burkhard Holl

1997-03-01T23:59:59.000Z

352

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications  

Science Conference Proceedings (OSTI)

This report documents the verification and validation (VV) of five selected fire models commonly used in support of risk-informed and performance-based (RI/PB) fire protection at nuclear power plants (NPPs).

2007-05-30T23:59:59.000Z

353

Fire Events Database for U.S. Nuclear Power Plants: Update Through 1999  

Science Conference Proceedings (OSTI)

This report documents an update to the EPRI Fire Events Database for U.S. Nuclear Power Plants. This database was last published in January 1993 as NSAC-178L.

2000-10-19T23:59:59.000Z

354

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward  

SciTech Connect

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

John Collins

2009-01-01T23:59:59.000Z

355

Integration of Biorefineries and Nuclear Cogeneration Power Plants - A Preliminary Analysis  

SciTech Connect

Biomass-based ethanol and nuclear power are two viable elements in the path to U.S. energy independence. Numerous studies suggest nuclear power could provide a practical carbon-free heat source alternative for the production of biomass-based ethanol. In order for this coupling to occur, it is necessary to examine the interfacial requirements of both nuclear power plants and bioethanol refineries. This report describes the proposed characteristics of a small cogeneration nuclear power plant, a biochemical process-based cellulosic bioethanol refinery, and a thermochemical process-based cellulosic biorefinery. Systemic and interfacial issues relating to the co-location of either type of bioethanol facility with a nuclear power plant are presented and discussed. Results indicate future co-location efforts will require a new optimized energy strategy focused on overcoming the interfacial challenges identified in the report.

Greene, Sherrell R [ORNL; Flanagan, George F [ORNL; Borole, Abhijeet P [ORNL

2009-03-01T23:59:59.000Z

356

Identification of hazards in non-nuclear power plants. Volume II. Phase II  

DOE Green Energy (OSTI)

This study extends the Phase I study to also include a hazards evaluation for two new emerging coal power plant technologies: coal fired atmospheric fluidized bed and pressurized fluidized bed power generating systems. The study also considers the sensitivity of the hazards ranking for all the non-nuclear power plants to the effects of population density, mode of plant operation, technical changes, location and environmental (temperature) effects. Information is provided under the following section headings: background; environmental and public health concerns associated with fluidized-bed combustion power plants; description of a conceptual atmospheric fluidized-bed power plant; pressurized fluidized-bed combustion combined cycle (PFBCC) power plant; hazard ranking and risk assessment for non-nuclear power plants; and, hazards sensitivity analysis.

Fell, R.W.

1979-08-01T23:59:59.000Z

357

Plant Engineering, Aging Management Program Guidance for Medium-Voltage Cable Systems for Nuclear Power Plants, Revision 1  

Science Conference Proceedings (OSTI)

This report was prepared in response to regulatory and management concern regarding the reliability of medium-voltage cable systems at nuclear plants. The staff of the U.S. Nuclear Regulatory Commission (NRC) have been concerned that wetted (up to and including submergence) medium-voltage cable circuits may be degrading to the point at which multiple cable circuits may fail when called on to perform functions affecting safety. A utility managers concern is that cables may fail, causing ...

2013-06-03T23:59:59.000Z

358

ENGINEERED NEAR SURFACE DISPOSAL FACILITY OF THE INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT AT CHERNOBYL NUCLEAR POWER PLANT  

SciTech Connect

As a part of the turnkey project ''Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant (ChNPP)'' an Engineered Near Surface Disposal Facility (ENSDF, LOT 3) will be built on the VEKTOR site within the 30 km Exclusion Zone of the ChNPP. This will be performed by RWE NUKEM GmbH, Germany, and it governs the design, licensing support, fabrication, assembly, testing, inspection, delivery, erection, installation and commissioning of the ENSDF. The ENSDF will receive low to intermediate level, short lived, processed/conditioned wastes from the ICSRM Solid Waste Processing Facility (SWPF, LOT 2), the ChNPP Liquid Radwaste Treatment Plant (LRTP) and the ChNPP Interim Storage Facility for RBMK Fuel Assemblies (ISF). The ENSDF has a capacity of 55,000 m{sup 3}. The primary functions of the ENSDF are: to receive, monitor and record waste packages, to load the waste packages into concrete disposal units, to enable capping and closure of the disposal unit s, to allow monitoring following closure. The ENSDF comprises the turnkey installation of a near surface repository in the form of an engineered facility for the final disposal of LILW-SL conditioned in the ICSRM SWPF and other sources of Chernobyl waste. The project has to deal with the challenges of the Chernobyl environment, the fulfillment of both Western and Ukrainian standards, and the installation and coordination of an international project team. It will be shown that proven technologies and processes can be assembled into a unique Management Concept dealing with all the necessary demands and requirements of a turnkey project. The paper emphasizes the proposed concepts for the ENSDF and their integration into existing infrastructure and installations of the VEKTOR site. Further, the paper will consider the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper provides information on the output of the Detail Design and will reflect the progress of the design work.

Ziehm, Ronny; Pichurin, Sergey Grigorevich

2003-02-27T23:59:59.000Z

359

Assessment of Seismic Hazard at 34 U.S. Nuclear Plant Sites  

Science Conference Proceedings (OSTI)

Interest in recent years in early site permits (ESPs) for new nuclear plants has prompted a reevaluation of seismic design criteria and a reexamination of the basis for current criteria. Currently, Regulatory Guide 1.208 bases seismic design requirements on a performance-based approach using probabilistic seismic hazard analysis (PSHA). The performance-based approach was based on PSHA results at 29 nuclear plant sites, using results that were published in 1989 and 1994. These results were supported by pr...

2008-08-27T23:59:59.000Z

360

Study of the potential uses of the Barnwell Nuclear Fuel Plant (BNFP). Final report  

Science Conference Proceedings (OSTI)

The purpose of this study is to provide an evaluation of possible international and domestic uses for the Barnwell Nuclear Fuel Plant, located in South Carolina, at the conclusion of the International Nuclear Fuel Cycle Evaluation. Four generic categories of use options for the Barnwell plant have been considered: storage of spent LWR fuel; reprocessing of LWR spent fuel; safeguards development and training; and non-use. Chapters are devoted to institutional options and integrated institutional-use options.

Not Available

1980-03-25T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Characterization and Dose Modeling of Soil, Sediment and Bedrock During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

A decommissioning nuclear power plant must confirm that the radionuclides present in the soils, sediments, and bedrock left on site at the time of license termination will meet the appropriate dose limits for site release. This process involves the characterization, dose modeling, and if required, remediation, of these media. At some decommissioning nuclear power plants, the management of contaminated soil, sediments, and bedrocks was a major project that led to generation of remediation projects and rad...

2009-11-20T23:59:59.000Z

362

Jose Cabrera Nuclear Power Plant Full System Chemical Decontamination Experience Report  

Science Conference Proceedings (OSTI)

Chemical decontamination is one of the key challenging tasks of decommissioning a nuclear power plant. This report describes a full system chemical decontamination at SpainJosCabrera Nuclear Power Plant that sought to facilitate future dismantling by removing contamination and lowering radiation fields. Because of several unique features of the JosCabrera decontamination project, it has provided new good practices and useful lessons learned.

2009-11-17T23:59:59.000Z

363

Aging Management Guidelines for Commercial Nuclear Power Plants -- Electrical and Mechanical Penetrations  

Science Conference Proceedings (OSTI)

As part of the application process for license renewal, nuclear utilities must perform an evaluation to confirm that they have appropriately considered aging effects on plant components within the scope of the License Renewal Rule. This report provides guidelines for managing relevant degradation mechanisms applicable to electrical and mechanical penetrations in nuclear power plants. Use of these guidelines will provide utilities with a basis for verifying that effective methods for managing age-related ...

2002-04-25T23:59:59.000Z

364

Technical Guideline for Cyber Security Requirements and Life Cycle Implementation Guidelines for Nuclear Plant Digital Systems  

Science Conference Proceedings (OSTI)

Nuclear power plants face increasing regulatory requirements from the U.S. Nuclear Regulatory Commission (NRC) and the Federal Energy Regulatory Commission (FERC) for cyber security of digital devices, components, and systems. The focus of these cyber security requirements is to protect plant digital computer systems, communications systems, and networks from cyber attacks that would affect reactor safety or generation reliability. This EPRI guideline document provides technical guidance for addressing c...

2010-10-29T23:59:59.000Z

365

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

366

Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report  

Science Conference Proceedings (OSTI)

OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

NONE

2000-08-01T23:59:59.000Z

367

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

368

Incentive regulation of nuclear power plants by state public utility commissions  

Science Conference Proceedings (OSTI)

This report on incentive regulation of nuclear power plants by state public utility commissions (PUCs). Economic performance incentives established by state PUCs are applicable to the construction or operation of about 45 nuclear power reactors owned by 30 utilities in 17 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Petersen, J.C.

1987-12-01T23:59:59.000Z

369

Incentive regulation of nuclear power plants by state Public Utility Commissions  

Science Conference Proceedings (OSTI)

Economic performance incentives established by state Public Utility Commissions (PUCs) currently are applicable to the construction or operation of approximately 73 nuclear power reactors owned by 27 utilities with investment greater than 10% in 18 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its headquarters and regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report on incentive regulation of nuclear power plants by state PUCs presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant.

Martin, R.L.; Olson, J. (Battelle Human Affairs Research Center, Seattle, WA (USA)); Hendrickson, P. (Pacific Northwest Lab., Richland, WA (USA))

1989-12-01T23:59:59.000Z

370

Sun-Sentinel How Florida's nuclear plants compare to Japan's  

E-Print Network (OSTI)

Point plant near Miami and two at its plant in St. Lucie County. Progress has one near Crystal River operation began," said FPL Spokesman Mike Waldron. #12;Progress Energy's Crystal River reactor and one was an effort to wrap up the issue at the Crystal River plant. "Was the company merely unlucky

Belogay, Eugene A.

371

Trial Plant Review of an American Nuclear Society External Event Probabilistic Risk Assessment Standard  

Science Conference Proceedings (OSTI)

This study examined a representative set of Seismic Probabilistic Risk Assessments (SPRAs) and Seismic Margin Assessments (SMAs) performed for U.S. nuclear plants and evaluated them against the American Nuclear Society's draft External-Event PRA Methodology Standard for conducting Probabilistic Risk Assessment of external events.

2003-09-22T23:59:59.000Z

372

Qualification of safety-critical systems in TVO nuclear power plants  

Science Conference Proceedings (OSTI)

Teollisuuden Voima Oy (TVO) operates two nuclear power plant units in Finland and has started to build a third one. The current nuclear power units have to continuously maintain and update existing instrumentation and control systems (I&C). Each new ... Keywords: FMECA, SPICE, instrumentation and control, qualification, safety-critical systems

Juha Halminen; Risto Nevalainen

2007-11-01T23:59:59.000Z

373

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

2004-06-01T23:59:59.000Z

374

Extended outages at several nuclear plants led to high outage ...  

U.S. Energy Information Administration (EIA)

Southern California Edison's San Onofre Nuclear ... and Progress's handling of the Crystal River repairs became an issue in the company's recent merger with ...

375

Nuclear norm minimization for the planted clique and biclique ...  

E-Print Network (OSTI)

Jan 21, 2009 ... Both problems are NP-hard. We write both problems as matrix-rank minimization and then relax them using the nuclear norm. This technique...

376

Sensitivity analysis for the outages of nuclear power plants  

E-Print Network (OSTI)

Feb 17, 2012 ... voirs, fossil energy (coal, gas), atom (nuclear fission process) and to a small .... The dynamic of the stocks of fuel is clear from the differential...

377

Nuclear power plants undergo seasonal scheduled outages - Today in ...  

U.S. Energy Information Administration (EIA)

Uranium fuel, nuclear reactors, generation, spent fuel. Total Energy. ... Privacy/Security Copyright & Reuse Accessibility. Related Sites U.S. Department of Energy

378

The Management of Aging in Nuclear Power Plant Concrete Structures  

Science Conference Proceedings (OSTI)

An example of application of structural reliability theory to investigate the impact of ... Cladding and Duct Materials for Advanced Nuclear Recycle Reactors

379

Program on Technology Innovation: Information Integration for Equipment Reliability at Nuclear Plants  

Science Conference Proceedings (OSTI)

This report investigates the status of information integration for equipment reliability (ER) at nuclear power plants. ER consists of a comprehensive set of processes that span the organization and require extensive data gathering, retrieval, and information integration. To assist nuclear operators, the Institute of Nuclear Power Operations (INPO) issued AP-913, Equipment Reliability Process Description, as a standard approach to implement effective ER processes among its members. Despite the success tha...

2009-04-30T23:59:59.000Z

380

Plant Support Engineering: Degradation Research for Nuclear Service Level I Coatings  

Science Conference Proceedings (OSTI)

Nuclear power plants have experienced degradation of the protective coating systems (nuclear Service Level I coatings) inside reactor containment. The degradation is a matter of concern, but the history of degradation and its causes have not been thoroughly documented. In response, the Electric Power Research Institute (EPRI) and the Nuclear Utilities Coating Council (NUCC) began a research project designed to gain an understanding of the degradation and the potential influence of aging on the qualified ...

2007-09-24T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

THE INTEGRATION OF THE 241-Z BUILDING DECONTAMINATION & DECOMMISSIONING (D&D) UNDER COMPREHENSIVE ENVIRONMENTAL RESPONSE COMPENSATION & LIABILITY ACT (CERCLA) WITH RESOURCE CONSERVATION & RECOVERY ACT (RCRA) CLOSURE AT THE PLUTONIUM FINISHING PLANT (PFP)  

SciTech Connect

The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the ''Resource Conservation and Recovery Act of 1976'' (RCRA) and Washington State ''Hazardous Waste Management Act, RCW 70.105'', have been deactivated and are being actively decommissioned. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4, D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building. The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground mining from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the ''Hanford Facility Dangerous Waste Closure Plant, 241-Z Treatment and Storage Tanks''.

HOPKINS, A.M.

2007-02-20T23:59:59.000Z

382

Automatically closing swing gate closure assembly  

DOE Patents (OSTI)

A swing gate closure assembly for nuclear reactor tipoff assembly wherein the swing gate is cammed open by a fuel element or spacer but is reliably closed at a desired closing rate primarily by hydraulic forces in the absence of a fuel charge.

Chang, Shih-Chih (Richland, WA); Schuck, William J. (Richland, WA); Gilmore, Richard F. (Kennewick, WA)

1988-01-01T23:59:59.000Z

383

Establishing a Groundwater Protection Program for New Nuclear Generating Units: Appendix to the EPRI Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

New nuclear power plants should plan for groundwater protection early in the planning process. The construction project team should be made aware of the need to establish the groundwater protection program prior to the construction planning process. This document provides guidance for establishing Groundwater Protection Programs for new nuclear generating units. It applies to new nuclear generating units on both new and existing nuclear power plant ...

2013-03-27T23:59:59.000Z

384

COST COMPARISONS OF CAPITOL INVESTMENT IN VARIOUS NUCLEAR POWER PLANTS FOR CENTRAL STATION APPLICATION  

SciTech Connect

The capital costs for a number of power reactors are compared after escalation to equivalent construction dates. It is shown that the most important factor affecting nuclear power plant capital costs is the net capacity of the plant. Steam conditions are shown to have a relatively minor effect on capital costs. (auth)

Bender, M.; Stulting, R.D.

1958-10-14T23:59:59.000Z

385

Assessement of Codes and Standards Applicable to a Hydrogen Production Plant Coupled to a Nuclear Reactor  

DOE Green Energy (OSTI)

This is an assessment of codes and standards applicable to a hydrogen production plant to be coupled to a nuclear reactor. The result of the assessment is a list of codes and standards that are expected to be applicable to the plant during its design and construction.

M. J. Russell

2006-06-01T23:59:59.000Z

386

Location dependent common cause analysis with an application to fires. [Nuclear power plants  

SciTech Connect

The purpose of the work described is to develop a methodology by which the public risk arising from localized common cause events (e.g., fires) in nuclear plants can be assessed. Attention was paid to maximizing both the completeness and efficiency of the analysis. This methodology was then applied to the analysis of fire events in the Clinch River Breeder Reactor Plant (CRBRP).

Leaver, D.; vonHerrmann, J.; Olmos, J.; Boardman, R.

1978-01-01T23:59:59.000Z

387

Life Cycle Management Plan for Main Generator and Exciter at Callaway Nuclear Plant: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides Ameren UE with an optimized LCM plan for the main generator and exciter at Callaway Plant.

2003-09-30T23:59:59.000Z

388

Exergetic analyse for the cooling systems with R-407 refrigerant for application in nuclear plants  

Science Conference Proceedings (OSTI)

The experimental Pilot plant for tritium and deuterium separation, part of National Research and Development Institute for Cryogenics and Isotopic Technologies - ICSI Rm. Valcea, as principal target have to establish the technology of the water-hydrogen ... Keywords: R407 refrigerant, irreversibility, nuclear plants, refrigeration efficiency

Sorin Gherghinescu

2010-06-01T23:59:59.000Z

389

Pre-validation of nuclear power plant control room design  

Science Conference Proceedings (OSTI)

Evaluation of the design of complex automation and control room systems is an essential phase in the design process in the nuclear field. For example, in order to meet the nuclear regulatory requirements, the new control room systems have to be evaluated ... Keywords: concept of operations, control room, pre-validation, verification & validation

Jari Laarni; Paula Savioja; Hannu Karvonen; Leena Norros

2011-07-01T23:59:59.000Z

390

Nuclear Power Plant License Renewal Environmental Compliance Program: Donald C. Cook Nuclear Case Study, Phase 1--Preliminary Planni ng  

Science Conference Proceedings (OSTI)

This report describes preliminary environmental compliance planning activities that American Electric Power (AEP) is taking to preserve the option of renewing the Donald C. Cook Nuclear Plant license. The activities are based on a program plan manual published previously by EPRI. The report includes an evaluation of the usefulness of that manual.

1997-07-08T23:59:59.000Z

391

EIS-0391: Hanford Tank Closure and Waste Management, Richland...  

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

single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal...

392

Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants  

SciTech Connect

This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs.

Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A. [St. Petersburg Mining Inst. (Russian Federation)

1994-07-01T23:59:59.000Z

393

Plant Support Engineering: Aging Management Program Development Guidance for Instrument and Control Cable Systems for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This document provides guidance for developing and implementing a cable aging management program for low-voltage instrument and control cable circuits in nuclear power plants. Guidance is provided for identifying cables located in adverse localized environments and determining if those environments have caused significant cable circuit degradation.

2010-11-29T23:59:59.000Z

394

Assessment of Nuclear Safety Culture at the Pantex Plant, November 2012  

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

Pantex Plant Pantex Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Pantex Plant Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2 3.0 Results and Conclusions ....................................................................................................................... 3 4.0 Recommendations................................................................................................................................. 5

395

Technical Guidance for Achieving Higher Levels of Electromagnetic Compatibility for Advanced Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report presents guidance for enhancing electromagnetic compatibility (EMC) for advanced nuclear power plants (NPPs). Included is a summary of EMC challenges facing these plants and the threats that utilities, equipment designers, and plant designers must be aware of. The following requested areas are covered: 1) programmatically addressing EMC through the development of an EMC protection system, 2) minimizing the use of exclusion zones through the demonstration of electromagnetic energy (EM) calcula...

2010-12-22T23:59:59.000Z

396

Incentive regulation of investor-owned nuclear power plants by public utility regulators. Revision 1  

Science Conference Proceedings (OSTI)

The US Nuclear Regulatory Commission (NRC) periodically surveys the Federal Energy Regulatory Commission (FERC) and state regulatory commissions that regulate utility owners of nuclear power plants. The NRC is interested in identifying states that have established economic or performance incentive programs applicable to nuclear power plants, how the programs are being implemented, and in determining the financial impact of the programs on the utilities. The NRC interest stems from the fact that such programs have the potential to adversely affect the safety of nuclear power plants. The current report is an update of NUREG/CR-5975, Incentive Regulation of Investor-Owned Nuclear Power Plants by Public Utility Regulators, published in January 1993. The information in this report was obtained from interviews conducted with each state regulatory agency that administers an incentive program and each utility that owns at least 10% of an affected nuclear power plant. The agreements, orders, and settlements that form the basis for each incentive program were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program.

McKinney, M.D.; Seely, H.E.; Merritt, C.R.; Baker, D.C. [Pacific Northwest Lab., Richland, WA (United States)

1995-04-01T23:59:59.000Z

397

Actions to Support Employees of Accelerated Closure Sites, 5/19/2000 |  

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

Actions to Support Employees of Accelerated Closure Sites, Actions to Support Employees of Accelerated Closure Sites, 5/19/2000 Actions to Support Employees of Accelerated Closure Sites, 5/19/2000 At present, there are approximately 400 employees assigned to accelerated closure sites. These sites are among our former nuclear production sites that are now being managed for clean up and closure on or before fiscal year 2006. As you may know, these sites have been identified in the Department's appropriations language for accelerated closure for the purpose of transitioning the real property to private commercial activities or environmentally friendly set-asides. Accelerated closure of these sites requires that employees with critical skills be retained, to the extent possible, to complete closure activities. Upon completion of closure activities requiring their specialized skills,

398

Assessment of Nuclear Safety Culture at the Pantex Plant, November...  

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

the Plant. Human Performance Improvement Coordinator works with the Safety Team and Human Error team from BBS to conduct human performance evaluations. B-12 Data on the...

399

Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for  

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

Vogtle Nuclear Power Plant -- As Vogtle Nuclear Power Plant -- As Prepared for Delivery Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery February 15, 2012 - 12:27pm Addthis It's great to be with all of you today. I want to acknowledge the many people who are playing a role here: Tom Fanning, President of Southern Company Paul Bowers, President and Chief Executive Officer of Georgia Power Tom Smith, Chief Executive Officer of Oglethorpe Power Bob Johnston, Chief Executive Officer of MEAG (Me-ag) Power Jim Bernhard, President and Chief Executive Officer of The Shaw Group Ric Perez, President of Westinghouse Operations Marv Fertel, President and Chief Executive Officer of the Nuclear Energy Institute; and Finally, all of the workers here, whose skill and expertise are

400

Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for  

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

Chu's Remarks at Vogtle Nuclear Power Plant -- As Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery February 15, 2012 - 12:27pm Addthis It's great to be with all of you today. I want to acknowledge the many people who are playing a role here: Tom Fanning, President of Southern Company Paul Bowers, President and Chief Executive Officer of Georgia Power Tom Smith, Chief Executive Officer of Oglethorpe Power Bob Johnston, Chief Executive Officer of MEAG (Me-ag) Power Jim Bernhard, President and Chief Executive Officer of The Shaw Group Ric Perez, President of Westinghouse Operations Marv Fertel, President and Chief Executive Officer of the Nuclear Energy Institute; and Finally, all of the workers here, whose skill and expertise are

Note: This page contains sample records for the topic "nuclear plant closure" 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

Kansas City Plant - 10/01/2010 to 09/30/2013 | National Nuclear Security  

National Nuclear Security Administration (NNSA)

0/01/2010 to 09/30/2013 | National Nuclear Security 0/01/2010 to 09/30/2013 | 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 Kansas City Plant - 10/01/2010 to 09/30/2013 Home > About Us > Our Operations > Acquisition and Project Management > M & O Support Department > Kansas City Plant - 10/01/2010 to 09/30/2013 Kansas City Plant - 10/01/2010 to 09/30/2013

402

Adult leukemia and proximity-based surrogates for exposure to Pilgrim plant`s nuclear emissions  

Science Conference Proceedings (OSTI)

Possible associations between adult leukemia incidence and proximity-based surrogate measures of potential for exposure to radioactive emission from the Pilgrim nuclear power plant in Plymouth, Massachusetts, were investigated. Include din this study were 105 nonchronic lymphocytic leukemia cases, diagnosed between 1978 and 1986 at age 13 y or older, that occured in 22 towns near Pilgrim; population controls numbered 208. Residence within 4 mi (6.4 km) of Pilgrim during {open_quotes}high-emissions{close_quotes} years was related to case-control status (adjusted odds ratio [OR] = 3.88, 95% confidence interval [95% Cl] = 0.81-10.64). A high {open_quotes}exposure{close_quotes} score (i.e., a value that accounted for downwind time) was also related to case-control status (OR = 3.46, 95% Cl = 1.50-7.96). Some statistically significant dose-response trends were found. Cautious interpretation of associations is warranted in light of the low levels of reported emission. 42 refs., 1 fig., 4 tabs.

Morris, M.S.; Knorr, R.S. [Massachusetts Dept. of Public Health, Boston, MA (United States)

1996-07-01T23:59:59.000Z

403

Aging Management of Nuclear Power Plant Concrete Structures - Overview and Suggested Research Topics  

SciTech Connect

Nuclear power plant concrete structures are described and their operating experience noted. Primary considerations related to management of their aging are noted and an indication of their status provided: degradation mechanisms, damage models, and material performance; assessment and remediation (i.e., component selection, in-service inspection, nondestructive 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). Several activities are identified that provide background information and data on areas of concern with respect to nondestructive examination of nuclear power plant concrete structures: inspection of thick-walled, heavily-reinforced sections, basemats, and inaccessible areas of the containment metallic pressure boundary. Topics are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

Naus, Dan J [ORNL

2008-01-01T23:59:59.000Z

404

Natural Versus Artificial Aging of Nuclear Power Plant Components  

Science Conference Proceedings (OSTI)

Examination of test specimens, placed in eight operating reactors during this study, will provide information on the long-term aging effects of plant environments on cabling and electrical components. Material property data, when compared with measured degradation in artificially aged specimens, will help improve predictions of the safe, useful life of plant equipment.

1986-12-31T23:59:59.000Z

405

Identification of performance indicators for nuclear power plants  

E-Print Network (OSTI)

Performance indicators have been assuming an increasingly important role in the nuclear industry. An integrated methodology is proposed in this research for the identification and validation of performance indicators for ...

Sui, Yu, 1973-

2001-01-01T23:59:59.000Z

406

Enterprise Knowledge Management System for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Although initially proposed by the Nuclear Sector, an enterprise knowledge management system can support the work of all business sectors ... fossil generation, nuclear generation, power delivery, environment, as well as business operations. The motivation for this project is the concern that valuable skills, expertise and the corporate knowledge base may be lost due to retirements and other forms of attrition associated with an aging workforce. As originally conceived, the objective of this BSI project ...

2005-01-23T23:59:59.000Z

407

Station blackout at nuclear power plants: Radiological implications for nuclear war  

Science Conference Proceedings (OSTI)

Recent work on station blackout is reviewed its radiological implications for a nuclear war scenario is explored. The major conclusion is that the effects of radiation from many nuclear weapon detonations in a nuclear war would swamp those from possible reactor accidents that result from station blackout.

Shapiro, C.S.

1986-12-01T23:59:59.000Z

408

Source book for planning nuclear dual-purpose electric/distillation desalination plants  

SciTech Connect

A source book on nuclear dual-purpose electric/distillation desalination plants was prepared to assist government and other planners in preparing broad evaluations of proposed applications of dual-purpose plants. The document is divided into five major sections. Section 1 presents general discussions relating to the benefits of dual-purpose plants, and spectrum for water-to-power ratios. Section 2 presents information on commercial nuclear plants manufactured by US manufacturers. Section 3 gives information on distillation desalting processes and equipment. Section 4 presents a discussion on feedwater pretreatment and scale control. Section 5 deals with methods for coupling the distillation and electrical generating plants to operate in the dual mode.

Reed, S.A.

1981-02-01T23:59:59.000Z

409

Department of Energy interest and involvement in nuclear plant license renewal activities  

SciTech Connect

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE cosponsored with the Electric Power Research Institute (EPRI) pilot-plant efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot-plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankee Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions, and ongoing activities of the DOE effort. 18 refs.

Bustard, L.D. (Sandia National Labs., Albuquerque, NM (USA)); Harrison, D.L. (USDOE Assistant Secretary for Nuclear Energy, Washington, DC (USA). Office of LWR Safety and Technology)

1991-01-01T23:59:59.000Z

410

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

411

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

412

Use of fuel cells for improving on-site emergency power availability and reliability ad nuclear power plants  

E-Print Network (OSTI)

To assure safe shutdown of a nuclear power plant, there must always be reliable means of decay heat removal provided, in last resort, by an Emergency Core Cooling System (ECCS). Currently the majority of nuclear power ...

Akkaynak, Derya

2005-01-01T23:59:59.000Z

413

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

414

Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability  

SciTech Connect

The U.S. Department of Energys Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

2013-03-01T23:59:59.000Z

415

Examination of cracked turbine discs from nuclear power plants  

SciTech Connect

Investigations were performed on a cracked turbine disc from the Cooper Nuclear Power Station (BWR), and on two failed turbine discs from the Yankee-Rowe Nuclear Power Station (PWR). The Yankee-Rowe discs were subjected to SEM/EDAX, uniaxial tension tests, hardness testing, notch sensitivity tests, and environmental notched tensile tests. The results of this investigation support the model whereby the cracks initiated at startup of the turbine, probably from H/sub 2/S produced by hydrolysis of MoS/sub 2/, and grew at a rate consistent with published data for propagation of cracks in pure steam.

Czajkowski, C.J.; Weeks, J.R.

1983-03-01T23:59:59.000Z

416

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

Science Conference Proceedings (OSTI)

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

Robert Bean; Casey Durst

2009-10-01T23:59:59.000Z

417

Investigation on the Benefits of Safety Margin Improvement in CANDU Nuclear Power Plant Using an FPGA-based Shutdown System.  

E-Print Network (OSTI)

??The relationship between response time and safety margin of CANadian Deuterium Uranium (CANDU) nuclear power plant (NPP) is investigated in this thesis. Implementation of safety (more)

She, Jingke

2012-01-01T23:59:59.000Z

418

Explosions and other uncontrolled chemical reactions at non-reactor nuclear facilities of the Savannah River Plant  

Science Conference Proceedings (OSTI)

This paper describes five energetic reactions (explosions) that have occurred at the Savannah River Plant non-reactor nuclear facilities. 1 fig.

Durant, W.S.; Gray, L.W.; Wallace, R.M.; Yau, W.W.F.

1988-01-01T23:59:59.000Z

419

Plant Support Engineering: Guidance for Replacing Heat Exchangers at Nuclear Power Plants with Plate Heat Exchangers  

Science Conference Proceedings (OSTI)

This report is the first of a "suite" of guidelines that will enable licensees to be "intelligent customers" when faced with replacing major plant components like heat exchangers to support license renewal and plant life extension.

2006-07-31T23:59:59.000Z

420

Groundwater and Soil Remediation Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) Groundwater and Soil Remediation Guidelines provides the nuclear power industry with technical guidance for evaluating the need for and timing of remediation of soil and/or groundwater contamination from onsite leaks, spills, or inadvertent releases to a) prevent migration of licensed material off-site and b) minimize decommissioning impacts.

2010-12-21T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Transport of radioactive droplet moisture from a source in a nuclear power plant spray pond  

Science Conference Proceedings (OSTI)

In addition to a change in the microclimate in the region surrounding a nuclear power plant resulting from the emission of vapor form a cooling tower, evaporation of water from the water surface of a cooling pond or a spray pond, in the latter case direct radioactive contamination of the underlying surface around the nuclear power plant can also occur due to discharge of process water (radioactive) into the pond and its transport in the air over a certain distance in the form of droplet moisture. A typical example may be the situation at the Zaporozhe nuclear power plant in 1986 when accidental discharge of process water into the cooling pond occurred. Below we present a solution for the problem of transport of droplet moisture taking into account its evaporation, which may be used to estimate the scale of radioactive contamination of the locality.

Elokhin, A.P.

1995-11-01T23:59:59.000Z

422

OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS  

SciTech Connect

This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

Ronald L. Boring

2012-10-01T23:59:59.000Z

423

Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Volume Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant Supplemental Volume Table of Contents Foreword ...................................................................................................................................................... iii Acronyms ...................................................................................................................................................... v

424

The status of nuclear power plants in the People's Republic of China  

SciTech Connect

China's main energy source is coal, but transportation and environmental problems make that fuel less than desirable. Therefore, the Chinese, as part of an effort toward alternative energy sources, are developing nuclear power plants. In addition to providing a cleaner power source, development of nuclear energy would improve the Chinese economic condition and give the nation greater world status. China's first plants, at Qinshan and Daya Bay, are still incomplete. However, China is working toward completion of those reactors and planning the training and operating procedures needed to operate them. At the same time, it is improving its nuclear fuel exports. As they develop the capability for generating nuclear power, the Chinese seem to be aware of the accompanying quality and safety considerations, which they have declared to be first priorities. 50 refs., 7 figs.

Puckett, J.

1991-05-01T23:59:59.000Z

425

Summary of Utility License Termination Documents and Lessons Learned: Summary of License Termination Plan Submittals by Three Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission's (NRC's) 1996 revised decommissioning regulations specify that the operator of a nuclear plant must submit a "License Termination Plan" (LTP) two years prior to termination of the plant license. The LTP explicitly defines the elements that the plant operator must address in the decommissioning plan. This report focuses on the approaches and experience gained by three of the leading plants in the preparation and submittal of their LTP submittals under the 1996 regul...

2002-10-28T23:59:59.000Z

426

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

427

Guide to Assessing Radiological Elements for License Termination of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report provides guidance in the preparation of a License Termination Plan (LTP) to utilities engaged in nuclear plant decommissioning. The U.S. Nuclear Regulatory Commission (NRC) requires utilities to submit the LTP document years prior to the site license termination. This report focuses on the radiological components of the LTP. It identifies and addresses the regulatory requirements of each element in a way useful to the utility end user.

2002-06-12T23:59:59.000Z

428

Technology Innovation: Fiber Bragg Gratings for Pressure Monitoring in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

To create a reliable power generation network, emerging nuclear energy reactor designs require reliable pressure-measurement technology that is not presently available. Because of their operating conditions, pressure transducers currently used in the power generation industry offer a limited usable life. An improved transducer design would have the opportunity to improve maintenance efficiencies and reliability. The usable life of current pressure-measurement technology used for nuclear power plant appli...

2012-07-16T23:59:59.000Z

429

Risk-Informed Evaluation of Protective Action Strategies for Nuclear Plant Off-Site Emergency Planning  

Science Conference Proceedings (OSTI)

All commercial nuclear power plants have developed formal emergency preparedness programs, which are implemented if actions required to protect public health and safety are deemed a necessary response to accident conditions. However, in the United States, the basis for these programs and the associated protective action strategies that would be implemented have not been modified since the time of the Three Mile Island accident. Based on the significant advancements in the knowledge of potential nuclear a...

2007-09-18T23:59:59.000Z

430

Coordination of EPRI Risk Ranking Methodologies for Nuclear Power Plant Groundwater Protection & Underground Piping Programs  

Science Conference Proceedings (OSTI)

The nuclear power industry committed to the Groundwater Protection Initiative (GPI) and the Underground Piping and Tanks Initiative (UPTI) to improve the management of soil and groundwater contamination, and the management of underground piping and tanks. These two Initiatives, while they have different objectives, are closely aligned in the area of preventing leaks and spills of licensed materials. The results of this Electric Power Research Institute (EPRI) work will provide nuclear power plant sites w...

2011-12-14T23:59:59.000Z

431

Incentive regulation of investor-owned nuclear power plants by public utility regulators  

Science Conference Proceedings (OSTI)

The US Nuclear Regulatory Commission (NRC) periodically surveys the Federal Energy Regulatory Commission (FERC) and state regulatory commissions that regulate utility owners of nuclear power plants. The NRC is interested in identifying states that have established economic or performance incentive programs applicable to nuclear power plants, including states with new programs, how the programs are being implemented, and in determining the financial impact of the programs on the utilities. The NRC interest stems from the fact that such programs have the potential to adversely affect the safety of nuclear power plants. The information in this report was obtained from interviews conducted with each state regulatory agency that administers an incentive program and each utility that owns at least 10% of an affected nuclear power plant. The agreements, orders, and settlements that form the basis for each incentive program were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program.

McKinney, M.D.; Elliot, D.B. (Pacific Northwest Lab., Richland, WA (United States))

1993-01-01T23:59:59.000Z

432

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

433

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography  

SciTech Connect

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

Youngen, G.

1988-10-01T23:59:59.000Z

434

Neutron dosimetry at commercial nuclear plants. Final report of Subtask B: dosimeter response  

SciTech Connect

As part of a larger program to evaluate personnel neutron dosimetry at commercial nuclear power plants, this study was designed to characterize neutron dosimeter responses inside the containment structure of commercial nuclear plants. In order to characterize those responses, dosimeters were irradiated inside containment at 2 pressurized water reactors and at pipe penetrations outside the biological shield at two boiling water reactors. The reactors were operating at full power during the irradiations. Measurements were also performed with electronic instruments, the tissue equivalent proportional counter (TEPC), and portable remmeters, SNOOPY, RASCAL and PNR-4.

Cummings, F.M.; Endres, G.W.R.; Brackenbush, L.W.

1983-03-01T23:59:59.000Z

435

Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments  

Science Conference Proceedings (OSTI)

In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''.

Jose Reyes

2005-02-14T23:59:59.000Z

436

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

437

Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers  

SciTech Connect

This report is a guidance document prepared for the benefit of commercial nuclear power plants (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making, planning, and preparation of a business case.

Heather D. Medema; Ronald K. Farris

2012-09-01T23:59:59.000Z

438

Comments on the leak-before-break concept for nuclear power plant piping systems  

SciTech Connect

The leak-before-break concept is based on the idea that, with a high degree of probability, failure of the pressure boundary of piping systems will be signaled by a detectable leak that will provide ample time to shutdown and repair that leak. The status of the leak-before-break concept is discussed in this report, including a review of industrial and nuclear power plant experience with respect to leak-before-break, fracture mechanics, and potential elimination of postulated pipe breaks in nuclear power plant piping design. 36 refs., 12 figs., 3 tabs.

Rodabaugh, E.C.

1985-08-01T23:59:59.000Z

439

YAEC's view of the cause and control of escalating nuclear plant O and M costs  

Science Conference Proceedings (OSTI)

This paper provides insights on this issue in terms of both the genesis and effective long-term control of O and M costs. Yankee Atomic Electric Company's (YAEC's) insights stem not only from an analysis of certain industry data, but also from its unique position within the nuclear industry in terms of its age, plant size, and organization. First, at 30 yr of age, the YAEC plant has endured the full swing of the regulatory/institutional pendulum and the associated impact on O and M costs. Second, with a size of only 185 MW(electric), YAEC's imperative since start-up has been the strict control of O and M costs while still achieving operational excellence. Finally, YAEC is an organization strictly focused on nuclear power operations and has not been distracted by fossil plant operations or other utility requirements like distribution, retail sales, etc., that may have plagued other plant operators.

Haseltine, J.D.; Lessard, L.P.

1990-01-01T23:59:59.000Z

440

Nuclear safety procedure upgrade project at USEC/MMUS gaseous diffusion plants  

SciTech Connect

Martin Marietta Utility Services has embarked on a program to upgrade procedures at both of its Gaseous Diffusion Plant sites. The transition from a U.S. Department of Energy government-operated facility to U.S. Nuclear Regulatory Commission (NRC) regulated has necessitated a complete upgrade of plant operating procedures and practices incorporating human factors as well as a philosophy change in their use. This program is designed to meet the requirements of the newly written 10CFR76, {open_quotes}The Certification of Gaseous Diffusion Plants,{close_quotes} and aid in progression toward NRC certification. A procedures upgrade will help ensure increased nuclear safety, enhance plant operation, and eliminate personnel procedure errors/occurrences.

Kocsis, F.J. III

1994-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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

Aging management guideline for commercial nuclear power plants - tanks and pools  

Science Conference Proceedings (OSTI)

Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities.

Blocker, E.; Smith, S.; Philpot, L.; Conley, J.

1996-02-01T23:59:59.000Z

442

Transgenic plants are sensitive bioindicators of nuclear pollution caused by the Chernobyl accident  

SciTech Connect

To evaluate the genetic consequences of radioactive contamination originating from the Nuclear reactor accident of Chernobyl on indigenous populations of plants and animals, it is essential to determine the rates of accumulating genetic changes in chronically irradiated populations. An increase in germline mutation rates in humans living close to the Chernobyl Nuclear Power Plant site, and a two- to tenfold increase in germline mutations in barn swallows breeding in Chernobyl have been reported. Little is known, however, about the effects of chronic irradiation on plant genomes. Ionizing radiation causes double-strand breaks in DNA, which are repaired via illegitimate or homologous recombination. The authors make use of Arabidopsis thaliana plants carrying a {beta}-glucuronidase marker gene as a recombination substrate to monitor genetic alterations in plant populations, which are caused by nuclear pollution of the environment around Chernobyl. A significant increase in somatic intrachromosomal recombination frequencies was observed at nuclear pollution levels from 0.1--900 Ci/km{sup 2}, consistent with an increase in chromosomal aberrations. This bioindicator may serve as a convenient and ethically acceptable alternative to animal systems.

Kovalchuk, I.; Kovalchuk, O. [Ivano-Frankivsk State Medical Academy (Ukraine)]|[Friedrich Miescher Inst., Basel (Switzerland); Arkhipov, A. [Chernobyl Scientific and Technical Center of International Research (Ukraine); Hohn, B. [Friedrich Miescher Inst., Basel (Switzerland)

1998-11-01T23:59:59.000Z

443

A confirmatory research approach to the measurement of EMI/RFI in commercial nuclear power plants  

Science Conference Proceedings (OSTI)

The Oak Ridge National Laboratory (ORNL) is conducting confirmatory research on the measurement of electromagnetic/radio frequency interference (EMI/RFI) in nuclear power plants while it makes a good beginning, the currently available research data are not sufficient to characterize the EMI/RFI environment of the typical nuclear plant. Data collected over several weeks at each of several observation points are required to meet this need. To collect the required data, several approaches are examined, the most promising of which is the relatively new technology of application specific spectral receivers. While several spectral receiver designs have been described in the literature, none is well suited for nuclear power plant EMI/RFI surveys. This paper describes the development of two receivers specifically designed for nuclear power plant EMI/RFI surveys. One receiver surveys electric fields between 5 MHz and 8 GHz, while the other surveys magnetic fields between 305 Hz and 5 MHz. The results of field tests at TVA`s Bull Run Fossil Plant are reported.

Kercel, S.W.

1995-02-01T23:59:59.000Z

444

FOR NUCLEAR POWER PLANTS DURING DECOMMISSIONING AND PERMANENT SHUTDOWN  

E-Print Network (OSTI)

This guide has been developed to describe methods acceptable to the NRC staff for complying with the NRCs regulations regarding fire protection programs for licensees who have certified that their plants have permanently ceased operations and that the fuel has been permanently removed from the reactor vessels.

A. Introduction

2001-01-01T23:59:59.000Z

445

A Roadmap to Deploy New Nuclear Power Plants  

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

I I Summary Report Prepared for the United States Department of Energy Office of Nuclear Energy, Science and Technology and its Nuclear Energy Research Advisory Committee Subcommittee on Generation IV Technology Planning October 31, 2001 Disclaimer This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any of its employees make 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 upon privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not

446

POWER PLANT USING A STEAM-COOLED NUCLEAR REACTOR  

SciTech Connect

A method of providing efficient and economic means for obtaining reheat from nuclear heat is described. A steamcooled steam-moderated reactor produces high-pressure, high-temperature steam. A multi-stage steam turbine partially expands the high-pressure steam, which is then withdrawn and reheated, and then further expanded for producing useful power. The saturated steam is superheated by leading it through tubular passages provided in the fuel assemblies of a nuclear reactor, leading the useful part of the superheated steam into a steam turbine in which it expands to a predetermined intermediate pressure, leading the steam at that reduced pressure from the turbine back into the reactor where it is reheated by flowing through other tubular passages in the fuel assemblies, and returning the reheated steam to the turbine for further expansion. (M.C.G.)

Nettel, F.; Nakanishi, T.

1963-10-29T23:59:59.000Z

447

Examination of turbine discs from nuclear power plants  

SciTech Connect

Investigations were performed on a cracked turbine disc from the Cooper Nuclear Power Station, and on two failed turbine discs (governor and generator ends) from the Yankee-Rowe Nuclear Power Station. Cooper is a boiling water reactor (BWR) which went into commercial operation in July 1974, and Yankee-Rowe is a pressurized water reactor (PWR) which went into commercial operation in June 1961. Cracks were identified in the bore of the Cooper disc after 41,913 hours of operation, and the disc removed for repair. At Yankee-Rowe two discs failed after 100,000 hours of operation. Samples of the Cooper disc and both Yankee-Rowe disc (one from the governor and one from the generator end of the LP turbine) were sent to Brookhaven National Laboratory (BNL) for failure analysis.

Czajkowski, C.J.; Weeks, J.R.

1982-01-01T23:59:59.000Z

448

The debate over re-licensing the Vermont Yankee nuclear power plant  

Science Conference Proceedings (OSTI)

In 2009, the NRC's Atomic Safety and Licensing Board approved a 20-year license extension for the Vermont Yankee Nuclear Power plant. Less than seven months later, the Vermont State Senate voted 26-4 to block the required certificate for public good. How did a plant seen as likely to be re-licensed become the first in 20 years to be rejected in a public vote? (author)

Watts, Richard; Hines, Paul; Dowds, Jonathan

2010-05-15T23:59:59.000Z

449

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

450

Reliability and Risk Significance: For Maintenance and Reliability Professionals at Nuclear Power Plants (Japanese Version)  

Science Conference Proceedings (OSTI)

This Japanese version of Report 1007079 explains the connections between the reliability and availability of commercial nuclear power plant components and their risk significance as measured by a probabilistic safety assessment (PSA). The scope covers the two most common measures of risk significance and how they can be used to inform plant decision makers about risk. It also provides guidance on achieving balance between reliability and availability when performing preventive maintenance (PM) and on est...

2012-06-19T23:59:59.000Z

451

Comparison of Decommissioning Dose Modeling Codes for Nuclear Power Plant Use: RESRAD and DandD  

Science Conference Proceedings (OSTI)

A number of power plants are currently in the decommissioning phase. As the plants seek to terminate their operating license, they need to successfully conduct definite dose assessments. To assist these utilities in selecting an analysis code and appropriate input data, EPRI conducted a code comparison. However, this report was done as the industry's input to the NRC on their evolving review and improvement of decommissioning modeling. In early 2000, EPRI will publish a report for the commercial nuclear ...

1999-10-29T23:59:59.000Z

452

Use of In-Situ Gamma Spectroscopy During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

Due to leakage and other events that may occur during nuclear power plant operations, soil, concrete and bedrock have the potential to become contaminated, and therefore must be characterized to demonstrate that they meet strict regulatory site release limits. This report provides detailed information on the use of portable gamma spectroscopy systems for the characterization and Final Status Survey of soil, concrete and bedrock contaminated with radionuclides at a number of plants undergoing decommission...

2010-12-06T23:59:59.000Z

453

Main Generator and Exciter Life Cycle Management Plans at STARS Nuclear Plants  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This CD is a compilation of six optimum LCM plans for the main generators and exciters at the six STARS plants and also contains a generic LCM information "sourcebook" for generators.

2003-09-30T23:59:59.000Z

454

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

455

Management of the Licensed Bases of Advanced Nuclear Plants: Proof of Approach  

Science Conference Proceedings (OSTI)

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its lifecycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This project adopted and demonstrated a "twin-engine" approach that integrates a program from the emerging class of concept searching tools with a mod...

2000-08-28T23:59:59.000Z

456

Nuclear Power Plant Risk Analysis and Management for Critical Asset Protection (RAMCAP) Trial Applications Summary Report  

Science Conference Proceedings (OSTI)

The nuclear power plant risk analysis and management for critical asset protection (NPP RAMCAP ) methodology provides a common, high-level framework for evaluating NPP risk from terrorist attacks that plant owners/operators can use. Development of this method has been coordinated with other U.S. Department of Homeland Security (DHS) efforts in order to enable a consistent risk characterization among all critical infrastructure sectors. This effort culminated in a generic RAMCAP methodology potentially ap...

2005-12-22T23:59:59.000Z

457

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

458

Hydrogen Detection in Nuclear Power Plants: Comparison of Potential, Existing, and Innovative Technologies  

Science Conference Proceedings (OSTI)

The ability to monitor hydrogen volumes accurately and quickly within containment environments at nuclear power plants is a critical capability, especially during accident conditions where hydrogen generation may be occurring within the reactor vessel. Since the initial installation of hydrogen monitoring systems in plants following the Three Mile Island accident in 1979, new technologies have been developed and offer performance advantages when compared with existing installed sensors. In addition ...

2013-12-13T23:59:59.000Z

459

EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington |  

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

391: Hanford Tank Closure and Waste Management, Richland, 391: Hanford Tank Closure and Waste Management, Richland, Washington EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington Summary This EIS evaluates the environmental impacts for the following three key areas: (1) retrieval, treatment, and disposal of waste from 149 single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal of Hanford's waste and other DOE sites' low-level and mixed low-level radioactive waste. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 13, 2013 EIS-0391: Record of Decision Final Tank Closure and Waste Management Environmental Impact Statement for

460

A COMPARISON OF THE NUCLEAR DEFENSE CAPABILITIES ON NUCLEAR AND COAL-FIRED POWER PLANTS. FUEL COST STUDY VARIOUS REACTORS AT 100 AND 300 Mwe  

SciTech Connect

Appendices C and D may further be identified as SL1925 and CF-61-12- 20(Rev.), respectively. A comparative report is presented in which the economics and feasibility of plant protection from nuclear attack by plant hardening, remote siting, and utilization of optional fueling concepts for the coal-fired plant are evaluated. (J.R.D.)

Gift, E.H.

1962-05-29T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear plant closure" 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.


461

NUCLEAR-CONVENTIONAL POWER PLANT COST STUDY CONVENTIONAL COAL FIRED POWER PLANTS, 25,000 KW TO 325,000 KW, FOR ARGONNE NATIONAL LABORATORY, LEMONT, ILLINOIS  

SciTech Connect

In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. ( A.C.)

Chittenden, W.A.

1959-03-01T23:59:59.000Z

462

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

463

COOLING WATER ISSUES AND OPPORTUNITIES AT U.S. NUCLEAR POWER PLANTS  

SciTech Connect

This report has been prepared for the Department of Energy, Office of Nuclear Energy (DOE-NE), for the purpose of providing a status report on the challenges and opportunities facing the U.S. commercial nuclear energy industry in the area of plant cooling water supply. The report was prompted in part by recent Second Circuit and Supreme Court decisions regarding cooling water system designs at existing thermo-electric power generating facilities in the U.S. (primarily fossil and nuclear plants). At issue in the courts have been Environmental Protection Agency regulations that define what constitutes Best Technology Available for intake structures that withdraw cooling water that is used to transfer and reject heat from the plants steam turbine via cooling water systems, while minimizing environmental impacts on aquatic life in nearby water bodies used to supply that cooling water. The report was also prompted by a growing recognition that cooling water availability and societal use conflicts are emerging as strategic energy and environmental issues, and that research and development (R&D) solutions to emerging water shortage issues are needed. In particular, cooling water availability is an important consideration in siting decisions for new nuclear power plants, and is an under-acknowledged issue in evaluating the pros and cons of retrofitting cooling towers at existing nuclear plants. Because of the significant ongoing research on water issues already being performed by industry, the national laboratories and other entities, this report relies heavily on ongoing work. In particular, this report has relied on collaboration with the Electric Power Research Institute (EPRI), including its recent work in the area of EPA regulations governing intake structures in thermoelectric cooling water systems.

Gary Vine

2010-12-01T23:59:59.000Z

464

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

465

Achieving closure at Fernald  

Science Conference Proceedings (OSTI)

When Fluor Fernald took over the management of the Fernald Environmental Management Project in 1992, the estimated closure date of the site was more than 25 years into the future. Fluor Fernald, in conjunction with DOE-Fernald, introduced the Accelerated Cleanup Plan, which was designed to substantially shorten that schedule and save taxpayers more than $3 billion. The management of Fluor Fernald believes there are three fundamental concerns that must be addressed by any contractor hoping to achieve closure of a site within the DOE complex. They are relationship management, resource management and contract management. Relationship management refers to the interaction between the site and local residents, regulators, union leadership, the workforce at large, the media, and any other interested stakeholder groups. Resource management is of course related to the effective administration of the site knowledge base and the skills of the workforce, the attraction and retention of qualified a nd competent technical personnel, and the best recognition and use of appropriate new technologies. Perhaps most importantly, resource management must also include a plan for survival in a flat-funding environment. Lastly, creative and disciplined contract management will be essential to effecting the closure of any DOE site. Fluor Fernald, together with DOE-Fernald, is breaking new ground in the closure arena, and ''business as usual'' has become a thing of the past. How Fluor Fernald has managed its work at the site over the last eight years, and how it will manage the new site closure contract in the future, will be an integral part of achieving successful closure at Fernald.

Bradburne, John; Patton, Tisha C.

2001-02-25T23:59:59.000Z

466

Applicability of base-isolation R D in non-reactor facilities to a nuclear reactor plant  

SciTech Connect

Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs.

Seidensticker, R.W.; Chang, Y.W.

1990-01-01T23:59:59.000Z

467

100-MW NUCLEAR POWER PLANT UTILIZING A SODIUM COOLED, GRAPHITE MODERATED REACTOR  

SciTech Connect

The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)

1958-02-28T23:59:59.000Z

468

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

469

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

470

Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper  

SciTech Connect

This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

Pete Jordan

2010-09-01T23:59:59.000Z

471

Nuclear power plants: Ecology and health physics. (Latest citations from the NTIS bibliographic database). Published Search  

Science Conference Proceedings (OSTI)

The bibliography contains citations concerning ecological and health aspects related to nuclear power plants. References cover radiation protection, occupational exposure, reactor safety and shielding, reactor accidents, and radiation measuring instruments. Genetic radiation effects, radiation-induced neoplasms, and radiation contaminants are examined. (Contains 50-250 citations and includes a subject term index and title list.)

NONE

1995-08-01T23:59:59.000Z

472

Trojan Nuclear Plant Decommissioning: Final Survey for the Independent Spent Fuel Storage Installation Site  

Science Conference Proceedings (OSTI)

This report describes the final radiological survey for the area where Portland General Electric (PGE) will construct the Independent Spent Fuel Storage Installation (ISFSI) at Trojan nuclear power plant. The survey fulfills the requirements for release of this area from Trojan's 10 CFR 50 license before radiation levels increase with spent fuel storage in the ISFSI.

1998-05-13T23:59:59.000Z

473

Guideline for the Seismic Technical Evaluation of Replacement Items for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This guideline provides practical, cost-effective techniques for reasonably assuring that replacement items will meet seismic performance requirements. Meeting such requirements is necessary to maintain the seismic design basis of commercial nuclear power plants. The guideline also offers a method for determining when a seismic technical evaluation of replacement items is required as part of the procurement process for spare and replacement items.

1993-06-01T23:59:59.000Z

474

Nuclear Power Plant License Renewal Environmental Life Cycle Management Plan Manual: License Renewal Environmental Compliance  

Science Conference Proceedings (OSTI)

This manual focuses on preparing to meet NRC environmental requirements for license renewal. It describes a nuclear power plant's day-to-day environmental protection activities and the relationship between these activities and a plan for preparing a license renewal environmental report supplement.

1995-06-01T23:59:59.000Z

475

Interim Guidelines for Protecting Fire-Fighting Personnel From Multiple Hazards at Nuclear Plant Sites  

Science Conference Proceedings (OSTI)

Fire fighters and other emergency response personnel may encounter radiation, heat stress, or trauma when fighting fires in nuclear power plants. Recommendations contained in this report can be effective in reducing the impact of these hazards on fire brigade safety and performance.

1989-07-28T23:59:59.000Z