Powered by Deep Web Technologies
Note: This page contains sample records for the topic "nuclear power plant" 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

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

2

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...

3

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...

4

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...

5

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...

6

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...

7

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...

8

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...

9

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...

10

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...

11

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...

12

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...

13

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...

14

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...

15

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...

16

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...

17

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...

18

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...

19

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...

20

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...

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

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...

22

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...

23

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...

24

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...

25

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...

26

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

27

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

28

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

29

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"

30

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...

31

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...

32

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...

33

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

34

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

35

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

36

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

37

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

38

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

39

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  ...

40

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

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

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 ...

42

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 ...

43

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

44

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

45

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

46

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...

47

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.

48

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...

49

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...

50

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

51

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

52

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

53

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

54

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

55

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

56

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.

57

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

58

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

59

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

60

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 power plant" 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

Michigan Nuclear Profile - Power Plants  

U.S. Energy Information Administration (EIA)

snpt2mi Donald C Cook Unit 1, Unit 2 2,069 15,646 52.8 Indiana Michigan Power Co Fermi Unit 2 1,085 7,738 26.1 Detroit Edison Co Palisades Unit 1 793 ...

62

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

63

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

64

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

65

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

66

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

67

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 -...

68

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), ...

69

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

70

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

71

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.

72

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...

73

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.

74

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 ...

75

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?

76

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

77

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

78

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

79

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

80

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

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

82

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

83

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

84

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

85

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

86

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

87

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,

88

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

89

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

90

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

91

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

92

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

93

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

94

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

95

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

96

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

97

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

98

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

99

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

100

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

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

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 Díaz; Daniel Garrido; Sergio Romero; Bartolomé Rubio; Enrique Soler; José M. Troya

2005-05-01T23:59:59.000Z

102

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

103

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

104

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

105

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

106

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

107

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

108

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

109

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

110

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

111

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 2002–2011.

2012-06-11T23:59:59.000Z

112

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

113

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

114

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

115

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

116

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

117

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

118

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 ...

119

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

120

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

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

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

122

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

123

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

124

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

125

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

126

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

127

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

128

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

129

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

130

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

131

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, ...

132

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

133

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

134

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

135

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

136

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

137

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

138

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

139

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

140

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

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

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

142

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

143

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

144

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 Energy’s (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

145

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

146

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

147

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

148

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

149

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

150

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

151

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

152

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

153

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

154

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

155

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

156

Losses of Offsite Power at U.S. Nuclear Power Plants: Summary of Experience Through 2012  

Science Conference Proceedings (OSTI)

This report describes the losses of offsite power that occurred during 2012 at nuclear power plants operating in the United States and offers insights into the causes of such events for the 10-year period from 2003 through 2012.BackgroundEach year the Electric Power Research Institute (EPRI) updates a summary of experience involving losses of offsite power. This update describes relevant events that occurred during 2012 and provides an evaluation of the ...

2013-07-31T23:59:59.000Z

157

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

158

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

159

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

160

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

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

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

162

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

163

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

164

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

165

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

166

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

167

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

168

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

169

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

170

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

171

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

172

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

173

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

174

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

175

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 Institute’s (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

176

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

177

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

178

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

179

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

180

New instrument for the confirmation of declared power histories of central station nuclear power plants  

SciTech Connect

An operationally simple, portable, microprocessor-based, unattended reactor power monitor was developed for International Atomic Energy Agency inspector use in confirming operator records of the power history of nuclear power plants. The monitor is based on the principle that the leakage neutron flux outside the biological shield is proportional to the thermal power level. The leakage flux is detected and compared with the leakage flux from the same reactor for a confirmed calibration period. Several output options are available, and a record of more than three months of hourly measurements of the themal power of the plant can be obtained. The monitor has battery backup power for interruptions of host power of duration up to 18 hours.

Dowdy, E.J.; Robba, A.A.; Hastings, R.D.; France, S.W.

1979-01-01T23:59:59.000Z

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

Nuclear power and nuclear weapons  

SciTech Connect

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described.

Vaughen, V.C.A.

1983-01-01T23:59:59.000Z

182

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

183

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

184

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

185

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

186

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

187

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

188

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

189

Nuclear Power and the Environment  

Reports and Publications (EIA)

This Nuclear Issue Paper discusses Nuclear Plant Wastes, Interactions of Fossil Fuel and Nuclear Power Waste Decisions, and the Environmental Position of Nuclear Power.

2013-05-30T23:59:59.000Z

190

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

191

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

192

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

193

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

194

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

195

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

196

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

197

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

198

Ice Thermal Storage Systems for Nuclear Power Plant Supplemental Cooling and Peak Power Shifting  

Science Conference Proceedings (OSTI)

Availability of cooling water has been one of the major issues for the nuclear power plant site selection. Cooling water issues have frequently disrupted the normal operation at some nuclear power plants during heat waves and long draught. One potential solution is to use ice thermal storage (ITS) systems that reduce cooling water requirements and boost the plant’s thermal efficiency in hot hours. ITS uses cheap off-peak electricity to make ice and uses the ice for supplemental cooling during peak demand time. ITS also provides a way to shift a large amount of electricity from off peak time to peak time. For once-through cooling plants near a limited water body, adding ITS can bring significant economic benefits and avoid forced derating and shutdown during extremely hot weather. For the new plants using dry cooling towers, adding the ITS systems can effectively reduce the efficiency loss during hot weather so that new plants could be considered in regions lack of cooling water. This paper will review light water reactor cooling issues and present the feasibility study results.

Haihua Zhao; Hongbin Zhang; Phil Sharpe; Blaise Hamanaka; Wei Yan; WoonSeong Jeong

2013-03-01T23:59:59.000Z

199

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

200

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

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

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.

202

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

203

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

204

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

205

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

206

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

207

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

208

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

209

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

210

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

211

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

212

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

213

Reliability of the emergency ac power system at nuclear power plants  

SciTech Connect

This paper contains an evaluation of the onsite ac power system reliability. The approach to determine the onsite system reliability is to gather from the operating nuclear plants detailed data that have not been available to the NRC, to select typical but detailed design features, and to combine the two to determine ac power system reliability for different designs. Fault trees were constructed from the specific designs, and the categorized data will be used to calculate a spectrum of the expected frequency of station blackout.

Battle, R.E.; Campbell, D.J.; Baranowsky, P.W.

1982-01-01T23:59:59.000Z

214

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

215

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

216

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

217

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

218

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

219

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

220

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

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

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 Energy’s (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.

222

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

223

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

224

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

225

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

226

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 ...

227

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

228

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

229

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

230

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

231

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

232

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

233

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

234

(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

235

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

236

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

237

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

238

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

239

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

240

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

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

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

242

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.”

243

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

244

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

245

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

246

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

247

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

SciTech Connect

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

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

1980-05-01T23:59:59.000Z

248

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

249

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

250

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

251

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

252

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

253

Cesium Isotope Ratios as Indicators of Nuclear Power Plant Operations  

SciTech Connect

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

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

2011-11-01T23:59:59.000Z

254

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

255

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

256

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

257

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

258

Decommissioning in the mature nuclear power industry  

SciTech Connect

Procedures for decommissioning a nuclear power plant or a spent fuel reprocessing plant are described. (DCC)

Anderson, F.H.; Slansky, C.M.

1975-01-01T23:59:59.000Z

259

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

260

Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems  

Science Conference Proceedings (OSTI)

This report presents the technical basis for establishing acceptable mitigating strategies that resolve diversity and defense-in-depth (D3) assessment findings and conform to U.S. Nuclear Regulatory Commission (NRC) requirements. The research approach employed to establish appropriate diversity strategies involves investigation of available documentation on D3 methods and experience from nuclear power and nonnuclear industries, capture of expert knowledge and lessons learned, determination of best practices, and assessment of the nature of common-cause failures (CCFs) and compensating diversity attributes. The research described in this report does not provide guidance on how to determine the need for diversity in a safety system to mitigate the consequences of potential CCFs. Rather, the scope of this report provides guidance to the staff and nuclear industry after a licensee or applicant has performed a D3 assessment per NUREG/CR-6303 and determined that diversity in a safety system is needed for mitigating the consequences of potential CCFs identified in the evaluation of the safety system design features. Succinctly, the purpose of the research described in this report was to answer the question, 'If diversity is required in a safety system to mitigate the consequences of potential CCFs, how much diversity is enough?' The principal results of this research effort have identified and developed diversity strategies, which consist of combinations of diversity attributes and their associated criteria. Technology, which corresponds to design diversity, is chosen as the principal system characteristic by which diversity criteria are grouped to form strategies. The rationale for this classification framework involves consideration of the profound impact that technology-focused design diversity provides. Consequently, the diversity usage classification scheme involves three families of strategies: (1) different technologies, (2) different approaches within the same technology, and (3) different architectures within the same technology. Using this convention, the first diversity usage family, designated Strategy A, is characterized by fundamentally diverse technologies. Strategy A at the system or platform level is illustrated by the example of analog and digital implementations. The second diversity usage family, designated Strategy B, is achieved through the use of distinctly different technologies. Strategy B can be described in terms of different digital technologies, such as the distinct approaches represented by general-purpose microprocessors and field-programmable gate arrays. The third diversity usage family, designated Strategy C, involves the use of variations within a technology. An example of Strategy C involves different digital architectures within the same technology, such as that provided by different microprocessors (e.g., Pentium and Power PC). The grouping of diversity criteria combinations according to Strategies A, B, and C establishes baseline diversity usage and facilitates a systematic organization of strategic approaches for coping with CCF vulnerabilities. Effectively, these baseline sets of diversity criteria constitute appropriate CCF mitigating strategies for digital safety systems. The strategies represent guidance on acceptable diversity usage and can be applied directly to ensure that CCF vulnerabilities identified through a D3 assessment have been adequately resolved. Additionally, a framework has been generated for capturing practices regarding diversity usage and a tool has been developed for the systematic assessment of the comparative effect of proposed diversity strategies (see Appendix A).

Wood, Richard Thomas [ORNL; Belles, Randy [ORNL; Cetiner, Mustafa Sacit [ORNL; Holcomb, David Eugene [ORNL; Korsah, Kofi [ORNL; Loebl, Andy [ORNL; Mays, Gary T [ORNL; Muhlheim, Michael David [ORNL; Mullens, James Allen [ORNL; Poore III, Willis P [ORNL; Qualls, A L [ORNL; Wilson, Thomas L [ORNL; Waterman, Michael E. [U.S. Nuclear Regulatory Commission

2010-02-01T23:59:59.000Z

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

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

262

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

263

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

264

COSTS OF NUCLEAR POWER  

SciTech Connect

The discussion on the costs of nuclear power from stationary plants, designed primarily for the generation of electricity. deals with those plants in operation, being built, or being designed for construction at an early date. An attempt is made to consider the power costs on the basis of consistent definitions and assumptions for the various nuclear plants and for comparable fossil-fuel plants. Information on several new power reactor projects is included. (auth)

1961-01-01T23:59:59.000Z

265

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

266

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

267

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

268

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 ...

269

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

270

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

271

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

272

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

273

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

274

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

275

Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants,  

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

Cooling Water Issues and Opportunities at U.S. Nuclear Power Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants, December 2010 Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants, December 2010 Energy and water are both essential to sustainable development and economic productivity. Ample supplies of water are essential to energy production, and water management is dependent on ample supplies of energy for water treatment and transportation. The critical nexus between energy and water has been recognized in a variety of recent studies, but the policy and regulatory machinery that this nexus depends on is not keeping up with the growing challenges. Population growth and societal demand for improved quality of life will require more clean water for drinking and sanitation, more water for

276

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants  

Science Conference Proceedings (OSTI)

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

Not Available

1980-04-01T23:59:59.000Z

277

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

278

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

279

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

280

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

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

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

282

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

283

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

284

A data acquisition system for the Laguna Verde nuclear power plant  

Science Conference Proceedings (OSTI)

This paper focuses on a Data Acquisition Real-Time System developed for the Laguna Verde Nuclear Power Plant in Veracruz, Mexico. Due to the fact that the data acquisition modules needed to be replaced, the need for a New Acquisition System arose. Replacing ... Keywords: Linux, archive, data acquisition system, design, real-time, software

Ilse Leal Aulenbacher; José María Suárez Jurado

2009-11-01T23:59:59.000Z

285

Guide for Predicting Long-Term Reliability of Nuclear Power Plant Systems, Structures, and Components  

Science Conference Proceedings (OSTI)

This report provides guidelines for predicting long-term reliability of nuclear power plant systems, structures, and components. The methods described will allow life cycle management planners to make improved estimates of lost generation and revenues, which play an important role in the choice of the economically optimum long-term maintenance plan for systems and components.

2002-12-05T23:59:59.000Z

286

Characteristics of water chemistry in heavy water recovery system of nuclear power plant  

Science Conference Proceedings (OSTI)

The moisture inside the coolant and moderator system areas of Candu-type nuclear power plant is recycled to prevent the deuterium of value from being lost and the tritium of harm from being spread to the natural environment. The deuterium is separated ... Keywords: anion, breakthrough time, cation, deuterium recovery, ion exchange, resin ratio

In Hyoung Rhee; Hyun Kyoung Ahn; Hyun Jun Jeong

2007-02-01T23:59:59.000Z

287

Use of Level 3 PSA in Risk Informed, Performance Based Regulation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

At the request of the South Texas Electric Generating Station (STP), EPRI assessed the role of probabilistic safety assessment (PSA) Level 3 consequence analysis in the regulation of nuclear power plants. By surveying use of consequence analysis codes, their development, and current status, this report attempts to put Level 3 PSAs in perspective relative to their usefulness for making regulatory decisions.

1998-02-19T23:59:59.000Z

288

Wind Tunnel Experiment for Predicting a Visible Plume Region from a Nuclear Power Plant Cooling Tower  

Science Conference Proceedings (OSTI)

The current paper introduces a wind tunnel experiment to study the effect of the cooling tower of a Nuclear Power Plant (NPP) on the flow and the characteristics of visible plume regions. The relevant characteristics of the flow field near the ...

Guo Dong-peng; Yao Ren-tai; Fan Dan

289

Delays in nuclear power plant construction. Progress report, September 15, 1976--September 14, 1977  

SciTech Connect

This report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts that 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.

1977-08-10T23:59:59.000Z

290

Aerial Radiation Measurements from the Fukushima Dai-ichi Nuclear Power Plant Accident  

SciTech Connect

This document is a slide show type presentation concerning DOE and Aerial Measuring System (AMS) activities and results with respect to assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. These include ground monitoring and aerial monitoring.

Guss, P. P.

2012-07-16T23:59:59.000Z

291

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

292

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

293

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

294

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

295

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

296

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

297

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

298

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

299

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 5–10 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

300

Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications  

SciTech Connect

This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor technology, and PHM software architectures is provided. Appropriate codes and standards for PHM are discussed, along with a description of the ongoing work in developing additional necessary standards. Finally, an outline of key research needs and opportunities that must be addressed in order to support the application of PHM in legacy and new NPPs is presented.

Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.; Hines, Wes; Upadhyaya, Belle

2012-07-17T23:59:59.000Z

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

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

302

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

303

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

304

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

305

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

306

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 NRC’s 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

307

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

308

The Decline and Death of Nuclear Power  

E-Print Network (OSTI)

since the Cold War, nuclear power plants are being plannedthe fuel used in nuclear power plants is almost completelya mere 43% believe that more nuclear power plants should be

Melville, Jonathan

2013-01-01T23:59:59.000Z

309

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

310

Can New Nuclear Power Plants be Project Financed?  

E-Print Network (OSTI)

manufacturing companies with sites in France contracted in 2010 for 24 year power contracts from EDF through a special purpose vehicle company called Exeltium.4 The Olkiluoto NPP under construction in Finland is backed by several long term power contracts... independent project company financed with equity from one or more sponsoring firms and non-recourse debt for the purpose of investing in a capital asset”. The key feature of project financing is that a new company (known as a special purpose vehicle (SPV...

Taylor, Simon

311

The potential role of new technology for enhanced safety and performance of nuclear power plants through improved service maintenance  

E-Print Network (OSTI)

Refinements in the safety and performance of nuclear power plants must be made to maintain public confidence and ensure competitiveness with other power sources. The aircraft industry, US Navy, and other programs have ...

Achorn, Ted Glen

1991-01-01T23:59:59.000Z

312

Space Nuclear Power Plant Pre-Conceptual Design Report, For Information  

Science Conference Proceedings (OSTI)

This letter transmits, for information, the Project Prometheus Space Nuclear Power Plant (SNPP) Pre-Conceptual Design Report completed by the Naval Reactors Prime Contractor Team (NRPCT). This report documents the work pertaining to the Reactor Module, which includes integration of the space nuclear reactor with the reactor radiation shield, energy conversion, and instrumentation and control segments. This document also describes integration of the Reactor Module with the Heat Rejection segment, the Power Conditioning and Distribution subsystem (which comprise the SNPP), and the remainder of the Prometheus spaceship.

B. Levine

2006-01-27T23:59:59.000Z

313

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

SciTech Connect

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

Naus, Dan J [ORNL

2014-01-01T23:59:59.000Z

314

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

SciTech Connect

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

Naus, Dan J [ORNL

2010-01-01T23:59:59.000Z

315

Extending Sensor Calibration Intervals in Nuclear Power Plants  

SciTech Connect

Currently in the USA, sensor recalibration is required at every refueling outage, and it has emerged as a critical path item for shortening outage duration. International application of calibration monitoring, such as at the Sizewell B plant in UK, has shown that sensors may operate for eight years, or longer, within calibration tolerances. Online monitoring can be employed to identify those sensors which require calibration, allowing for calibration of only those sensors which need it. The US NRC accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no plants have been granted the necessary license amendment to apply it. This project addresses key issues in advanced recalibration methodologies and provides the science base to enable adoption of best practices for applying online monitoring, resulting in a public domain standardized methodology for sensor calibration interval extension. Research to develop this methodology will focus on three key areas: (1) quantification of uncertainty in modeling techniques used for calibration monitoring, with a particular focus on non-redundant sensor models; (2) accurate determination of acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and (3) the use of virtual sensor estimates to replace identified faulty sensors to extend operation to the next convenient maintenance opportunity.

Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Shumaker, Brent; Hashemian, Hash

2012-11-15T23:59:59.000Z

316

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 plant’s 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

317

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

318

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

319

Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06  

SciTech Connect

Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes and standards. - 5. Plant Safety Assessment and Regulatory Issues Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management, assessment and management of aging, degradation and damage, life extension lessons from plant operations, probabilistic safety assessment, plant safety analysis, reliability engineering, operating and future plants. - 6. Thermal Hydraulic Analysis and Testing Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. - 7. Core and Fuel Cycle Concepts and Experiments Core physics, advances in computational reactor analysis, in-core fuel management, mixed-oxide fuel, thorium fuel cycle, low moderation cores, high conversion reactor designs, particle and pebble bed fuel design, testing and reliability; fuel cycle waste minimization, recycle, storage and disposal. - 8. Materials and Structural Issues Fuel, core, RPV and internals structures, advanced materials issues and fracture mechanics, concrete and steel containments, space structures, analysis, design and monitoring for seismic, dynamic and extreme accidents; irradiation issues and materials for new plants. - 9. Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, fully integrated fuel cycle and symbiotic nuclear power systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co-generation applications. - 10. Near Term Issues (New) Applies to plants that have a significa

NONE

2006-07-01T23:59:59.000Z

320

Integrated head package cable carrier for a nuclear power plant  

DOE Patents (OSTI)

A cabling arrangement is provided for a nuclear reactor located within a containment. Structure inside the containment is characterized by a wall having a near side surrounding the reactor vessel defining a cavity, an operating deck outside the cavity, a sub-space below the deck and on a far side of the wall spaced from the near side, and an operating area above the deck. The arrangement includes a movable frame supporting a plurality of cables extending through the frame, each connectable at a first end to a head package on the reactor vessel and each having a second end located in the sub-space. The frame is movable, with the cables, between a first position during normal operation of the reactor when the cables are connected to the head package, located outside the sub-space proximate the head package, and a second position during refueling when the cables are disconnected from the head package, located in the sub-space. In a preferred embodiment, the frame straddles the top of the wall in a substantially horizontal orientation in the first position, pivots about an end distal from the head package to a substantially vertically oriented intermediate position, and is guided, while remaining about vertically oriented, along a track in the sub-space to the second position.

Meuschke, Robert E. (Monroeville, PA); Trombola, Daniel M. (Murrysville, PA)

1995-01-01T23:59:59.000Z

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

November 2010CAPACITY FACTOR RISK AT NUCLEAR POWER PLANTS  

E-Print Network (OSTI)

We develop a model of the dynamic structure of capacity factor risk. It incorporates the risk that the capacity factor may vary widely from year-to-year, and also the risk that the reactor may be permanently shutdown prior to the end of its anticipated useful life. We then fit the parameters of the model to the IAEA’s PRIS dataset of historical capacity factors on reactors across the globe. The estimated capacity factor risk is greatest in the first year of operation. It then quickly declines over the next couple of years, after which it is approximately constant. Whether risk is constant or increasing in later years depends significantly on the probability of a premature permanent shutdown of the reactor. Because these should be very rare events, the probability is difficult to estimate reliably from the small historical sample of observations. Our base case is parameterized with a conservatively low probability of a premature permanent shutdown which yields the approximately constant variance. Our model, combined with the global historical dataset, also yields relatively low estimates for the expected level of the capacity factor through the life of the plant. Our base case estimate is approximately 74%. Focusing on alternative subsets of the data raises the estimated mean capacity factor marginally, but not significantly, unless the sample chosen is restricted to selected countries over select years. This emphasizes the need for judgment in exploiting the historical data to project future probabilities.

Yangbo Du; John E. Parsons; Yangbo Du; John E. Parsons

2010-01-01T23:59:59.000Z

322

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

323

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

324

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

Science Conference Proceedings (OSTI)

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

Not Available

1993-09-01T23:59:59.000Z

325

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

326

CONSTRUCTION DESIGN OF EBR-II: AN INTEGRATED UNMODERATED NUCLEAR POWER PLANT  

SciTech Connect

The Argoune Experimentul Breeder Reactor-II is a completely integrated nuclear power plant which employs an unmoderated reactor as a heat source, and generates 20,000 kw of electricity. The integrated nuclear plant includes the fuel re-processing and fabrication cycle and thereby makes a signigicant contribution to power reactor techaology by operating on recycled fuel. The preliminary design of this plant was described at the First International Conference on the Peaceful Uses of Atomic Energy in 1955. Although the basic design concept and objectives have remained unchanged, many modiflcations have been made in the detailed design, including separation of the facility into several plants and providing containment for the reaetor system. The plant capacity and basic power cycle have rematned essentially unchanged: 62.5 Mw thermal, 900F reactor sodium outlet temperature, and 1250-psig steam at 850F at the turbine throttle. The feed-water te mperature, however, has been increased to 550F to reduce thermal stresses in the steam generator. (auth)

Koch, L.J.; Monson, H.O.; Simmons, W.R.; Levenson, M.; Verber, F.; Hutter, E.; Jaross, R.A.; Spalding, T.R.; Simanton, J.R.; Lovoff, A.

1958-10-31T23:59:59.000Z

327

Identification of hazards in non-nuclear power plants: phase II  

DOE Green Energy (OSTI)

Electric generating stations can impose on and expose the general public and environment to adverse demands and emissions that may be considered detrimental or degrading. For example, a conventional coal fired plant demands coal as its fuel which, in turn, creates a demand for coal mining and coal transportation systems that may degrade the environment. In addition, the emissions from the coal plant (sulfur dioxide, ash, and other waste products), if not managed and controlled properly, might lead to a diminution in public health. These environmental and public hazards have been qualitatively ranked for a modern conventional coal fired power plant in the Phase I study report dated January 1978. This Phase II 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 (AFB) and pressurized fluidized bed combined-cycle (PFBCC) power generating systems, and considers the sensitivity of the hazards ranking for all the non-nuclear, i.e. coal-fired, oil-fired, and geothermal, power plants to the effects of population density, mode of plant operation, technical changes, location and environmental (temperature) effects.

Fell, R.W.

1979-08-01T23:59:59.000Z

328

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)

to the nuclear power plant, the Marine Corps base, thePower Plant Emergency Response Plan, July 1975. United States Marine

Yen, W.W.S.

2010-01-01T23:59:59.000Z

329

Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report describes the status of ongoing research towards the development of advanced algorithms for online calibration monitoring. The objective of this research is to develop the next generation of online monitoring technologies for sensor calibration interval extension and signal validation in operating and new reactors. These advances are expected to improve the safety and reliability of current and planned nuclear power systems as a result of higher accuracies and increased reliability of sensors used to monitor key parameters. The focus of this report is on documenting the outcomes of the first phase of R&D under this project, which addressed approaches to uncertainty quantification (UQ) in online monitoring that are data-driven, and can therefore adjust estimates of uncertainty as measurement conditions change. Such data-driven approaches to UQ are necessary to address changing plant conditions, for example, as nuclear power plants experience transients, or as next-generation small modular reactors (SMR) operate in load-following conditions.

Ramuhalli, Pradeep; Lin, Guang; Crawford, Susan L.; Konomi, Bledar A.; Braatz, Brett G.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

2013-09-01T23:59:59.000Z

330

Guideline for Assessing Maintenance Effectiveness: A Self-Assessment Guideline for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The EPRI Technologies for Equipment Assessment and Maintenance (TEAM) group has prepared this guideline to assist EPRI-member nuclear power plants in further improving their maintenance processes by presenting, in detail, a collection of the key elements and activities that contribute to a well-organized maintenance program. An honest assessment of these activities then provides tools that can be used to perform a self-assessment of an existing maintenance program. This assessment is directed toward how ...

2002-12-10T23:59:59.000Z

331

Environmental radiation real-time monitoring system permanently installed near Qinshan Nuclear Power Plant  

SciTech Connect

An environmental radiation real-time monitoring system with high pressure ionization chamber was developed. It has been installed permanently in the vicinity of Qinshan Nuclear Power Plant, the first built in mainland China. The system consists of four basic components: environmental radiation monitors; data communication network; a data processing center; and a remote terminal computer situated in Hangzhou. It has provided five million readings of environmental radiation levels as of January 1993. 8 refs., 1 fig., 3 tabs.

Minde Ding; Peiru Sheng; Zhangji Zhi [Suzhou Nuclear Research Institute, Jiangsu (China)

1996-03-01T23:59:59.000Z

332

SOME SPECIAL APPLICATIONS OF WELDING IN STEAM, GAS TURBINE, AND NUCLEAR POWER PLANTS  

SciTech Connect

Six special applications of welding in steam, gasturbine, and nuclear power plants are described. Experiences are quoted of: the welding of austenittc steel gas-turbine rotors; the butt welding of heat-exchanger tubes in dissimilar metals; the welding of steam pipes for advanced steam conditions; welding in relation to feedwater heaters; the construction of expansion bellows in alloy steels; and the attachment of fins to heat-exchanger tubes. (auth)

Robertson, J.M.

1961-10-01T23:59:59.000Z

333

A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)  

Science Conference Proceedings (OSTI)

EPRI's seismic margin methodology enables utility engineers to quantify a nuclear power plant's ability to withstand an earthquake greater than design and still safely shut down for at least 72 hours. This cost-effective, practical methodology uses generic screening of systems and component seismic ruggedness and does not require probabilistic calculations. The revision adds depth, detail, and more complete procedures to the original report but does not change the basic method.

1991-08-01T23:59:59.000Z

334

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

Science Conference Proceedings (OSTI)

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

2013-05-01T23:59:59.000Z

335

Review of Methods and Tools for Estimating Atmospheric Deposition of Tritium at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

As part of a groundwater protection program, nuclear power plant operators must understand the sources and concentrations of tritium in on-site groundwater. Low levels of tritium from gaseous effluents and evaporating liquid effluents held in on-site impoundments or ponds can impact the tritium concentration in groundwater through rain washout. This report reviews the methods and tools necessary to quantify the impact of such atmospherically deposited tritium in groundwater.

2009-12-08T23:59:59.000Z

336

Program on Technology Innovation: Security Technology Evaluation for New Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report provides a summary of the state-of-the-art technologies available for perimeter surveillance and intrusion detection systems. These technologies are applicable to the planning and implementation of security measures for the next generation of nuclear power plants. In the absence of intelligence information, the first indication of a potential attack would be from an intrusion into a facility. This intrusion would be detected by a properly designed and deployed perimeter security system. The a...

2007-10-22T23:59:59.000Z

337

Program Considerations for Addressing Alpha Emitting Radionuclides at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report is a technical reference for assessing the magnitude and potential dose impact of alpha emitting nuclides at nuclear power plants with elevated levels of alpha contamination. Since alpha emitting nuclides are not always easy to detect and can have serious health consequences, quantifying their presence and assessing their impact can be important. This report provides several options for modifying a radiation protection program to address elevated levels of alpha contamination.

2001-11-12T23:59:59.000Z

338

Advanced Technologies for Groundwater Monitoring and Remediation at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

As part of the industry Groundwater Protection Initiative, EPRI has been investigating groundwater monitoring and remediation technologies that have potential for implementation at nuclear power plant sites. This report explores groundwater monitoring and remediation technologies under development or implemented at other industrial and U.S. Department of Energy sites, for both radionuclide and non-radionuclide contaminants. The report documents the potential for development of these technologies for impl...

2008-12-03T23:59:59.000Z

339

The Decline and Death of Nuclear Power  

E-Print Network (OSTI)

measures founder and a nuclear reactor does fail, theafter that, the first nuclear reactor, Chicago Pile-1, wentword “nuclear” can be. Nuclear reactors in power plants are

Melville, Jonathan

2013-01-01T23:59:59.000Z

340

Dynamic reliability using entry-time approach for maintenance of nuclear power plants  

E-Print Network (OSTI)

Entry-time processes are finite-state continuous-time jump processes with transition rates depending only on the two states involved in transition, the calendar time, and the most recent arrival time, which is termed as entry-time. The entry-time processes have the potential to provide a significantly greater range of applicability and flexibility than traditional reliability tools for case studies related to equipment and components in nuclear power plants. In this dissertation, the finite difference approximation of the integrodifferential Chapman-Kolmogorov equations for the entry-time processes was developed, and then it was verified by application to some hypothetical examples that are solved by alternative means, either (semi-)analytically or via simulation. To demonstrate the ability of entry-time model to applications in nuclear power plants for a RIAM based scenario, the entry-time approach is applied to the maintenance of main generators in nuclear power using the data from INPO-EPIX database. In this application, both reliability and financial performances acquired using the entry-time approaches corresponding to different maintenance policies are presented and discussed to help make maintenance decisions for the plant management. The ability of the EPIX database to provide time-dependent failure rates is demonstrated and the techniques for extraction of failure rates from the database for main generators are also discussed.

Wang, Shuwen

2008-05-01T23:59:59.000Z

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

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

Science Conference Proceedings (OSTI)

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

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

2010-06-22T23:59:59.000Z

342

Underground collocation of nuclear power plant reactors and repository to facilitate the post-renaissance expansion of nuclear power  

SciTech Connect

Underground collocation of nuclear power reactors and the nuclear waste management facilities supporting those reactors, termed an underground nuclear park (UNP), appears to have several advantages compared to the conventional approach to siting reactors and waste management facilities. These advantages include the potential to lower reactor capital and operating cost, lower nuclear waste management cost, and increase margins of physical security and safety. Envirorunental impacts related to worker health, facility accidents, waste transportation, and sabotage and terrorism appear to be lower for UNPs compared to the current approach. In-place decommissioning ofUNP reactors appears to have cost, safety, envirorunental and waste disposal advantages. The UNP approach has the potential to lead to greater public acceptance for the deployment of new power reactors. Use of the UNP during the post-nuclear renaissance time frame has the potential to enable a greater expansion of U.S. nuclear power generation than might otherwise result. Technical and economic aspects of the UNP concept need more study to determine the viability of the concept.

Myers, Carl W [Los Alamos National Laboratory; Elkins, Ned Z [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

343

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network (OSTI)

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

A. Petraglia; C. Sabbarese; M. De Cesare; N. De Cesare; F. Quinto; F. Terrasi; A. D'Onofrio; P. Steier; L. K. Fifield; A. M. Esposito

2012-07-17T23:59:59.000Z

344

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network (OSTI)

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

2012-01-01T23:59:59.000Z

345

Considerations in the evaluation of concrete structures for continued service in aged Nuclear Power Plants (NPPs)  

SciTech Connect

Currently, there are /approximately/119 commercial nuclear power plants (NPPs) in the US either under construction, operating at low-to-full power, or awaiting an operating license. Together, these units have a net generating capacity of /approximately/110 GW(e). Assuming no life extension of present facilities, the operating licenses for these plants will start to expire in the middle of the next decade with Yankee Rowe being the first plant to attain this status. Where it is noted that with no life extension of facilities, a potential loss of electrical generating capacity in excess of 75 GW(e) could occur during the time period 2006 to 2020 when the operating licenses of 80 to 90 NPPs are scheduled to expire. A potential timely and cost-effective solution to meeting future electricity demand, which has worked well for non-nuclear generating plants, is to extend the service life (operating licenses) of existing NPPs. Since the concrete components in these plants provide a vital safety function, any continued service considerations must include an in-depth assessment of the safety-related concrete structures. 7 refs.

Naus, D.; Marchbanks, M.; Oland, B.; Arndt, G.; Brown, T.

1989-01-01T23:59:59.000Z

346

Decision to reorganise or reorganising decisions? A First-Hand Account of the Decommissioning of the Phnix Nuclear Power Plant  

E-Print Network (OSTI)

of scheduled nuclear reactor shutdowns. It was also the approach adopted for the study presented here, which in the decommissioning of nuclear facilities. ORGANISATIONAL THEORY AND RESEARCH TOOL VALIDATION The study of the Decommissioning of the Phénix Nuclear Power Plant Melchior Pelleterat de Borde, MINES ParisTech, Christophe Martin

Paris-Sud XI, Université de

347

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

Science Conference Proceedings (OSTI)

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

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

1997-12-01T23:59:59.000Z

348

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

349

Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report  

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 battery chargers, inverters and uninterruptible power supplies 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.

Berg, R.; Stroinski, M.; Giachetti, R. [Multiple Dynamics Corp., Southfield, MI (United States)

1994-02-01T23:59:59.000Z

350

Data base on dose reduction research projects for nuclear power plants. Volume 5  

SciTech Connect

This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

Khan, T.A.; Yu, C.K.; Roecklein, A.K. [Brookhaven National Lab., Upton, NY (United States)] [Brookhaven National Lab., Upton, NY (United States)

1994-05-01T23:59:59.000Z

351

Comparative analysis of United States and French nuclear power plant siting and construction regulatory policies and their economic consequences  

E-Print Network (OSTI)

Despite the substantial commitments of time and money which are devoted to the nuclear power plant siting process, the effectiveness of the system in providing a balanced evaluation of the technical, environmental and ...

Golay, Michael Warren.

1977-01-01T23:59:59.000Z

352

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

E-Print Network (OSTI)

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

Yildiz, Bilge, 1976-

2003-01-01T23:59:59.000Z

353

What are the security threats to further development of nuclear power plants in the U.S.? .  

E-Print Network (OSTI)

??What are the security threats to further development of nuclear power plants in the U.S.? The U.S. stands alone today in terms of the vast… (more)

Nottestad, Tammie L.

2010-01-01T23:59:59.000Z

354

Economic Analysis of a Nuclear Reactor Powered High-Temperature Electrolysis Hydrogen Production Plant  

DOE Green Energy (OSTI)

A reference design for a commercial-scale high-temperature electrolysis (HTE) plant for hydrogen production was developed to provide a basis for comparing the HTE concept with other hydrogen production concepts. The reference plant design is driven by a high-temperature helium-cooled nuclear reactor coupled to a direct Brayton power cycle. The reference design reactor power is 600 MWt, with a primary system pressure of 7.0 MPa, and reactor inlet and outlet fluid temperatures of 540°C and 900°C, respectively. The electrolysis unit used to produce hydrogen includes 4,009,177 cells with a per-cell active area of 225 cm2. The optimized design for the reference hydrogen production plant operates at a system pressure of 5.0 MPa, and utilizes an air-sweep system to remove the excess oxygen that is evolved on the anode (oxygen) side of the electrolyzer. The inlet air for the air-sweep system is compressed to the system operating pressure of 5.0 MPa in a four-stage compressor with intercooling. The alternating-current, AC, to direct-current, DC, conversion efficiency is 96%. The overall system thermal-to-hydrogen production efficiency (based on the lower heating value of the produced hydrogen) is 47.12% at a hydrogen production rate of 2.356 kg/s. An economic analysis of this plant was performed using the standardized H2A Analysis Methodology developed by the Department of Energy (DOE) Hydrogen Program, and using realistic financial and cost estimating assumptions. The results of the economic analysis demonstrated that the HTE hydrogen production plant driven by a high-temperature helium-cooled nuclear power plant can deliver hydrogen at a competitive cost. A cost of $3.23/kg of hydrogen was calculated assuming an internal rate of return of 10%.

E. A. Harvego; M. G. McKellar; M. S. Sohal; J. E. O'Brien; J. S. Herring

2008-08-01T23:59:59.000Z

355

Identification of hazards in non-nuclear power plants. Phase I and Phase II. Summary report  

DOE Green Energy (OSTI)

Work performed in the first step of an evaluation of the public health and safety hazards associated with non-nuclear plants is reported. This study was limited to hazards which could affect the general public outside the plant boundaries. Public health and safety hazards were identified for seven types of power plants: coal-fired conventional boiler, atmospheric fluidized bed boiler, pressurized fluidized bed-combined cycle, oil-fired, oil-fired steam turbine, combined cycle, combustion (gas) turbine, and geothermal. Major plant systems effecting the hazards were identified and are described. Potentially hazardous conditions and events were identified for normal and abnormal plant operating conditions and for accidents at the plant. A classification of each hazard was made which identifies the initiating event, the hazard source, equipment or conditions that increase, monitor or mitigate the hazard. An event tree was developed for each plant which relates the effect on the general public for each hazard and initiating event. A semi-quantitative hazard ranking was developed that provides a method of comparing the hazards and events at different types of plants. Consideration was given to the sensitivity of the hazard ranking to population density, changes in operating mode and technology changes.

Not Available

1979-08-01T23:59:59.000Z

356

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants  

Science Conference Proceedings (OSTI)

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

2007-08-01T23:59:59.000Z

357

A Review of Information for Managing Aging in Nuclear Power Plants  

SciTech Connect

Age related degradation effects in safety related systems of nuclear power plants should be managed to prevent safety margins from eroding below the acceptable limits provided in plant design bases. The Nuclear Plant Aging Research (NPAR) Pro- gram, conducted under the auspices of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, and other related aging management programs are developing technical information on managing aging. The aging management process central to these efforts consists of three key elements: 1) selecting structures, systems, and components (SSCs) in which aging should be controlled; 2) understanding the mechanisms and rates of degradation in these SSCs; and 3) managing degradation through effective inspection, surveillance, condition monitoring, trending, record keeping, mainten- ance, refurbishment, replacement, and adjustments in the operating environment and service conditions. This document concisely reviews and integrates information developed under the NPAR Program and other aging management studies and other available information related to understanding and managing age-related degradation effects and provides specific refer- ences to more comprehensive information on the same subjects.

WC Morgan; JV Livingston

1995-09-01T23:59:59.000Z

358

Emerging Technologioes in Instrumentation and Controls and Their Potential Regulatory Implications for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This paper provides a summary of eight instrumentation and control (&C) technology areas, with applications in nuclear power plants (NPPs), that were the focus of a recent study performed by Oak Ridge National Laboratory (ORNL) for the Nuclear Regulatory Commission (NRC.) The state of the technology s application in NPPs, along with potential regulatory impact(s), are discussed. The technology focus areas are: (1) sensors and measurement systems, (2) communications media and networking, (3) microprocessors and other integrated circuits, (4) computational platforms, (5) surveillance, diagnostics, and prognostics, (6) human-system interactions, (7) high-integrity software, and (8) I&C architectures in new plants. The regulatory implications of these focus areas with regard to their application in NPPs are also discussed.

Korsah, Kofi [ORNL; Bobrek, Miljko [ORNL; Cetiner, Mustafa Sacit [ORNL; Ewing, Paul D [ORNL; Holcomb, David Eugene [ORNL; Howlader, Mostofa [ORNL; Killough, Stephen M [ORNL; Kisner, Roger A [ORNL; Loebl, Andy [ORNL; Moore, Michael Roy [ORNL; Muhlheim, Michael David [ORNL; Mullens, James Allen [ORNL; Shourbaji, Ayman A [ORNL; Wilson, Thomas L [ORNL

2009-01-01T23:59:59.000Z

359

Method of installing a control room console in a nuclear power plant  

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)

1994-01-01T23:59:59.000Z

360

A STEAM POWER INSTALLATION FOR NUCLEAR POWER PLANT WITH GAS-COOLED REACTORS  

SciTech Connect

A steam power plant is designed for use with gas-cooled power reactors. In this plant, the turbine is divided into two sections, one high pressure and the other low pressure, the low-pressure turbine being the condensing turbine. The feed water from the condensing turbine is divided into two streams, one of which is brought to a higher pressure than the other. The high-pressure feed water is evaporated and superheated in the heat exchanger and then supplied to the high-pressure turbine, while the low-pressure feed water is evaporated and mixed with the exhaust steam of the highpressure turbine before superhenting and then passing to the low-pressure condensing turbine. Circulation of the reactor coolant is effected by a blower driven by a series turbine with no regulating devices and arranged in the steam plant circuit upstream of the low-pressure turbine; such a turbine works with constant efficiency over its whole load range. (D.L.C.)

1961-03-01T23:59:59.000Z

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

Use of ion exchange for the treatment of liquids in nuclear power plants  

SciTech Connect

The current and future use of ion exchange (demineralization) as a method for treating liquid radioactive streams at nuclear power plants was investigated. Pertinent data were obtained by contacting utility companies, nuclear-steam-supply system vendors, selected AEC-operated facilities, as well as ion exchange resin and equipment manufacturers. Principal emphasis was on obtaining data concerning the decontamination of aqueous solutions characterized by levels of radioactivity that range from 10/sup -7/ to 1 mu Ci/ml. Ion exchange media commonly used in nuclear power plants are synthetic organic resins of polystyrene matrix. They are utilized primarily in the mixed-bed (deep-bed) ion exchange system. Powdered resin (mixed) systems (so-called filter- demineralizer'') are also used in several recent boiling-water-reactor plants. The term decontamination factor (DF), the ratio of the feed to effluent concentration, is widely used and is assumed by designers and operators of the plants to express the ion exchange system performance. In some cases, such DF values may not represent the true system performance. To achieve a desired DF, the feed and effiuent must be sampled for the nuclides of interest and the processing discontinued when the desired effluent concentration is exceeded. Average DF values that can be obtained for various ion-exchange systems and various groups of radionuclides if good engineering practice is used in the design and operation of these systems are listed. These values are based on ion- exchange fundamentals, literature data, laboratory experiments, and plant operating experience. They represent time-average values expected under normal operating conditions rather than maximum values attainable under optimum conditions. (auth)

Lin, K.H.

1973-12-01T23:59:59.000Z

362

An aerial radiological survey of the Pilgrim Station Nuclear Power Plant and surrounding area, Plymouth, Massachusetts  

SciTech Connect

Terrestrial radioactivity surrounding the Pilgrim Station Nuclear Power Plant was measured using aerial radiolog- ical survey techniques. The purpose of this survey was to document exposure rates near the plant and to identify unexpected, man-made radiation sources within the survey area. The surveyed area included land areas within a three-mile radius of the plant site. Data were acquired using an airborne detection system that employs sodium iodide, thallium-activated detectors. Exposure rate and photopeak counts were computed from these data and plotted on aerial photographs of the survey area. Several ground-based exposure measurements were made for comparison with the,aerial survey results. Exposure rates in areas surrounding the plant site varied from 6 to 10 microroentgens per hour, with exposure rates below 6 microroentgens per hour occurring over bogs and marshy areas. Man-made radiation was found to be higher than background levels at the plant site. Radation due to nitrogen-1 6, which is produced in the steam cycle of a boiling-water reactor, was the primaty source of activity found at the plant site. Cesium-137 activity at levels slightly above those expected from natural fallout was found at isolated locations inland from the plant site. No other detectable sources of man-made radioactivity were found.

Proctor, A.E.

1997-06-01T23:59:59.000Z

363

Aging management guideline for commercial nuclear power plants-stationary batteries. Final report  

Science Conference Proceedings (OSTI)

The 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 stationary batteries 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.

Berg, R.; Shao, J.; Krencicki, G.; Giachetti, R. [Multiple Dynamics Corp., Southfield, MI (United States)

1994-03-01T23:59:59.000Z

364

Aging Management Guideline for commercial nuclear power plants: Motor control centers; Final report  

SciTech Connect

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers 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.

Toman, G.; Gazdzinski, R.; O`Hearn, E. [Ogden Environmental and Energy Services Co., Inc., Blue Bell, PA (United States)

1994-02-01T23:59:59.000Z

365

New baseload power plants  

Science Conference Proceedings (OSTI)

This is a tabulation of the results of this magazines survey of current plans for new baseload power plants. The table lists the unit name, capacity, fuel, engineering firm, constructor, suppliers for steam generator, turbine generator and flue gas desulfurization equipment, date due on-line, and any non-utility participants. The table includes fossil-fuel plants, nuclear plants, geothermal, biomass and hydroelectric plants.

Not Available

1993-04-01T23:59:59.000Z

366

Nuclear Power  

E-Print Network (OSTI)

The world of the twenty first century is an energy consuming society. Due to increasing population and living standards, each year the world requires more energy and new efficient systems for delivering it. Furthermore, the new systems must be inherently safe and environmentally benign. These realities of today's world are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. The goal of the book is to show the current state-of-the-art in the covered technical areas as well as to demonstrate how general engineering principles and methods can be applied to nuclear power systems.

Tsvetkov, Pavel

2010-08-01T23:59:59.000Z

367

Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4  

Science Conference Proceedings (OSTI)

Containment flooding is an important strategy for severe accident management of a conventional boiling water reactor (BWR) system. The purpose of this work is to investigate the containment flooding strategy of the Mark-III system after a reactor pressure vessel (RPV) breach. The Kuosheng Power Plant is a typical BWR-6 nuclear power plant (NPP) with Mark-III containment. The Severe Accident Management Guideline (SAMG) of the Kuosheng NPP has been developed based on the BWR Owners Group (BWROG) Emergency Procedure and Severe Accident Guidelines, Rev. 2. Therefore, the Kuosheng NPP is selected as the plant for study, and the MAAP4 code is chosen as the tool for analysis. A postulated specific station blackout sequence for the Kuosheng NPP is cited as a reference case for this analysis. Because of the design features of Mark-III containment, the debris in the reactor cavity may not be submerged after an RPV breach when one follows the containment flooding strategy as suggested in the BWROG generic guideline, and the containment integrity could be challenged eventually. A more specific containment flooding strategy with drywell venting after an RPV breach is investigated, and a more stable plant condition is achieved with this strategy. Accordingly, the containment flooding strategy after an RPV breach will be modified for the Kuosheng SAMG, and these results are applicable to typical Mark-III plants with drywell vent path.

Su Weinian; Wang, S.-J.; Chiang, S.-C

2005-06-15T23:59:59.000Z

368

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

369

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

370

NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency  

SciTech Connect

This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members, supplemented by other LLNL scientists, invested over 5000 person-hours of time and generated over 300 analyses and predictions.

Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

2012-02-14T23:59:59.000Z

371

The hunt for theta13 at the Daya Bay nuclear power plant  

E-Print Network (OSTI)

The Daya Bay reactor neutrino experiment is located at the Daya Bay nuclear power plant in Shenzhen, China. The experiment deploys eight "identical" antineutrino detectors to measure antineutrino fluxes from six 2.9 GW_{th} reactor cores in three underground experimental halls at different distances. The target zone of the Daya Bay detector is filled with 20 t 0.1% Gd doped LAB liquid scintillator. The baseline uncorrelated detector uncertainty is ~0.38% using current experimental techniques. Daya Bay can reach a sensitivity of <0.01 to $sin^2 2theta_{13}$ with baseline uncertainties after 3 years of data taking.

Wei Wang; for the Daya Bay collaboration

2009-10-23T23:59:59.000Z

372

The hunt for theta13 at the Daya Bay nuclear power plant  

E-Print Network (OSTI)

The Daya Bay reactor neutrino experiment is located at the Daya Bay nuclear power plant in Shenzhen, China. The experiment deploys eight "identical" antineutrino detectors to measure antineutrino fluxes from six 2.9 GW_{th} reactor cores in three underground experimental halls at different distances. The target zone of the Daya Bay detector is filled with 20 t 0.1% Gd doped LAB liquid scintillator. The baseline uncorrelated detector uncertainty is ~0.38% using current experimental techniques. Daya Bay can reach a sensitivity of <0.01 to $sin^2 2theta_{13}$ with baseline uncertainties after 3 years of data taking.

Wang, Wei

2009-01-01T23:59:59.000Z

373

Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants  

SciTech Connect

This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States); Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications

1995-03-01T23:59:59.000Z

374

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

SciTech Connect

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

NONE

1995-08-01T23:59:59.000Z

375

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

DOE Green Energy (OSTI)

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

E. A. Harvego

2006-04-01T23:59:59.000Z

376

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 HYDROGEN STORAGE FOR MIXED WIND-NUCLEAR POWER PLANTS IN  

E-Print Network (OSTI)

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 1 HYDROGEN STORAGE FOR MIXED WIND evaluation of hydrogen production and storage for a mixed wind-nuclear power plant considering some new of a combined nuclear-wind-hydrogen system is discussed first, where the selling and buying of electricity

Cañizares, Claudio A.

377

The future of nuclear power  

SciTech Connect

Present conditions and future prospects for the nuclear power industry in the United States are discussed. The presentation includes a review of trends in electrical production, the safety of coal as compared to nuclear generating plants, the dangers of radiation, the economics of nuclear power, the high cost of nuclear power in the United States, and the public fear of nuclear power. 20 refs. (DWL)

Zeile, H.J.

1987-01-01T23:59:59.000Z

378

Safety implications associated with in-plant pressurized gas storage and distribution systems in nuclear power plants  

SciTech Connect

Storage and handling of compressed gases at nuclear power plants were studied to identify any potential safety hazards. Gases investigated were air, acetylene, carbon dioxide, chlorine, Halon, hydrogen, nitrogen, oxygen, propane, and sulfur hexaflouride. Physical properties of the gases were reviewed as were applicable industrial codes and standards. Incidents involving pressurized gases in general industry and in the nuclear industry were studied. In this report general hazards such as missiles from ruptures, rocketing of cylinders, pipe whipping, asphyxiation, and toxicity are discussed. Even though some serious injuries and deaths over the years have occurred in industries handling and using pressurized gases, the industrial codes, standards, practices, and procedures are very comprehensive. The most important safety consideration in handling gases is the serious enforcement of these well-known and established methods. Recommendations are made concerning compressed gas cylinder missiles, hydrogen line ruptures or leaks, and identification of lines and equipment.

Guymon, R.H.; Casto, W.R.; Compere, E.L.

1985-05-01T23:59:59.000Z

379

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)

Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.Fuel and Geo- thermal Power Plants," by G.D. Case, T.A.

Nero, A.V.

2010-01-01T23:59:59.000Z

380

Architecture and design of third Qinshan nuclear power plant risk monitor  

SciTech Connect

Risk monitor is a real-time analysis tool to determine the point-in-time risk based on actual plant configuration, which is an important application of PSA (Probabilistic Safety Assessment). In this study the status and development trend of risk monitor were investigated and a risk monitor named TQRM (Third Qinshan nuclear power plant Risk Monitor) was developed. The B/S architecture and the two key computing methods pre-solved and resolving PSA model method adopted in TQRM were introduced. The functions and technical features were also presented. Now TQRM has been on-line for more than one year and used in the operation and maintenance of TQNPP. The experience demonstrates that TQRM's results are accurate and real-time, the architecture is stable, and it could be extended and maintained conveniently for any other Risk-Informed Application. (authors)

Wang, F.; Li, Y.; Wang, J.; Wang, J.; Hu, L. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, No.350 Shushanhu Road, Shushan District, Hefei, Anhui, 230031 (China)

2012-07-01T23:59:59.000Z

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

Radioactive Releases Impact from Kozloduy Nuclear Power Plant, Bulgaria into the Environment  

SciTech Connect

The aim of this paper is to present a general overview of the radioactive releases impact generated by Kozloduy Nuclear Power Plant (KNPP), Bulgaria to the environment and public. The liquid releases presented are known as the so called controlled water discharges, that are generated after reprocessing of the inevitable accumulated liquid radioactive waste in the plant operation process. The radionuclides containing in the liquid releases are given in the paper as a result of systematic measuring. Database for radiation doses evaluation on the public around Kozloduy NPP site is developed using IAEA LADTAP computerized program. The computer code LADTAP represents realization of a model that evaluates the public dose as a result of NPP releases under normal operation conditions. The results of this evaluation were the basic licensing document for a new liquid release limit.

Genchev, G. T.; Kuleff, I.; Tanev, N. T.; Delistoyanova, E. S.; Guentchev, T.

2002-02-26T23:59:59.000Z

382

Digital control systems in nuclear power plants: Failure information, modeling concepts, and applications. Revision 1  

SciTech Connect

This report briefly describes some current applications of advanced computerized digital display and control systems at US commercial nuclear power plants and presents the results of a literature search that was made to gather information on the reliability of these systems. Both hardware and software reliability were addressed in this review. Only limited failure rate information was found, with the chemical process industry being the primary source of information on hardware failure rates and expert opinion the primary source for software failure rates. Safety-grade digital control systems are typically installed on a functional like-for-like basis, replacing older analog systems without substantially changing interactions with other plant systems. Future work includes performing a limited probabilistic risk assessment of a representative DCS to assess its risk significance.

Galyean, W.J.

1993-06-23T23:59:59.000Z

383

Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors  

Science Conference Proceedings (OSTI)

The objective of this study was to provide a primer on the environmental effects that can affect the durability of nuclear power plant concrete structures. As concrete ages, changes in its properties will occur as a result of continuing microstructural changes (i.e., slow hydration, crystallization of amorphous constituents, and reactions between cement paste and aggregates), as well as environmental influences. These changes do not have to be detrimental to the point that concrete will not be able to meet its performance requirements. Concrete, however, can suffer undesirable changes with time because of improper specifications, a violation of specifications, or adverse performance of its cement paste matrix or aggregate constituents under either physical or chemical attack. Contained in this report is a discussion on concrete durability and the relationship between durability and performance, a review of the historical perspective related to concrete and longevity, a description of the basic materials that comprise reinforced concrete, and information on the environmental factors that can affect the performance of nuclear power plant concrete structures. Commentary is provided on the importance of an aging management program.

Naus, Dan J [ORNL

2007-02-01T23:59:59.000Z

384

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

SciTech Connect

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

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

1997-03-01T23:59:59.000Z

385

Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology  

SciTech Connect

Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report.

Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

1995-10-01T23:59:59.000Z

386

A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants  

SciTech Connect

The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A. [Brookhaven National Lab., Upton, NY (United States)

1997-08-01T23:59:59.000Z

387

Challenges in Determining the Isotopic Mixture for the Fukushima Daiichi Nuclear Power Plant  

SciTech Connect

As part of the United States response to the Fukushima Daiichi Nuclear Power Plant emergency, the National Nuclear Security Administration (NNSA) Consequence Management (CM) Teams were activated with elements deploying to Japan. The NNSA CM teams faced the urgent need for information regarding the potential radiological doses that citizens of might experience. This paper discusses the challenges and lessons learned associated with the analysis of field collected samples and gamma spectra in an attempt to determine the isotopic mixture present on the ground around the Plant. There were several interesting and surprising lessons to be learned from the sample analysis portion of the response. The paper discusses several elements of the response that were unique to the event occurring in Japan, as well as several elements that would have occurred in a U.S. nuclear reactor event. Sections of this paper address details of the specific analytical challenges faced during the efforts to analyze samples and try to understand the overall release source term.

Shanks, Arthur [Sandia National Laboratories; Fournier, Sean [Sandia National Laboratories; Shanks, Sonoya [Sandia National Laboratories

2012-05-01T23:59:59.000Z

388

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

389

Plant Modernization with Digital Reactor Protection System Safety System Upgrades at US Nuclear Power Stations  

SciTech Connect

As the current fleet of nuclear power plants in the US reaches 25+ years of operation, obsolescence is driving many utilities to implement upgrades to both their safety and non-safety-related Instrumentation and Control (I and C) Systems. Digital technology is the predominant replacement technology for these upgrades. Within the last 15 years, digital control systems have been deployed in non-safety- related control applications at many utilities. In addition, a few utilities have replaced small safety-related systems utilizing digital technology. These systems have shown digital technology to be robust, reliable and simpler to maintain. Based upon this success, acceptance of digital technology has gained momentum with both utilities and regulatory agencies. Today, in an effort to extend the operating lives of their nuclear stations and resolve obsolescence of critical components, utilities are now pursuing digital technology for replacement of their primary safety systems. AREVA is leading this effort in the United States with the first significant digital upgrade of a major safety system. AREVA has previously completed upgrades to safety-related control systems emergency diesel engine controls and governor control systems for a hydro station which serves as the emergency power source for a nuclear station. Currently, AREVA is implementing the replacement of both the Reactor Protection System (RPS) and the Engineered Safety Features Actuation System (ESFAS) on all three units at a US PWR site. (authors)

Heckle, Wm. Lloyd; Bolian, Tricia W. [AREVA NP, an AREVA and Siemens Company, 1345 Ridgeland Parkway, Suite 130 (United States)

2006-07-01T23:59:59.000Z

390

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

391

U.S. nuclear power plants as terrorist targets : threat perception and the media  

E-Print Network (OSTI)

In recent history, nuclear engineers and the nuclear power industry have been primarily concerned with two things: safety and waste. In the past few years, a third concern has risen to join these two at the top: terrorism. ...

Laughter, Mark, 1980-

2005-01-01T23:59:59.000Z

392

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

393

Secondary system modeling and method for a nuclear power plant training simulator. [PWR  

SciTech Connect

Disclosed is a method and system for the real-time simulation of the dynamic operation of a nuclear power plant in which a secondary system for operating the steam turbine includes reheaters for increasing the steam temperature and pressure between the low and high pressure turbine stages, an electrohydraulic controller for operating the turbine at required speed, a condenser for condensing turbine exhaust steam, a condensate and feedwater system for pumping condensed steam back to the secondary side of a steam generator, a gland steam system for preventing leakage from and to the atmosphere, and a cooling system for the main generator, utilizes apparatus that includes a digital computer for calculating output data corresponding to physical values for the operation of the plant in accordance with input data. A control console includes automatic and manually operable devices corresponding to plant control devices for varying the input data, and indicating devices responsive to the output data for monitoring the operation of the plant. 40 claims, 45 figures.

Johnson, S.J.

1977-08-16T23:59:59.000Z

394

Carbon-14 Background, Pathway, and Dose Calculation Analysis for Nuclear Power Plants: A Sourcebook for Accurate Carbon-14 Dose Calculations  

Science Conference Proceedings (OSTI)

Commercial nuclear power plants (NPPs) generate carbon-14 during operation, and release it in power plant effluents. This report explores the current state of carbon and carbon-14 science and understanding to identify and recommend any enhancements to carbon-14 dose calculation methodologies.BackgroundWhile the amount of carbon-14 released by NPPs is small compared to natural and other anthropogenic sources, it is important to accurately document it, along ...

2013-12-11T23:59:59.000Z

395

A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants  

SciTech Connect

Currently in the United States, periodic sensor recalibration is required for all safety-related sensors, typically occurring at every refueling outage, and it has emerged as a critical path item for shortening outage duration in some plants. Online monitoring can be employed to identify those sensors that require calibration, allowing for calibration of only those sensors that need it. International application of calibration monitoring, such as at the Sizewell B plant in United Kingdom, has shown that sensors may operate for eight years, or longer, within calibration tolerances. This issue is expected to also be important as the United States looks to the next generation of reactor designs (such as small modular reactors and advanced concepts), given the anticipated longer refueling cycles, proposed advanced sensors, and digital instrumentation and control systems. The U.S. Nuclear Regulatory Commission (NRC) accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no U.S. plants have been granted the necessary license amendment to apply it. This report presents a state-of-the-art assessment of online calibration monitoring in the nuclear power industry, including sensors, calibration practice, and online monitoring algorithms. This assessment identifies key research needs and gaps that prohibit integration of the NRC-approved online calibration monitoring system in the U.S. nuclear industry. Several needs are identified, including the quantification of uncertainty in online calibration assessment; accurate determination of calibration acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and assessment of the feasibility of using virtual sensor estimates to replace identified faulty sensors in order to extend operation to the next convenient maintenance opportunity. Understanding the degradation of sensors and the impact of this degradation on signals is key to developing technical basis to support acceptance criteria and set point decisions, particularly for advanced sensors which do not yet have a cumulative history of operating performance.

Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Hashemian, Hash; Shumaker, Brent; Cummins, Dara

2012-08-31T23:59:59.000Z

396

Aging assessment of essential HVAC chillers used in nuclear power plants  

SciTech Connect

The Pacific Northwest Laboratory conducted a comprehensive aging assessment of chillers used in the essential safety air-conditioning systems in nuclear power plants (NPPs). The chillers used, and air-conditioning systems served, vary in design from plant to plant. The review of operating experience indicated that chillers experience aging degradation and failures. The primary aging factors of concern for chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. The evaluation of Licensee Event Reports (LERs) indicated that about 38% of the failures were primarily related to aging, 55% were partially aging related, and 7% of the failures were unassignable. About 25% of the failures were primarily caused by human, design, procedure, and other errors. The large number of errors is probably directly related to the complexity of chillers and their interfacing systems. Nearly all of the LERs were the result of entering plant Technical Specification Limiting Condition for Operation (LCO) that initiated remedial actions like plant shutdown procedures. The trend for chiller-related LERs has stabilized at about 0.13 LERs per plant year since 1988. Carefully following the vendor procedures and monitoring the equipment can help to minimize and/or eliminate most of the premature failures. Recording equipment performance can be useful for trending analysis. Periodic operation for a few hours on a weekly or monthly basis is useful to remove moisture and non-condensable gases that gradually build up inside the chiller. Chiller pressurization kits are available that will help minimize the amount of moisture and air ingress to low-pressure chillers during standby periods. The assessment of service life condition monitoring of chillers indicated there are many simple to sophisticated methods available that can help in chiller surveillance and monitoring.

Blahnik, D.E.; Camp, T.W.

1996-09-01T23:59:59.000Z

397

Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System  

SciTech Connect

The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities identified by experts to improve upon the design of the DCS. A set of nine design recommendations was developed to address these potential issues. The design principles addressed the following areas: (1) color, (2) pop-up window structure, (3) navigation, (4) alarms, (5) process control diagram, (6) gestalt grouping, (7) typography, (8) terminology, and (9) data entry. Visuals illustrating the improved DCS displays accompany the design recommendations. These nine design principles serve as the starting point to a planned general DCS style guide that can be used across the U.S. nuclear industry to aid in the future design of effective DCS interfaces.

Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

2012-08-01T23:59:59.000Z

398

Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

O, J.M.; Higgins, J.; Stephen Fleger - NRC

2011-09-19T23:59:59.000Z

399

REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS  

SciTech Connect

Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

David I Gertman; Katya Le Blanc; Ronald L Boring

2011-09-01T23:59:59.000Z

400

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR  

SciTech Connect

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

1983-08-01T23:59:59.000Z

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

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 Energy’s 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

402

The Decline and Death of Nuclear Power  

E-Print Network (OSTI)

world-nuclear.org/info/Nuclear-Fuel-Cycle/Nuclear- Wastes/fuel sources; the fuel used in nuclear power plants isphase out both nuclear energy and fossil fuels at the same

Melville, Jonathan

2013-01-01T23:59:59.000Z

403

Assessment of RELAP5/MOD2 against a natural circulation experiment in Nuclear Power Plant Borssele. International Agreement Report  

Science Conference Proceedings (OSTI)

As part of the ICAP (International Code Assessment and Applications Program) agreement between ECN (Netherlands Energy Research Foundation) and USNRC, ECN has performed a number of assessment calculations for the thermohydraulic system analysis code RELAP5/MOD2/36.05. This document describes the assessment of this computer program versus a natural circulation experiment as conducted at the Borssele Nuclear Power Plant. The results of this comparison show that the code RELAP5/MOD2 predicts well the natural circulation behaviour of Nuclear Power Plant Borssele.

Winters, L. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands)

1993-07-01T23:59:59.000Z

404

Aging assessment of essential HVAC chillers used in nuclear power plants. Phase 1, Volume 1  

SciTech Connect

The Pacific Northwest Laboratory conducted a Phase I aging assessment of chillers used in the essential safety air-conditioning systems of nuclear power plants. Centrifugal chillers in the 75- to 750-ton refrigeration capacity range are the predominant type used. The chillers used, and air-conditioning systems served, vary in design from plant-to-plant. It is crucial to keep chiller internals very clean and to prevent the leakage of water, air, and other contaminants into the refrigerant containment system. Periodic operation on a weekly or monthly basis is necessary to remove moisture and noncondensable gases that gradually build up inside the chiller. This is especially desirable if a chiller is required to operate only as an emergency standby unit. The primary stressors and aging mechanisms that affect chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. Aging is accelerated by moisture, non-condensable gases (e.g., air), dirt, and other contamination within the refrigerant containment system, excessive start/stop cycling, and operating below the rated capacity. Aging is also accelerated by corrosion and fouling of the condenser and evaporator tubes. The principal cause of chiller failures is lack of adequate monitoring. Lack of performing scheduled maintenance and human errors also contribute to failures.

Blahnik, D.E.; Klein, R.F. [Pacific Northwest Lab., Richland, WA (United States)

1993-09-01T23:59:59.000Z

405

Study of Potential Sites for the Deployment of New Nuclear Power Plants  

E-Print Network (OSTI)

in the United States The work reflected in this document represents Dominion’s and Bechtel's best judgment as recognized companies familiar with the engineering, construction, and operation of nuclear power plants. Nevertheless, since the work has been based on preliminary design information only, evaluations contained in this document should be considered preliminary in nature, and are not intended to be the basis of final financial and other management decisions. The information on which these evaluations have been based was provided to Dominion and Bechtel by DOE and third parties, and, except where specifically stated otherwise, has not been independently verified. Accordingly, neither Dominion, Bechtel, nor anyone acting on their behalf makes any warranty, express or implied, as to the accuracy or completeness of the information or conclusions contained in this document or assumes any liability for damages resulting from the use of or reliance on such information or conclusions.

Bechtel Power Corporation; North Anna; Bechtel Power Corporation

2002-01-01T23:59:59.000Z

406

Automatic Scheduling of Outages of Nuclear Power Plants with Time Windows  

E-Print Network (OSTI)

We report on a successful project for transference of advanced AI technology into the domain of planning of outages of nuclear power plants as part of DOD's dual-use program. ROMAN (Rome Lab Outage Manager) is the prototype system that was developed as a result of this project. ROMAN's main innovation compared to the current state of the art of outage management tools is its capability to automatically enforce safety constraints during the planning and scheduling phase. Another innovative aspect of ROMAN is the generation of more robust schedules that are feasible over time windows. In other words, ROMAN generates a family of schedules by assigning time intervals as start times to activities rather than single point start times, without afecting the overall duration of the project. ROMAN uses a constraint satisfaction paradigm combining a global search tactic with constraint propagation. The derivation of very specialized representations for the constraints to perform efficient propaga...

Carla P. Gomes

1996-01-01T23:59:59.000Z

407

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

E-Print Network (OSTI)

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

K. A. Ainger

2001-01-01T23:59:59.000Z

408

Plant Support Engineering: Aging Management Program Development Guidance for AC and DC Low-Voltage Power Cable Systems for Nuclear P ower Plants  

Science Conference Proceedings (OSTI)

Regulatory and management concern regarding the reliability of low-voltage power cable systems at nuclear plants has been increasing for the past 5–10 years. The staff of the United States Nuclear Regulatory Commission are concerned that wetted (up to and including submergence) low-voltage power 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 sa...

2010-06-02T23:59:59.000Z

409

EPRI Independent Peer Review of the TEPCO Seismic Walkdown and Evaluation of the Kashiwazaki-Kariwa Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The Tokyo Electric Power Company's (TEPCO's) Kashiwazaki-Kariwa (KK) plant is the largest nuclear power plant in the world with a total output of 8212 MW. The KK plant is 16 kilometers away from the epicenter of the Niigataken-Chuetsu-Oki (NCO) offshore earthquake, which took place at 10:13 a.m. on July 16, 2007, and had a Richter magnitude of 6.6. Ground motion recordings at the basemat of the seven boiling water reactors at the site revealed that the S2 seismic design level had been exceeded during the...

2008-01-14T23:59:59.000Z

410

Plant Support Engineering: Guidance for the Replacement of Large Electric Motors at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

The purpose of this report is to prepare a primary source of guidance for a project manager who is coordinating a team of plant personnel tasked with replacing a large electric motor. The report provides a generic process that describes interfaces and key steps necessary to ensure that the motor is evaluated and replaced in the most cost-effective and efficient means possible. The report also provides guidance regarding the typical composition of the project team and demonstrates how performance of their...

2010-03-15T23:59:59.000Z

411

Survey of Field Programmable Gate Array Design Guides and Experience Relevant to Nuclear Power Plant Applications  

SciTech Connect

From a safety perspective, it is difficult to assess the correctness of FPGA devices without extensive documentation, tools, and review procedures. NUREG/CR-6463, "Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety Systems," provides guidance to the Nuclear Regulatory Commission (NRC) on auditing of programs for safety systems written in ten high-level languages. A uniform framework for the formulation and discussion of language-specific programming guidelines was employed. Comparable guidelines based on a similar framework are needed for FPGA-based systems. The first task involves evaluation of regulatory experience gained by other countries and other agencies, and those captured in existing standards, to identify regulatory approaches that can be adopted by NRC. If existing regulations do not provide a sufficient regulatory basis for adopting relevant regulatory approaches that are uncovered, ORNL will identify the gaps. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Bobrek, Miljko [ORNL; Bouldin, Don [ORNL; Holcomb, David Eugene [ORNL; Killough, Stephen M [ORNL; Smith, Stephen Fulton [ORNL; Ward, Christina D [ORNL

2007-09-01T23:59:59.000Z

412

Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings  

SciTech Connect

ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

Braverman, J.I.; Morante, R.

2010-07-18T23:59:59.000Z

413

BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant  

SciTech Connect

An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)

1962-10-31T23:59:59.000Z

414

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)

Power Plants. WASH~1400 (NUREG 75/014). October 1975. S.Power Plants -LWR Edison." NUREG-75! 094, October 1975. NRCof Fixed Nuclear Facilities, NUREG-75/l1l (Reprint of WASH-

Yen, W.W.S.

2010-01-01T23:59:59.000Z

415

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

416

Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Particle Erosion in Nuclear Power Plant Piping Systems  

Science Conference Proceedings (OSTI)

This report describes the most common forms of erosion encountered in nuclear power plant piping systems—cavitation, flashing, liquid droplet impingement, and solid particle erosion—and provides utility engineers with information on how to deal with these forms of damage.

2004-11-15T23:59:59.000Z

417

Modular Modeling System (MMS): A Code for the Dynamic Simulation of Fossil and Nuclear Power Plants, Volume 2: Programmer's Manual  

Science Conference Proceedings (OSTI)

Now complete and fully documented, the MMS code is available for the dynamic simulation of both fossil-fired and nuclear power plants. The broad range of applications, from troubleshooting new designs to analysis of startup tests, has made this easy-to use code a utility standard since its first-stage release in 1983.

1987-05-01T23:59:59.000Z

418

Modular Modeling System (MMS): A Code for the Dynamic Simulation of Fossil and Nuclear Power Plants, Volume 1: Theory Manual  

Science Conference Proceedings (OSTI)

Now complete and fully documented, the MMS code is available for the dynamic simulation of both fossil-fired and nuclear power plants. The broad range of applications, from troubleshooting new designs to analysis of startup tests, has made this easy-to use code a utility standard since its first-stage release in 1983.

1987-04-01T23:59:59.000Z

419

Application of Data Stream Outlier Mining Techniques in Steam Generator Safety Early Warning System of Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Mining outliers in data streams is a popular research issue in data mining field, which can help to find outliers under abnormal condition and then corresponding measures can be taken. The security guarantee of nuclear power plant is the center topic ... Keywords: safety early warning system, data stream, outlier mining, NPP

Liu Dingping, Zheng Kaitao, Yan Qiqi

2013-01-01T23:59:59.000Z

420

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

PRESENTATONS: Reawakening of United States Nuclear Energy: Materials Challenges for a New Generation of Power Plants Presentations by Harold ...

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

Thermal Design of an Ultrahigh Temperature Vapor Core Reactor Combined Cycle Nuclear Power Plant  

SciTech Connect

Current work modeling high temperature compact heat exchangers may demonstrate the design feasibility of a Vapor Core Reactor (VCR) driven combined cycle power plant. For solid nuclear fuel designs, the cycle efficiency is typically limited by a metallurgical temperature limit which is dictated by fuel and structural melting points. In a vapor core, the gas/vapor phase nuclear fuel is uniformly mixed with the topping cycle working fluid. Heat is generated homogeneously throughout the working fluid thus extending the metallurgical temperature limit. Because of the high temperature, magnetohydrodynamic (MHD) generation is employed for topping cycle power extraction. MHD rejected heat is transported via compact heat exchanger to a conventional Brayton gas turbine bottoming cycle. High bottoming cycle mass flow rates are required to remove the waste heat because of low heat capacities for the bottoming cycle gas. High mass flow is also necessary to balance the high Uranium Tetrafluoride (UF{sub 4}) mass flow rate in the topping cycle. Heat exchanger design is critical due to the high temperatures and corrosive influence of fluoride compounds and fission products existing in VCR/MHD exhaust. Working fluid compositions for the topping cycle include variations of Uranium Tetrafluoride, Helium and various electrical conductivity seeds for the MHD. Bottoming cycle working fluid compositions include variations of Helium and Xenon. Some thought has been given to include liquid metal vapor in the bottoming cycle for a Cheng or evaporative cooled design enhancement. The NASA Glenn Lewis Research Center code Chemical Equilibrium with Applications (CEA) is utilized for evaluating chemical species existing in the gas stream. Work being conducted demonstrates the compact heat exchanger design, utilization of the CEA code, and assessment of different topping and bottoming working fluid compositions. (authors)

Bays, Samuel E.; Anghaie, Samim; Smith, Blair; Knight, Travis [Innovative Space Power and Propulsion Institute, University of Florida, 202 Nuclear Science Building, Gainesville, FL 32611 (United States)

2004-07-01T23:59:59.000Z

422

Guidance for Deployment of Mobile Technologies for Nuclear Power...  

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

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...

423

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Topic Title: WEB RESOURCE: Virtual Nuclear Tourist! Nuclear Plants Around the ... Nuclear Power Plants Around the World.22 January 2006.

424

The Decline and Death of Nuclear Power  

E-Print Network (OSTI)

9. The Economist (2012). Nuclear power: The 30-year itch.Germany and France, the anti-nuclear movement has taken suchtime since the Cold War, nuclear power plants are being

Melville, Jonathan

2013-01-01T23:59:59.000Z

425

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

SciTech Connect

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

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

1996-02-01T23:59:59.000Z

426

Three Human Factors Engineering Training Courses for Utilities Involved in New Nuclear Power Plant Designs, Construction and Operati on  

Science Conference Proceedings (OSTI)

This product provides an assembled package of three Electric Power Research Institute (EPRI) developed human factors engineering (HFE) training courses to support a range of needs. The training materials for these courses were developed for utility personnel involved in new nuclear power plant (NPP) design, construction and operation. The training material is also useful for vendors and other stakeholders. The primary focus of the HFE training courses is the main control room and its human-system interfa...

2012-03-23T23:59:59.000Z

427

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

Agency regulating commercial nuclear power plants and other uses of nuclear materials, 0, 720, Lynne Robinson, 6/25/2007 9:29 AM by Lynne Robinson.

428

Nuclear power high technology colloquium: proceedings  

Science Conference Proceedings (OSTI)

Reports presenting information on technology advancements in the nuclear industry and nuclear power plant functions have been abstracted and are available on the energy data base.

Not Available

1984-12-10T23:59:59.000Z

429

Project Management Guidance when Upgrading Steam Turbines at Nuclear and Fossil Power Plants  

Science Conference Proceedings (OSTI)

Many power producers upgrade steam turbines to gain megawatts (MW) instead of installing new capacity for a variety of reasons. The engineering challenges encounteredwhen managing procurement and adequately analyzing plant support systems affected by this upgradeare becoming more pronounced.

2007-01-15T23:59:59.000Z

430

DESIGN STUDY OF A NUCLEAR POWER PLANT FOR 100-KW ELECTRIC AND 400-KW HEAT CAPACITY  

SciTech Connect

A conceptional design study was made of a lowpower ''package'' reactor plant for the production of 100 kw of electrical power and 400 kw of heat at remote Arctic installations. The power plant steam generator is proposed to be an unmanned, heterogeneous, boilingtype reactor capable of continuous operation for extended periods. The design is based on data derived from experiments with boiling-type reactors conducted by Argorne at the Reactor Testing Station, Arco, Idaho.

Treshow, M.; Snider, A.R.; Shaftman, D.H.

1955-05-01T23:59:59.000Z

431

Groundwater and Soil Remediation Guidelines for Nuclear Power Plants: Public Edition  

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.

2011-07-08T23:59:59.000Z

432

Review of nuclear power plant safety cable aging studies with recommendations for improved approaches and for future work.  

Science Conference Proceedings (OSTI)

Many U. S. nuclear power plants are approaching 40 years of age and there is a desire to extend their life for up to 100 total years. Safety-related cables were originally qualified for nuclear power plant applications based on IEEE Standards that were published in 1974. The qualifications involved procedures to simulate 40 years of life under ambient power plant aging conditions followed by simulated loss of coolant accident (LOCA). Over the past 35 years or so, substantial efforts were devoted to determining whether the aging assumptions allowed by the original IEEE Standards could be improved upon. These studies led to better accelerated aging methods so that more confident 40-year lifetime predictions became available. Since there is now a desire to potentially extend the life of nuclear power plants way beyond the original 40 year life, there is an interest in reviewing and critiquing the current state-of-the-art in simulating cable aging. These are two of the goals of this report where the discussion is concentrated on the progress made over the past 15 years or so and highlights the most thorough and careful published studies. An additional goal of the report is to suggest work that might prove helpful in answering some of the questions and dealing with some of the issues that still remain with respect to simulating the aging and predicting the lifetimes of safety-related cable materials.

Gillen, Kenneth Todd; Bernstein, Robert

2010-11-01T23:59:59.000Z

433

Nuclear power. Volume 2: nuclear power project management  

Science Conference Proceedings (OSTI)

The following topics are discussed: review of nuclear power plants; licensing procedures; safety analysis; project professional services; quality assurance and project organization; construction, scheduling and operation; construction, scheduling and operation; nuclear fuel handling and fuel management; and plant cost management. 116 references, 115 figures, 33 tables.

Not Available

1980-01-01T23:59:59.000Z

434

Spent Fuel Pool Cooling and Cleanup During Decommissioning: Experience at Trojan Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Operation of original in-plant spent fuel pool facilities at shutdown power plants is expensive compared to available alternatives and can interfere with the decommissioning process. This report describes the approach taken in the Trojan Decommissioning Project to establish independent cooling and cleanup services for the fuel pool until the spent fuel is placed in dry storage.

1999-03-15T23:59:59.000Z

435

Project Ranking Method for Nuclear Power Plants: Prioritizing Proposed Capital and O&M Projects  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, it becomes ever more important to invest limited budgets only in projects that increase or protect a plant's value and profitability over its remaining operating term. This report describes a robust method that plants can customize to evaluate, rank, and select their operating and maintenance (O&M) and capital projects.

2003-05-12T23:59:59.000Z

436

DYNAMIC SIMULATION OF MULTI-PASS PRESSURIZED WATER NUCLEAR POWER PLANTS BY ANALOG COMPUTER TECHNIQUES  

SciTech Connect

A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)

Brondel, J.O.

1961-06-01T23:59:59.000Z

437

Use of Modern Digital, Information, and Communication Technologies for Nuclear Power Plant Maintenance Activities  

Science Conference Proceedings (OSTI)

The use of modern digital, information, and communications technology (DT, IT, and CT)) capabilities provides tremendous opportunities for developing beneficial applications for improving plant and human performance in operating plants, including opportunities for replacing aging and obsolete functionality and for providing new support applications. These capabilities can also provide improved functionality that will support the high expectations for the performance of new plants. The Electric Power Rese...

2011-06-21T23:59:59.000Z

438

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

439

"1. Chalk Point LLC","Coal","Mirant Chalk Point LLC",2347 "2. Calvert Cliffs Nuclear Power Plant","Nuclear","Calvert Cliffs Nuclear PP Inc",1705  

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

Maryland" Maryland" "1. Chalk Point LLC","Coal","Mirant Chalk Point LLC",2347 "2. Calvert Cliffs Nuclear Power Plant","Nuclear","Calvert Cliffs Nuclear PP Inc",1705 "3. Morgantown Generating Plant","Coal","Mirant Mid-Atlantic LLC",1477 "4. Brandon Shores","Coal","Constellation Power Source Gen",1273 "5. Herbert A Wagner","Coal","Constellation Power Source Gen",976 "6. Dickerson","Coal","Mirant Mid-Atlantic LLC",844 "7. NAEA Rock Springs LLC","Gas","NAEA Rock Springs LLC",652 "8. Conowingo","Hydroelectric","Exelon Power",572

440

Threatened and endangered species evaluation for 75 licensed commercial nuclear power generating plants  

SciTech Connect

The Endangered Species Act (ESA) of 1973, as amended, and related implementing regulations of the jurisdictional federal agencies, the U.S. Departments of Commerce and Interior, at 50 CFR Part 17. 1, et seq., require that federal agencies ensure that any action authorized, funded, or carried out under their jurisdiction is not likely to jeopardize the continued existence of any threatened or endangered species or result in the destruction or adverse modification of critical habitats for such species. The issuance and maintenance of a federal license, such as a construction permit or operating license issued by the U.S. Nuclear Regulatory Commission (NRC) for a commercial nuclear power generating facility is a federal action under the jurisdiction of a federal agency, and is therefore subject to the provisions of the ESA. The U.S. Department of the Interior (through the Fish and Wildlife Service), and the U.S. Department of Commerce, share responsibility for administration of the ESA. The National Marine Fisheries Service (NMFS) deals with species that inhabit marine environments and anadromous fish, while the U.S. Fish and Wildlife Service (USFWS) is responsible for terrestrial and freshwater species and migratory birds. A species (or other distinct taxonomic unit such as subspecies, variety, and for vertebrates, distinct population units) may be classified for protection as `endangered` when it is in danger of extinction within the foreseeable future throughout all or a significant portion of its range. A `threatened` classification is provided to those animals and plants likely to become endangered within the foreseeable future throughout all or a significant portion of their ranges. As of February 1997, there were about 1067 species listed under the ESA in the United States. Additionally there were approximately 125 species currently proposed for listing as threatened or endangered, and another 183 species considered to be candidates for formal listing proposals.

Sackschewsky, M.R.

1997-03-01T23:59:59.000Z

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

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 manager’s concern is that cables may fail, causing ...

2013-06-03T23:59:59.000Z

442

Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant  

DOE Green Energy (OSTI)

The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct containment heating (DCH) phenomena on the containment load. High-temperature, chemically reactive melt (thermite) is ejected by high-pressure steam into a scale model of a reactor cavity. Debris is entrained by the steam blowdown into a containment model where specific phenomena, such as the effect of subcompartment structures, prototypic air/steam/hydrogen atmospheres, and hydrogen generation and combustion, can be studied. Four Integral Effects Tests (IETs) have been performed with scale models of the Surry NPP to investigate DCH phenomena. The 1/61{sup th} scale Integral Effects Tests (IET-9, IET-10, and IET-11) were conducted in CTRF, which is a 1/6{sup th} scale model of the Surry reactor containment building (RCB). The 1/10{sup th} scale IET test (IET-12) was performed in the Surtsey vessel, which had been configured as a 1/10{sup th} scale Surry RCB. Scale models were constructed in each of the facilities of the Surry structures, including the reactor pressure vessel, reactor support skirt, control rod drive missile shield, biological shield wall, cavity, instrument tunnel, residual heat removal platform and heat exchangers, seal table room and seal table, operating deck, and crane wall. This report describes these experiments and gives the results.

Blanchat, T.K.; Allen, M.D.; Pilch, M.M. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

1994-06-01T23:59:59.000Z

443

Health effects models for nuclear power plant accident consequence analysis: Low LET radiation  

SciTech Connect

This report describes dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes -- are considered. In addition, models are included for assessing the risks of several nonlethal early and continuing effects -- including prodromal vomiting and diarrhea, hypothyroidism and radiation thyroiditis, skin burns, reproductive effects, and pregnancy losses. Linear and linear-quadratic models are recommended for estimating cancer risks. Parameters are given for analyzing the risks of seven types of cancer in adults -- leukemia, bone, lung, breast, gastrointestinal, thyroid, and other.'' The category, other'' cancers, is intended to reflect the combined risks of multiple myeloma, lymphoma, and cancers of the bladder, kidney, brain, ovary, uterus and cervix. Models of childhood cancers due to in utero exposure are also developed. For most cancers, both incidence and mortality are addressed. The models of cancer risk are derived largely from information summarized in BEIR III -- with some adjustment to reflect more recent studies. 64 refs., 18 figs., 46 tabs.

Evans, J.S. (Harvard Univ., Boston, MA (USA). School of Public Health)

1990-01-01T23:59:59.000Z

444

Detection of $^{133}$Xe from the Fukushima nuclear power plant in the upper troposphere above Germany  

E-Print Network (OSTI)

After the accident in the Japanese Fukushima Dai-ichi nuclear power plant in March 2011 large amounts of radioactivity were released and distributed in the atmosphere. Among them were also radioactive noble gas isotopes which can be used as tracers to probe global atmospheric circulation models. This work presents unique measurements of the radionuclide $^{133}$Xe from Fukushima in the upper troposphere above Germany. The measurements involve air sampling in a research jet aircraft followed by chromatographic xenon extraction and ultra-low background gas counting with miniaturized proportional counters. With this technique a detection limit of the order of 100 $^{133}$Xe atoms in liter-scale air samples (corresponding to about 100 mBq/m$^3$) is achievable. Our results proof that the $^{133}$Xe-rich ground level air layer from Fukushima was lifted up to the tropopause and distributed hemispherically. Moreover, comparisons with ground level air measurements indicate that the arrival of the radioactive plume in Germany in high altitude is several days earlier than on ground.

Hardy Simgen; Frank Arnold; Heinfried Aufmhoff; Robert Baumann; Florian Kaether; Sebastian Lindemann; Ludwig Rauch; Hans Schlager; Clemens Schlosser; Ulrich Schumann

2013-09-06T23:59:59.000Z

445

EIS No. 20100312 EIS Comanche Peak Nuclear Power Plant Units 3 and 4  

SciTech Connect

In accordance with Section 309(a) of the Clean Air Act, EPA is required to make its comments on EISs issued by other Federal agencies public. Historically, EPA has met this mandate by publishing weekly notices of availability of EPA comments, which includes a brief summary of EPA's comment letters, in the Federal Register. Since February 2008, EPA has been including its comment letters on EISs on its Web site at: http://www.epa.gov/compliance/nepa/eisdata.html. Including the entire EIS comment letters on the Web site satisfies the Section 309(a) requirement to make EPA's comments on EISs available to the public. Accordingly, on March 31, 2010, EPA discontinued the publication of the notice of availability of EPA comments in the Federal Register. EIS No. 20100312, Draft EIS, NRC, TX, Comanche Peak Nuclear Power Plant Units 3 and 4, Application for Combined Licenses (COLs) for Construction Permits and Operating Licenses, (NUREG-1943), Hood and Somervell Counties, TX, Comment Period Ends: 10/26/2010.

Bjornstad, David J [ORNL

2010-08-01T23:59:59.000Z

446

Nuclear power has a significant role in the European power ...  

U.S. Energy Information Administration (EIA)

Sales, revenue and prices, power plants, fuel use, stocks, generation, trade, demand & emissions. ... Because nuclear power does not emit greenhouse gases, ...

447

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

May 25, 2007 ... The United States Nuclear Power Industry is “reawakening”. ... for a New Generation of Power Plants", Materials Technology@TMS, May 2007.

448

IMPROVEMENTS IN POWER PLANT  

SciTech Connect

A power plant for nuclear reactors is designed for improved cycle efficiency. In addition to the usual heat exchanger for heat transfer from gaseous reactor coolant to water for vaporization, a second heat exchanger is provided between the first heat exchanger and a point betwveen the intermediate- pressure and low-pressure turbine stages. In this way, interstage reheating of the steam is obtained without passage of the steam back to the first heat exchanger. (D.L.C.) Research Reactors

Peters, M.C.

1961-10-11T23:59:59.000Z

449

NEUTRONIC REACTOR POWER PLANT  

DOE Patents (OSTI)

This patent relates to a nuclear reactor power plant incorporating an air-cooled, beryllium oxide-moderated, pebble bed reactor. According to the invention means are provided for circulating a flow of air through tubes in the reactor to a turbine and for directing a sidestream of the circu1ating air through the pebble bed to remove fission products therefrom as well as assist in cooling the reactor. (AEC)

Metcalf, H.E.

1962-12-25T23:59:59.000Z

450

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

SciTech Connect

OAK-B135 This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

Camillo A. DiNunzio Framatome ANP DE& S; Dr. Abhinav Gupta Assistant Professor NCSU; Dr. Michael Golay Professor MIT Dr. Vincent Luk Sandia National Laboratories; Rich Turk Westinghouse Electric Company Nuclear Systems; Charles Morrow, Sandia National Laboratories; Geum-Taek Jin, Korea Power Engineering Company Inc.

2002-11-30T23:59:59.000Z

451

Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants  

Science Conference Proceedings (OSTI)

Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Woo, H.H.; Lu, S.C.

1981-09-15T23:59:59.000Z

452

Competitive economics of nuclear power  

Science Conference Proceedings (OSTI)

Some 12 components of a valid study of the competitive economics of a newly ordered nuclear power plant are identified and explicated. These are then used to adjust the original cost projections of four authoritative studies of nuclear and coal power economics.

Hellman, R.

1981-03-02T23:59:59.000Z

453

Quantitative Assessment of Human-Induced Loss of Offsite Power (HI-LOOP) Event Frequencies at U.S. Commercial Nuclear Power Plants (NPP)  

Science Conference Proceedings (OSTI)

This report provides a framework for developing improved methods and models for quantifying the frequencies of human-induced loss of offsite power (HI-LOOP) initiators at U.S. commercial nuclear power plants (NPPs). Leveraging these methods and models should enhance the NPP probabilistic risk assessment model completeness and would be useful for the NPP on-line risk models. The primary focus of the report is on investigating the impact of human activities on the frequencies of switchyard-centered ...

2013-04-04T23:59:59.000Z

454

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

SciTech Connect

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

Naus, Dan J [ORNL

2011-01-01T23:59:59.000Z

455

Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant  

SciTech Connect

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant.

Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D. (Pacific Northwest Lab., Richland, WA (United States))

1992-10-01T23:59:59.000Z

456

Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant  

Science Conference Proceedings (OSTI)

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant.

Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1993-12-01T23:59:59.000Z

457

POWER SUPPLY EXPANSION AND THE NUCLEAR OPTION  

E-Print Network (OSTI)

the fact that eventually thermal plant is duplicated by CO -2 free nuclear power. Similarly), Autoproducing Power Plants in Poland: Technological Data, Warsaw 1993b. ______, Public Thermal Power Plants% of all generating capacity, 5.6 GW, is combined heat and power (CHP), or cogeneration, plant, which also

458

Recommended Approaches and Design Criteria for Application of Field Programmable Gate Arrays in Nuclear Power Plant Instrumentation and Control Systems  

Science Conference Proceedings (OSTI)

Field-programmable gate arrays (FPGAs) are gaining increased attention worldwide for application in nuclear power plant (NPP) instrumentation and control (IC) systems, particularly for safety applications. The use of FPGAs might reduce complexity and the associated burden of gaining regulatory approval and provide better protection against obsolescence compared to conventional microprocessor-based systems. This report provides guidelines and design criteria for application of FPGAs in NPP IC systems, add...

2011-06-16T23:59:59.000Z

459

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

Science Conference Proceedings (OSTI)

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

2011-12-23T23:59:59.000Z

460

Drum Screen Filtration of Cooling Water in Fossil-Fired and Nuclear Power Plants: The Electricite de France (EDF) Experience  

Science Conference Proceedings (OSTI)

This document presents a summary of the lessons learned from operating the drum screen filtration systems used for the last three decades in Èlectricité de France’s (EDF’s) nuclear and fossil-fired power plants, both in terms of the technological aspects of filtration and with regard to the prevention of clogging risks and the prevention of damage to the living organisms impinged on the drum screens and entrained into the cooling ...

2012-11-21T23:59:59.000Z

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