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

Peach Bottom and Vermont Yankee Nuclear Power Plants  

SciTech Connect

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

2

The Debate over Re-Licensing the Vermont Yankee Nuclear Power Plant  

Science Journals Connector (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?

Richard Watts; Paul Hines; Jonathan Dowds

2010-01-01T23:59:59.000Z

3

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

SciTech Connect

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

4

The role of media actors in reframing the media discourse in the decision to reject relicensing the Vermont Yankee nuclear power plant  

Science Journals Connector (OSTI)

This paper examines 8 years of news media discourse on the operation of the Vermont Yankee nuclear power plant leading up to a 2010 vote by Vermont legislators to reject relicensing the facility. Nuclear ... purv...

Richard Watts; Jonathan Maddison

2012-06-01T23:59:59.000Z

5

Vermont Nuclear Profile - Vermont Yankee  

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

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

6

Confirmatory Survey Results for the Emergency Operations Facility (EOF) at the Connecticut Yankee Haddam Neck Plant, Haddam, Connecticut  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) requested that the Oak Ridge Institute for Science and Education (ORISE) perform a confirmatory survey on the Emergency Operations Facility (EOF) at the Connecticut Yankee Haddam Neck Plant (HNP) in Haddam, Connecticut

W. C. Adams

2007-07-03T23:59:59.000Z

7

"1. Vermont Yankee","Nuclear","Entergy Nuclear Vermont Yankee",620  

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

Vermont" Vermont" "1. Vermont Yankee","Nuclear","Entergy Nuclear Vermont Yankee",620 "2. J C McNeil","Other Renewables","City of Burlington-Electric",52 "3. Bellows Falls","Hydroelectric","TransCanada Hydro Northeast Inc.,",48 "4. Wilder","Hydroelectric","TransCanada Hydro Northeast Inc.,",41 "5. Harriman","Hydroelectric","TransCanada Hydro Northeast Inc.,",41 "6. Berlin 5","Petroleum","Green Mountain Power Corp",35 "7. Vernon","Hydroelectric","TransCanada Hydro Northeast Inc.,",34 "8. Sheldon Springs Hydroelectric","Hydroelectric","Sheldon Vermont Hydro Co., Inc.",24

8

Another Nuclear Plant To Close  

Science Journals Connector (OSTI)

The Vermont Yankee Nuclear Power Station in Vernon, Vt., will permanently shut down in 2014, according to plant owner Entergy. ... In the Vermont Yankee case, Entergy’s announcement ends a long-simmering dispute between the utility and state officials and residents over the continued operation of the 620-MW plant. ... The Vermont Yankee plant design nearly mirrors that of the Fukushima reactor facility. ...

JEFF JOHNSON

2013-09-02T23:59:59.000Z

9

AEC's New Environmental Rules for Nuclear Plant May Open New Debate, Extend Delays, Raise Plant Costs  

Science Journals Connector (OSTI)

...such times, and the Vermont Yankee plant would take turn...private power companies, Vermont Central and Green Mountain...majority in-vestors in the Yankee Nuclear Power Company...Among these is the Vermont Yankee plant at Vernon (see...

Robert Gillette

1971-09-17T23:59:59.000Z

10

Reload design process at Yankee Atomic Electric Company  

SciTech Connect

Yankee Atomic Electric Company (YAEC) performs reload design and licensing for their nuclear power plants: Yankee Rowe, Maine Yankee, and Vermont Yankee. Significant savings in labor and computer costs have been achieved in the reload design process by the use of the SIMULATE nodal code using the CASMO assembly burnup code or LEOPARD pin cell burnup code inputs to replace the PDQ diffusion theory code in many required calculations for the Yankee Rowe and Maine Yankee pressurized water reactors (PWRs). An efficient process has evolved for the design of reloads for the Vermont Yankee boiling water reactor (BWR). Due to the major differences in the core design of the three plants, different reload design processes have evolved for each plant.

Weader, R.J.

1986-01-01T23:59:59.000Z

11

Experience with gadolinium at yankee  

SciTech Connect

The Vermont Yankee nuclear power station, a boiling water reactor, has been operating with gadolinium in the fuel bundles since 1973. The gadolinium has ranged from 2.0 to 4.0 wt% in 7 x 7, 8 x 8, and retrofit 8 x 8 bundle designs. When Yankee Atomic Electric Company initiated its program in 1978 to perform reload licensing analysis, these bundles and the core designs had to be modeled accurately. The basic calculational model consists of the cross section generation code, CASMO, and the three-dimensional nodal code, SIMULATE. The gadolinium cross sections for use in CASMO were generated using MICBURN to model each gadolinium pin individually. This combination of codes has been used to calculate 11 cycles of operation at Vermont Yankee. The model has been depleted each cycle using explicit plant conditions at equilibrium xenon. At various state points, the eigenvalues, hot and cold, were calculated and tabulated for each cycle. Comparisons were made between plant-measured and SIMULATE-calculated TIP values and between process computer and SIMULATE thermal margins. The model is also used to predict future cycle operating conditions and thermal margins based on past comparisons.

Cacciapouti, R.J.; Sironen, M.A.; Kaptiz, D.M.; Potter, R.C.

1985-11-01T23:59:59.000Z

12

Vermont: A Power Deficit Raises Pressure for New Plants  

Science Journals Connector (OSTI)

...1112) seem to have pushed the Vermont Yankee nuclear plant further into legal...issue in the state. Even if the Vermont Yankee plant went on line schedule and...increasing consumption. The new Vermont Yankee nuclear plant on the Connecticut...

John Walsh

1971-09-17T23:59:59.000Z

13

,"Plant","Primary Energy Source","Operating Company","Net Summer...  

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

Vermont" ,"Plant","Primary Energy Source","Operating Company","Net Summer Capacity (MW)" 1,"Vermont Yankee","Nuclear","Entergy Nuclear Vermont Yankee",604.3 2,"Kingdom Community...

14

Yankee atomic experience with coastdown. Report YAEC-1270  

SciTech Connect

This report summarizes Yankee Atomic's operating experience with 19 coastdowns in three different nuclear power plants. The observed effects of coastdown on plant capacity factor, efficiency, maneuverability, and fuel integrity are demonstrated. Calculations of resource requirements and fuel cycle economics for equilibrium cycles show typical savings of 3 to 5% for cycles using coastdown compared to those which produce the same energy without coastdown.

Quan, B.L.; Malone, J.P.; Pilat, E.E.

1981-05-01T23:59:59.000Z

15

BWR (boiling-water reactor) radiation control: In-plant demonstration at Vermont Yankee: Final report  

SciTech Connect

Results of the RP1934 program, which was established by EPRI in 1981 to demonstrate the adequacy of BRAC program (RP819) principles for BWR radiation control at Vermont Yankee, are presented. Evaluations were performed of the effectiveness of optimization of purification system performance, control of feedwater dissolved oxygen concentrations, minimization of corrosion product and ionic transport, and improved startup, shutdown, and layup practices. The impact on shutdown radiation levels of these corrective actions was assessed based on extensive primary system radiation survey and component gamma scan data. Implementation of the BRAC recommendations was found to be insufficient to reduce the rate of activity buildup on out-of-core surfaces at Vermont Yankee, and additional corrective actions were found necessary. Specifically, replacement of cobalt-bearing materials in the control rod drive pins and rollers and feedwater regulating valves was pursued as was installation of electropolished 316 stainless steel during a recirculation piping replacement program. Aggressive programs to further reduce copper concentrations in the reactor water by improving condensate demineralizer efficiency and to minimize organic ingress to the power cycle by reducing organic concentrations in recycled radwaste also were undertaken. Evaluations of the impact on activity buildup of several pretreatment processes including prefilming in moist air, preexposure to high temperature water containing zinc, and electropolishing also were performed in a test loop installed in the reactor water cleanup system. A significant beneficial impact of electropolishing was shown to be present for periods up to 6000 hours.

Palino, G.F.; Hobart, R.L.; Sawochka, S.G.

1987-10-01T23:59:59.000Z

16

Technical-evaluation report on the adequacy of station electric-distribution-system voltages for the Vermont Yankee Nuclear Power Station. Document No. 50-271  

SciTech Connect

This report documents the technical evaluation of the adequacy of the station electric distribution system voltages for the Vermont Yankee Nuclear Power Station. The evaluation is to determine if the onsite distribution system, in conjunction with the offsite power sources, has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. The evaluation finds that the voltage analyses submitted demonstrate that adequate voltage will be supplied to the Class 1E equipment under worst case conditions.

Selan, J.C.

1982-09-03T23:59:59.000Z

17

The Vermont Yankee Nuclear Power Station will use a single-unit boilingwater  

E-Print Network (OSTI)

reactor with an initial power rating of 1593 thermal megawatts (MWt) to provide a net power output of 513 electrical megawatts (Me). The reactor will be cooled by a once-through flow of water pumped from and returned to Vernon Pond, an existing impoundment of the Connecticut River (built to serve the Vernon Hydroelectric Station) and also by means of mechanical draft cooling towers. 3. Sumnary of environmental impact including beneficial and adverse effects follows: a. Cooling water heated to about 20*F above inlet temperature will be discharged to Vernon Pond at a rate of 840 cfs when the plant operates on a total open-cycle basis. Mechanical-draft cooling towers are provided to protect Vernon Pond during low flow and critical temperature periods in the Connecticut River. b. About 150 acres of Vernon Pond in the vicinity of the station may be subjected to some thermal and biological stress from discharge of the

Vermont Yankee

18

Vermont Yankee simulator qualification: large-break LOCA  

SciTech Connect

Yankee Atomic Electric Company (YAEC) has developed simulator benchmark capabilities for the Seabrook, Maine Yankee, and Vermont Yankee Nuclear Power Station (VYNPS) simulators. The goal is to establish that each simulator has a satisfactory real-time response for different scenarios that will enhance operator training. Vermont Yankee purchased a full-scope plane simulator for the VYNPS, a four-unit boiling water reactor with a Mark-I containment. The following seven benchmark cases were selected by YAEC and VYNPC to supplement the Simulator Acceptance Test Program: (1) control rod swap; (2) partial reactor scram; (3) recirculation pump trip; (4) main steam isolation valve (MSIV) closure without scram, (5) main steamline break, (6) small-break loss-of-coolant accident (LOCA), and (7) large-break LOCA. Five simulator benchmark sessions have been completed. Each session identified simulator capabilities and limitations that needed correction. This paper discusses results from the latest large-break LOCA case.

Loomis, J.N.; Fernandez, R.T.

1987-01-01T23:59:59.000Z

19

The Initial Environmental Assessments for the Nuclear Waste Repository under Section 112 of the Nuclear Waste Policy Act  

E-Print Network (OSTI)

Pollak. J ) Se.e also Vermont Yankee Nuclear Power Corp. %,.requirement). 53. See Vermont Yankee Nuclear Power Corp. v.8th Cir. 1977). 77. Vermont Yankee Nuclear Power Corp. v.

Montange, Charles H.

1985-01-01T23:59:59.000Z

20

THE NUCLEAR ENERGY REVOLUTION—1966  

Science Journals Connector (OSTI)

...Edison Niagara Mohawk Connecticut Yankee Commonwealth Edison Boston Edison...E Northern States Power Co. TVA Vermont Yankee Duke Power Company Philadelphia...experience with such power plants as the Yankee pressurized-water reactor (175...

Alvin M. Weinberg; Gale Young

1967-01-01T23:59:59.000Z

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

Nuclear Regulatory Commission Proceedings: A Guide for Intervenors  

E-Print Network (OSTI)

U.S. 396 (1961); Vermont Yankee, 435 U.S. 519; Morningsidein two 2. See, e.g. , Vermont Yankee Nuclear Power Corp. v.8th Cir. 1971); and Vermont Yankee Nuclear Power Corp. v.

Hansell, Dean

1982-01-01T23:59:59.000Z

22

NUCLEAR PLANT AND CONTROL  

E-Print Network (OSTI)

for the digital protection systems of a nuclear power plant. When spec- ifying requirements for software and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital, the missiles, and the digital protection systems embed- ded in nuclear power plants. Obviously, safety

23

Quarterly Nuclear Deployment Scorecard- January 2015  

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

Includes news updates on nuclear power deployment including: vermont yankee closure, possible vogtle construction delay.

24

CASMO-3/SIMULATE-3 benchmarking against Vermont Yankee  

SciTech Connect

The cross-section generation code CASMO-3 and the advanced nodal code SIMULATE-3 are used to model Vermont Yankee (VY) cycles 9 through 13. Vermont Yankee is a small, high-power density boiling water reactor (BWR)-3 reactor. Cycles 9 through 13 were chosen for benchmarking because they have high-enrichment cores and use gamma-sensing traversing in-core probes (TIPs). To judge the merit of the new CASMO-3/SIMULATE-3 model, the results are compared to the old CASMO-2/SIMULATE-2 model. The figures of merit are consistent hot and cold eigenvalues near 1.0 and accurate reproduction of the plant TIP readings.

Hubbard, B.Y.; Morin, D.J.; Pappas, J.; Potter, R.C.; Woehlke, R.A. (Yankee Atomic Electric Co., Bolton, MA (USA))

1989-11-01T23:59:59.000Z

25

VERMONT YANKEE NUCLEAR POWER CORPORATION  

E-Print Network (OSTI)

interlocks. One aspect of the proposed change involved the frequency of surveillance testing contained in TS 4.12.A. VY intended to increase this specific surveillance interval based on a generic proposal under review by NRC's Technical Specifications Task Force (TSTF). In discussions with NRC staff it now appears that approval of the TSTF item is delayed and may require additional actions. Consequently, due to the forthcoming refueling outage, VY has decided to withdraw this one specific change from Proposed Change No. 239 (PC-239) and retain the current 7-day surveillance interval. Therefore, VY is hereby amending PC-239 by deleting the proposed increase in surveillance interval in TS 4.12.A that would have changed the test frequency to every 31 days. In Attachment 1 of Reference (a) this is identified as Change No. 5, which is now being deleted in its entirety. This is the only change to PC-239. Thus, the current surveillance frequency of TS 4.12.A will be retained. All other provisions of the Reference (a) amendment request are unchanged and remain as proposed. Withdrawal of this one aspect of the amendment request does not otherwise alter the Safety

Vermont Yankee; Michael A. Balduzzi

2001-01-01T23:59:59.000Z

26

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...

27

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...

28

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...

29

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...

30

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...

31

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...

32

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...

33

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...

34

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...

35

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...

36

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...

37

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...

38

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...

39

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...

40

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...

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

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...

42

Maryland 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...

43

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...

44

Nuclear Freeze Candidates Claim Mandate  

Science Journals Connector (OSTI)

...to their narrow wins. Environmentalists also assert that in Vermont and Maine, where acid rain has become a matter of concern...by a 55 to 45 percent vote a proposal to shut down the Maine Yankee plant in Wiscasset and ban construction of nuclear plants in...

JOHN WALSH

1982-11-19T23:59:59.000Z

45

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

SciTech Connect

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

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

1990-01-01T23:59:59.000Z

46

Next Generation Nuclear Plant Phenomena  

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

5 ORNLTM-2007147, Vol. 5 Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs Office of Nuclear Regulatory Research...

47

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...

48

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...

49

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...

50

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...

51

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...

52

Safety at a glance; Upgrading the displays in a nuclear plant control room  

SciTech Connect

As part of an effort to upgrade aging plants, computer-integrated data-acquisition systems are beginning to penetrate the nation's nuclear power control rooms. The impetus is also partly due to the legacy of Three Mile Island, where control room operators, confused about which stream pressure line reading was correct, unfortunately believed the wrong one. This paper reports on the Vermont Yankee nuclear generating facility near Brattleboro, Vt., where the new SPDS requirement provided the opportunity to reassess the existing automated data-acquisition system, an installation that came as original equipment when the plant opened in 1972. The system, a Honeywell industrial computer repackaged by General Electric (which built the reactor), has become obsolete.

Baer, T.

1992-01-01T23:59:59.000Z

53

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

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

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

54

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

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

55

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

56

Vermont Yankee Nucl Pwr Corp | Open Energy Information  

Open Energy Info (EERE)

Yankee Nucl Pwr Corp Jump to: navigation, search Name: Vermont Yankee Nucl Pwr Corp Place: Vermont References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form 861...

57

Issues for New Nuclear Plants  

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

to Explore * Idaho's energy picture * Nuclear power in the U.S. * Potential for a nuclear power plant in Idaho 0 5 10 15 20 25 1960 1970 1980 1990 2000 Million Megawatt-Hours Total...

58

Owners of nuclear power plants  

SciTech Connect

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

59

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"

60

Nuclear Energy: Do States Lack Power to Block Proliferation of Reactors?  

Science Journals Connector (OSTI)

...forms of power, not just nuclear. Vermont, meanwhile, has successfully...acquiescence. A few years ago the Vermont Yankee Nuclear Power Corporation signed...Murphy and La Pierre suggest that Vermont Yan-kee took this action to facilitate...

PHILIP M. BOFFEY

1976-01-30T23:59:59.000Z

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

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...

62

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...

63

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...

64

Nuclear Power Plants  

Science Journals Connector (OSTI)

A third issue related to the production, use and transportation of nuclear materials is the safety issue associated with ... an act of war or an act of terrorism. While the containment buildings of typical nuclear

Efstathios E. (Stathis) Michaelides

2012-01-01T23:59:59.000Z

65

Thermal spray coatings on Yankee dryers  

SciTech Connect

Several failure investigations and recent research on thermal spray coatings on Yankee dryer surfaces show at least three modes of environmentally induced degradation. Corrosion may occur with the ingress of certain chemicals into coating pores. Erosion or corrosion is manifested by streaks at local sites of high doctor blade loading. Erosion and cracking occur due to coating parameters, thermal stress, and differential expansion. While most of the results described in this paper are from investigations of molybdenum, stainless steel coatings also are discussed.

Bowers, D.F. (Packer Engineering, Inc., Naperville, IL (United States))

1994-08-01T23:59:59.000Z

66

Seismic failure and cask drop analyses of the spent fuel pools at two representative nuclear power plants  

SciTech Connect

This report discusses work done in support of the resolution of Generic Issue-82, ''Beyond Design Basis Accidents in Spent Fuel Pools''. Specifically the probability of spent fuel pool failure due to earthquakes was determined for the pools at the Vermont Yankee Nuclear Power Station (BWR) and the H. B. Robinson S.E. Plant, Unit 2 (PWR). The dominant failure mode for each pool was gross structural failure caused by seismic motion resulting in the loss of pool liner integrity. The resulting sudden loss of water was then assumed to lead to a self-propagating cladding failure and fission product inventory release from the spent fuel elements in the pool. The mean annual frequency of failure due to this failure mode was found to be 6.7E-06 at Vermont Yankee and 1.8E-06 at H. B. Robinson. Other earthquake induced failure modes studied but found to be less important were loss of pool cooling and make-up capability, fuel rack damage and loss of liner integrity due to a cask drop accident. 61 refs., 47 figs., 14 tabs.

Prassinos, P.G.; Kimura, C.Y.; McCallen, D.B.; Murray, R.C.; Ravindra, M.K.; Campbell, R.D.; Hashimoto, P.S.; Nafday, A.M.; Tong, W.H.

1989-01-01T23:59:59.000Z

67

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

68

Advanced nuclear plant control complex  

DOE Patents (OSTI)

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

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

1993-01-01T23:59:59.000Z

69

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

70

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

71

The Politically Correct Nuclear Energy Plant  

E-Print Network (OSTI)

The Politically Correct Nuclear Energy Plant Andrew C. Kadak Massachusetts Institute of Technology - Small is Beautiful · Nuclear Energy - But Getting Better #12;Politically Correct ! · Natural Safety is a bad idea. · There is no new nuclear energy plant that is competitive at this time. · De-regulation did

72

A comparison of factors impacting on radiation buildup at the Vermont Yankee and Monticello BWRs (boiling-water reactors): Interim report  

SciTech Connect

Design and operating features of the Monticello and Vermont Yankee BWRs were compared in an attempt to explain why shutdown radiation levels at Vermont Yankee were significantly higher than at Monticello. The plants were shown to be similar in many respects, for example, condenser and feedwater system design and materials, condensate treatment system design, feedwater iron and copper concentrations, reactor water piping materials and fabrication techniques, reactor water cleanup system flowrates and equipment type, fuel cycle lengths, and fuel failure history. Differences were noted in core power density, jet pump design, reactor water conductivity, volume of radwaste recycle, and the amount of Stellite bearing materials in the feedwater system. Corrosion films on reactor system decontamination flanges from the two plants also were very different. At Monticello, the film was typical of that observed at other BWRs. The Vermont Yankee film contained significantly higher levels of zinc, chromium, and cobalt. Since reactor water Co-60 concentrations at Monticello were about twice those at Vermont Yankee, the Vermont Yankee corrosion film must exhibit a greater tendency to incorporate Co-60.

Palino, G.F.; Hobart, R.L.; Sawochka, S.G.

1987-03-01T23:59:59.000Z

73

Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches  

SciTech Connect

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

Steven R. Sherman

2007-06-01T23:59:59.000Z

74

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...

75

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...

76

Pantex Plant | National Nuclear Security Administration  

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

Plant | National Nuclear Security Administration Plant | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Pantex Plant Pantex Plant http://www.pantex.com/ Field Office: The NNSA Production Office is responsible for contract management and oversight of the Pantex Plant in Amarillo, Texas and the Y-12 National Security Complex in Oak Ridge, Tenn. The Pantex Plant is

77

Cobalt transport at the Vermont Yankee BWR  

SciTech Connect

The behavior of Co-59 (the precursor of Co-60) is of particular interest in BWRs since Co-60 has been shown to be primarily responsible for BWR shutdown radiation levels. To assist in understanding cobalt transport in the BWR, a cobalt solution was injected at the effluent of the condensate demineralized system and was transported to the primary system via the feedwater at the Vermont Yankee BWR. The quantity injected was equivalent to the amount transported during routine operation over approximately 7 days. Sample system modified to eliminate cobalt bearing alloys were demonstrated to provide valid process stream samples for cobalt. Cobalt injected at the effluent of the condensate demineralizers was retained in portions of the feedwater cycle for approximately six hours prior to the initial indication of an increase in cobalt transport to the primary system. This anomaly, which led to considerable difficulty in interpreting concentration variations observed during and subsequent to the injection, is attributed to chemi-sorption of cobalt on iron oxide coated surfaces of the condensate/feedwater system. A similar phenomenon also occurred in the primary system thus eliminating the possibility of establishing an absolute value for the primary system cobalt source strength. Nonetheless, it was possible to infer that cobalt transported to the reactor by the feedwater was the primary source of cobalt available for deposition on the fuel. 14 figs., 13 tabs.

Palino, G.F.; Hobart, R.L.; Wall, P.S.; Sawochka, S.G.; Gardner, J.; Prystupa, M.

1986-05-01T23:59:59.000Z

78

Plutonium Processing Plant Deactivated | National Nuclear Security  

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

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

79

Plutonium Processing Plant Deactivated | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Processing Plant Deactivated | National Nuclear Security Processing Plant Deactivated | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated June 20, 1997 Hanford, WA Plutonium Processing Plant Deactivated The Plutonium Uranium Extraction Facility (PUREX), the largest of the

80

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

Energy Savers (EERE)

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

Note: This page contains sample records for the topic "yankee nuclear 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 Regulatory Commission issuances  

SciTech Connect

This document is the March 1996 listing of NRC issuances. Included are: (1) NRC orders granting Cleveland Electric Illuminating Company`s petition for review of the ASLB order LBP-95-17, (2) NRC orders relating to the potential disqualification of two commissioners in the matter of the decommissioning of Yankee Nuclear Power Station, (3) ASLB orders pertaining to the Oncology Services Corporation, (4) ASLB orders pertaining to the Radiation Oncology Center, (5) ASLB orders pertaining to the Yankee Nuclear Power Station, and (6) Director`s decision pertaining to the Yankee Nuclear Power Station.

NONE

1996-03-01T23:59:59.000Z

82

Vermont Yankee experience with interim storage of low level radioactive waste in concrete modules  

SciTech Connect

This paper discusses the implementation of interim storage of low level radioactive waste using concrete modules at the Vermont Yankee Nuclear Power Station in Vernon, Vermont. Under the threat of possible loss of disposal capability in 1986, Vermont Yankee first considered the on-site storage option in 1985. prior to settling on a design, an investigation and economic analysis was performed of several designs. Modular concrete storage on a gravel pad was chosen as the most economical and the one providing the greatest flexibility. The engineering work, safety analysis, and pad construction were completed in 1985. Because of the passage of the Low Level Radioactive Waste Policy amendments Act in 1985, the loss of disposal capability did not occur in 1986. However, because the State of Vermont failed to meet the milestones of the Amendments Act, Vermont Yankee was restricted from the existing disposal sites on January 31, 1989. As a result, modules were purchased and waste was stored on site from 1989 until 1991. In 1991, the State of Vermont came back into compliance with the Amendments Act, and all waste stored on-site was shipped for burial. During the storage period 2 types of modules (1 box type and 1 cylinder type) were used. Lessons were learned, and changes were made to better control the off-site dose contribution of the waste. Recommendations are made to enhance the usability of the facility, such s lighting power, phones, etc. A shortcoming of the module storage concept is the inability to move waste during inclement weather. Despite this, the modules have provided an economical, technically sound, method of waste storage. The storage pad has not been used since 1991, but work is under way to review, and update as necessary, the safety analysis and procedures in preparation for reuse of the on-site storage facility after June 30, 1994.

Berger, S.; Weyman, D. [Vermont Yankee Nuclear Power Corporation, Vernon, VT (United States)

1995-05-01T23:59:59.000Z

83

Beta Dosimetry at Nuclear Power Plants  

Science Journals Connector (OSTI)

......function of gamma dose and energy of the beta rays. Measurements...radiation and effective beta energy obtained in the working environment at nuclear power plants during the shut-down...decommissioning. The effective beta energy is most frequently between......

P. Carný; M. Lieskovsky

1991-08-01T23:59:59.000Z

84

Kansas City Plant | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

85

Kansas City Plant | National Nuclear Security Administration  

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

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our Locations > Kansas City Plant Kansas City Plant http://honeywell.com/sites/aero-kcp/Pages/Home.aspx Field Office: The Kansas City Field Office (KCFO) stewards the NNSA Kansas City Plant, the principal nonnuclear production site within the nuclear

86

Cabell on Nuclear Energy Power Plants  

Science Journals Connector (OSTI)

Cabell on Nuclear Energy Power Plants ... IN EXPLAINING the function of his research group t o the new works superintendent of a nuclear power plant at a mining and reduction installation in the Alaskan mountains, Dr. Blank, of the United Nations Inspection and Research Laboratories, said, "We can't inspect what we don't know. ... In order to know what you're doing, we have to know more about atomic energy than you do—more than anybody does. ...

1947-02-17T23:59:59.000Z

87

Evolution of Nuclear Power Plant Design  

Science Journals Connector (OSTI)

... research is expensive, and applied research and development on atomic energy is so expensive that expenditure should be justified either by the needs of defence or by the expectation of a ... per cent) have risen, and this rise reacts against nuclear power with its high capital cost. The result of these changes is that nuclear power from the plants which ...

CHRISTOPHER HINTON

1960-09-24T23:59:59.000Z

88

The Evolution of Nuclear Power Plant Design: Synopsis  

Science Journals Connector (OSTI)

1 April 1961 research-article The Evolution of Nuclear Power Plant Design: Synopsis Christopher Hinton

1961-01-01T23:59:59.000Z

89

South Carolina Nuclear Profile - Power Plants  

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

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

90

Video camera use at nuclear power plants  

SciTech Connect

A survey of US nuclear power plants was conducted to evaluate video camera use in plant operations, and determine equipment used and the benefits realized. Basic closed circuit television camera (CCTV) systems are described and video camera operation principles are reviewed. Plant approaches for implementing video camera use are discussed, as are equipment selection issues such as setting task objectives, radiation effects on cameras, and the use of disposal cameras. Specific plant applications are presented and the video equipment used is described. The benefits of video camera use --- mainly reduced radiation exposure and increased productivity --- are discussed and quantified. 15 refs., 6 figs.

Estabrook, M.L.; Langan, M.O.; Owen, D.E. (ENCORE Technical Resources, Inc., Middletown, PA (USA))

1990-08-01T23:59:59.000Z

91

Nuclear Regulatory Commission issuances, Volume 44, No. 4  

SciTech Connect

This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

NONE

1996-10-01T23:59:59.000Z

92

SELFMONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION)  

E-Print Network (OSTI)

SELF­MONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION) Aldo and identification are extremely important activities for the safety of a nuclear power plant. In particular inside huge and complex production plants. 1 INTRODUCTION Safety in nuclear power plants requires

93

Bonuses at nuclear arms plants condemned  

Science Journals Connector (OSTI)

The Department of Energy's management of its 17 nuclear weapons plants, already beset by massive environmental, safety, and health problems, drew further fire at a House hearing last week. ... Keith O. Fultz, director of energy issues at the General Accounting Office, presented a report detailing how DOE downplayed or ignored serious environmental, safety, and health problems at the Rocky Flats plant near Denver while awarding the operator, Rockwell International Corp., $26.8 million in performance bonuses in fiscal years 1986- 88. ...

RICHARD SELTZER

1989-10-30T23:59:59.000Z

94

Routine application of the in situ soil analysis technique by the Yankee Atomic Environmental Laboratory  

SciTech Connect

Using a technique developed by the Environmental Measurements Laboratory (EML) for field spectrometry, the Yankee Atomic Environmental Laboratory (YAEL) has routinely performed in situ soil measurements in the vicinity of five nuclear power stations for more than a decade. As a special research endeavor, several locations at the FURNAS Angra 1 site in Brazil having high natural backgrounds were also measured in 1987. The technical basis of the technique, a comparison of soil radionuclide concentrations predicted by the in situ technique to soil radionuclide concentrations predicted by the in situ technique to soil analyses from the same sites, the advantages and disadvantages of the in situ methodology, and the evolution of the portable equipment utilized at YAEL for the field measurements are presented in this paper.

Murray, J.C.; McCurdy, D.E.; Laurenzo, E.L.

1989-01-01T23:59:59.000Z

95

(Nuclear power plant control and instrumentation technology)  

SciTech Connect

While on vacation, the traveler attended the European Nuclear Conference in Lyon, France. This trip was part of an outside activity approved by DOE. The traveler is a consultant to Loyola College, serving as chairman of a panel to assess the state of the art in the controls and instrumentation technology in the European nuclear community. This study is being conducted by Loyola College under subcontract to the National Science Foundation. The traveler was surprised by the level of automation claimed (by the company Siemens AG KWU) to be present in the German Konvoi nuclear power plants. The claim was that this was done to improve the safety of the plant by keeping the operator out of the loop'' for the first 30 minutes of some transients or accidents.

White, J.D.

1990-10-10T23:59:59.000Z

96

Evaluation of BWROG EPG level/power control strategy for Vermont Yankee  

SciTech Connect

The current Boiling Water Reactor Owner's Group (BWROG) emergency procedure guidelines (EPGs) direct reactor operators to manually lower the reactor pressure vessel (RPV) water level to the top of active fuel (TAF) during an anticipated transient without scram (ATWS) event. Lowering the water level reduces the core inlet flow, thereby reducing core power. However, reducing water level is contrary to current operator training, which requires that normal RPV water level be maintained to assure core cooling. In addition, the indicated water level near TAF using cold calibrated level instrumentation may not be reliable, which could potentially result in uncovering the core. This paper evaluates the EPGs' level/power control strategy for the Vermont Yankee plant and proposes alternative to the BWROG guidelines as applied to ATWS response.

Chandola, V.; Robichaud, J.D.

1987-01-01T23:59:59.000Z

97

1 INTRODUCTION In Nuclear Power Plant (NPP) systems, effective  

E-Print Network (OSTI)

1 INTRODUCTION In Nuclear Power Plant (NPP) systems, effective prediction methods are sought for Nuclear Power Plant Failure Scenarios Using an Ensemble-based Approach J. Liu & V. Vitelli Chair

Paris-Sud XI, Université de

98

Nuclear power pros and cons: A comparative analysis of radioactive emissions from nuclear power plants and thermal power plants  

Science Journals Connector (OSTI)

On the basis of the public data statistics of recent years on pollution and emissions from nuclear power plants (NPPs) and thermal power plants...

V. A. Gordienko; S. N. Brykin; R. E. Kuzin…

2012-02-01T23:59:59.000Z

99

Advanced nuclear plant control room complex  

DOE Patents (OSTI)

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

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

1993-01-01T23:59:59.000Z

100

Configuration management in nuclear power plants  

E-Print Network (OSTI)

Configuration management (CM) is the process of identifying and documenting the characteristics of a facility's structures, systems and components of a facility, and of ensuring that changes to these characteristics are properly developed, assessed, approved, issued, implemented, verified, recorded and incorporated into the facility documentation. The need for a CM system is a result of the long term operation of any nuclear power plant. The main challenges are caused particularly by ageing plant technology, plant modifications, the application of new safety and operational requirements, and in general by human factors arising from migration of plant personnel and possible human failures. The IAEA Incident Reporting System (IRS) shows that on average 25% of recorded events could be caused by configuration errors or deficiencies. CM processes correctly applied ensure that the construction, operation, maintenance and testing of a physical facility are in accordance with design requirements as expressed in the d...

2003-01-01T23:59:59.000Z

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

Steam Men, Edisons, Connecticut Yankees: Technocracy and Imperial Identity in Nineteenth-Century American Fiction  

E-Print Network (OSTI)

STEAM MEN, EDISONS, CONNECTICUT YANKEES: TECHNOCRACY AND IMPERIAL IDENTITY IN NINETEENTH-CENTURY AMERICAN FICTION By Copyright 2010 Nathaniel Williams Ph.D., University of Kansas, 2010 Submitted to the Department of English... version of the following dissertation: STEAM MEN, EDISONS, CONNECTICUT YANKEES: TECHNOCRACY AND IMPERIAL IDENTITY IN NINETEENTH-CENTURY AMERICAN FICTION Committee: ______________________ Chairperson, Philip Barnard...

Williams, Nathaniel Langdon

2010-12-31T23:59:59.000Z

102

Relative Movements for Design of Commodities in Nuclear Power Plants  

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

Relative Movements for Design of Commodities in Nuclear Power Plants Javad Moslemian, Vice President, Nuclear Power Technologies, Sargent & Lundy LLC Nezar Abraham, Senior Associate II, Nuclear Power Technologies, Sargent & Lundy LLC

103

Effect of feedwater oxygen control at the Vermont Yankee BWR  

SciTech Connect

Results of a test program to evaluate the impact of oxygen injection on the release and transport of iron, nickel, cobalt, copper and zinc in the feedwater system at the Vermont Yankee boiling water reactor (BWR) are presented. Design and operation of the oxygen injection system are discussed. Conclusions and recommendations relative to generic application of oxygen injection for corrosion product control in BWRs during normal operation are presented. Application of oxygen injection to assist in feedwater system materials passivation after an extended outage also is discussed. 12 refs., 16 figs., 5 tabs.

Hobart, R.L.; Palino, G.F.

1985-07-01T23:59:59.000Z

104

Nuclear Power Plants and Their Fuel as Terrorist Targets  

Science Journals Connector (OSTI)

...applied to terrorism. To tell...Shipment Risk Estimates...Director of Nuclear Control Institute...said that an attack on a plant could make a huge...believe nuclear power is being...operation of nuclear facilities...applied to terrorism. To...Shipment Risk Estimates...Director of Nuclear Control Institute...said that an attack on a plant could make...believe nuclear power is being...

Douglas M. Chapin; Karl P. Cohen; W. Kenneth Davis; Edwin E. Kintner; Leonard J. Koch; John W. Landis; Milton Levenson; I. Harry Mandil; Zack T. Pate; Theodore Rockwell; Alan Schriesheim; John W. Simpson; Alexander Squire; Chauncey Starr; Henry E. Stone; John J. Taylor; Neil E. Todreas; Bertram Wolfe; Edwin L. Zebroski

2002-09-20T23:59:59.000Z

105

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.

106

UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS  

E-Print Network (OSTI)

1 UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS Piero Baraldi1 on transients originated by different faults in the pressurizer of a nuclear power reactor. Key Words: Fault of Nuclear Power Plants (NPPs) [Cheon et al., 1993; Kim et al., 1996; Reifman, 1997; Zio et al., 2006a; Zio

Boyer, Edmond

107

Cesium Removal at Fukushima Nuclear Plant - 13215  

SciTech Connect

The Great East Japan Earthquake that took place on March 11, 2011 created a number of technical challenges at the Fukushima Daiichi Nuclear Plant. One of the primary challenges involved the treatment of highly contaminated radioactive wastewater. Avantech Inc. developed a unique patent pending treatment system that addressed the numerous technical issues in an efficient and safe manner. Our paper will address the development of the process from concept through detailed design, identify the lessons learned, and provide the updated results of the project. Specific design and operational parameters/benefits discussed in the paper include: - Selection of equipment to address radionuclide issues; - Unique method of solving the additional technical issues associated with Hydrogen Generation and Residual Heat; - Operational results, including chemistry, offsite discharges and waste generation. Results show that the customized process has enabled the utility to recycle the wastewater for cooling and reuse. This technology had a direct benefit to nuclear facilities worldwide. (authors)

Braun, James L.; Barker, Tracy A. [Avantech Incorporated, 95A Sunbelt Blvd Columbia, SC 29203 (United States)] [Avantech Incorporated, 95A Sunbelt Blvd Columbia, SC 29203 (United States)

2013-07-01T23:59:59.000Z

108

Evaluation of low flow characteristics of the Vermont Yankee plant  

SciTech Connect

Boiling water reactor (BWR) core flow instrumentation inaccuracies under low-flow conditions have been the subject of both reactor vendor and regulatory communications in response to incidents of the reported core flow being less than the flow corresponding to the natural-circulation line on the power flow map. During single recirculation loop operation, low-flow conditions exist in the idle recirculation loop, and these flow inaccuracies can affect the usefulness of the reported core flow. Accurate core flow indications are needed above 25% power to administer fuel thermal limits and comply with restrictions associated with the potential for thermal-hydraulic instability. While the natural-circulation line on the power flow map is recognized to be a nominal estimate of the flow expected at and near natural-circulation conditions, the boundaries of the stability regions are associated with conditions assumed in safety analyses performed to demonstrate compliance with general design criteria 10 and 12.

Ganther, S.; LeFrancoi, M.; Bergeron, P. [Yankee Atomic Electric Co., Bolton, MA (United States)

1997-12-01T23:59:59.000Z

109

From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World’s First nuclear power plant  

Science Journals Connector (OSTI)

Successful commissioning in the 1954 of the World’s First nuclear power plant constructed at the Institute for Physics ... center for training Soviet and foreign specialists on nuclear power plants, the personnel...

V. I. Rachkov; S. G. Kalyakin; O. F. Kukharchuk; Yu. I. Orlov…

2014-05-01T23:59:59.000Z

110

Nuclear Regulatory Commission issuances  

SciTech Connect

This thirty-second volume of issuances (1--496) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Appeal Boards, Atomic Safety and Licensing Boards, and Administrative Law Judges it covers the period from July 1, 1990 to December 31, 1990. The hardbound edition of the Nuclear Regulatory commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Appeal Boards--ALAB, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors'Decisions--DD, and Denial of Petitions for Rulemaking--DPRM. Specific facilities discussed are: Carroll County Nuclear Station; Palo Verde Nuclear Generating Station; Perry Nuclear Power Plant; Quad Cities Nuclear Power Stations; Seabrook Station; Shoreham Nuclear Generating Plant; Vermont Yankee Nuclear Power Station; and Vogtle Electric Generating Plant.

Not Available

1990-01-01T23:59:59.000Z

111

Water generator replaces bottled water in nuclear power plant  

Science Journals Connector (OSTI)

WaterPure International Incorporated of Doylestown, Pennsylvania, USA, has announced that it has placed its atmospheric water generator (AWG) inside a selected nuclear power plant.

2007-01-01T23:59:59.000Z

112

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 ...

Kengy Barty

2012-02-17T23:59:59.000Z

113

Optimization Online - Nuclear norm minimization for the planted ...  

E-Print Network (OSTI)

Jan 21, 2009 ... Nuclear norm minimization for the planted clique and biclique problems. Brendan Ames(bpames ***at*** math.uwaterloo.ca) Stephen ...

Brendan Ames

2009-01-21T23:59:59.000Z

114

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

115

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

116

Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR  

E-Print Network (OSTI)

An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and ...

Mertens, Paul Gustaaf

1971-01-01T23:59:59.000Z

117

The New York Yankees as an American Cultural Icon, 1940-1970  

E-Print Network (OSTI)

The New York Yankees baseball club, arguably the United States' most successful and well-known sports franchise, have acquired many cultural connotations over the years, meanings transcending the immediate world of on-field sporting contest...

Bishop, William

2014-05-31T23:59:59.000Z

118

SUPERCRITICAL STEAM CYCLE FOR NUCLEAR POWER PLANT  

SciTech Connect

Revolutionary improvement of the nuclear plant safety and economy with light water reactors can be reached with the application of micro-fuel elements (MFE) directly cooled by a supercritical pressure light-water coolant-moderator. There are considerable advantages of the MFE as compared with the traditional fuel rods, such as: Using supercritical and superheated steam considerably increases the thermal efficiency of the Rankine cycle up to 44-45%. Strong negative coolant and void reactivity coefficients with a very short thermal delay time allow the reactor to shutdown quickly in the event of a reactivity or power excursion. Core melting and the creation of corium during severe accidents are impossible. The heat transfer surface area is larger by several orders of magnitude due to the small spherical dimensions of the MFE. The larger heat exchange surface significantly simplifies residual heat removal by natural convection and radiation from the core to a subsequent passive system of heat removal.

Tsiklauri, Georgi V.; Talbert, Robert J.; Schmitt, Bruce E.; Filippov, Gennady A.; Bogojavlensky, Roald G.; Grishanin, Evgeny I.

2005-07-01T23:59:59.000Z

119

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)

EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . • . . . .

Yen, W.W.S.

2010-01-01T23:59:59.000Z

120

NUCLEAR ARMS PLANTS: Idaho bars entry of plutonium wastes  

Science Journals Connector (OSTI)

The Department of Energy—already beset by massive cleanup and safety problems at its nuclear arms plants—now must grapple with a further dilemma in dealing with radioactive wastes. ... Gov. Cecil D. Andrus of Idaho closed the state's borders on Sept. 1 to waste shipments from the Rocky Flats nuclear weapons plant near Denver. ...

RICHARD SELTZER

1989-09-11T23:59:59.000Z

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

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

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

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

122

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

123

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

124

A regional simulation study on dispersion of nuclear pollution from the damaged Fukushima Nuclear Power Plant  

Science Journals Connector (OSTI)

A nuclear accident involving the leaking of radioactive pollutants occurred at the Fukushima Nuclear Power Plant in Japan, following an earthquake and subsequent tsunami on ... accident, this study simulates the ...

JianFang Fei; PengFei Wang; XiaoPing Cheng; XiaoGang Huang…

2014-07-01T23:59:59.000Z

125

16N ?-Ray Diagnostics of a Nuclear Reactor in a Nuclear Power Plant  

Science Journals Connector (OSTI)

The AIRM system, which uses the 16N activity in the VVÉR-1000 reactor at the Kalinin nuclear power plant to measure the thermal power of the reactor and the coolant flow rate, and similar systems used in nuclear

S. G. Tsypin; V. V. Lysenko; A. I. Musorin; L. N. Bogachek; V. F. Bai…

2003-09-01T23:59:59.000Z

126

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

127

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

128

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,

129

Nuclear plant-aging research on reactor protection systems  

SciTech Connect

This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

Meyer, L.C.

1988-01-01T23:59:59.000Z

130

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

131

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

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

132

FAULT DETECTION IN NUCLEAR POWER PLANTS COMPONENTS BY A COMBINATION OF STATISTICAL METHODS  

E-Print Network (OSTI)

FAULT DETECTION IN NUCLEAR POWER PLANTS COMPONENTS BY A COMBINATION OF STATISTICAL METHODS Independent Component Analysis nc Normal conditions NPP Nuclear Power Plant PCA Principal Component Analysis

Paris-Sud XI, Université de

133

Can New Nuclear Power Plants be Project Financed?  

E-Print Network (OSTI)

This paper considers the prospects for financing a wave of new nuclear power plants (NPP) using project financing, which is used widely in large capital intensive infrastructure investments, including the power and gas sectors, but has...

Taylor, Simon

134

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

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...

Yeon, Jaeheum 1981-

2012-12-11T23:59:59.000Z

135

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

136

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

137

US nuclear power plants: Emergency planning inadequate  

Science Journals Connector (OSTI)

... local ! area are considered inadequate. The I operators of the plants - both at IndianIndianPoint ...

Peter David

1983-05-12T23:59:59.000Z

138

Fresh nuclear fuel measurements at Ukrainian nuclear power plants  

SciTech Connect

In 2005, the Provisions on Nuclear Material Measurement System was enacted in Ukraine as an important regulatory driver to support international obligations in nuclear safeguards and nonproliferation. It defines key provisions and requirements for material measurement and measurement control programs to ensure the quality and reliability of measurement data within the framework of the State MC&A System. Implementing the Provisions requires establishing a number of measurement techniques for both fresh and spent nuclear fuel for various types of Ukrainian reactors. Our first efforts focused on measurements of fresh nuclear fuel from a WWR-1000 power reactor.

Kuzminski, Jozef [Los Alamos National Laboratory; Ewing, Tom [ANL; Dickman, Debbie [PNNL; Gavrilyuk, Victor [UKRAINE; Drapey, Sergey [UKRAINE; Kirischuk, Vladimir [UKRAINE; Strilchuk, Nikolay [UKRAINE

2009-01-01T23:59:59.000Z

139

Modelling power output at nuclear power plant by neural networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. NNs are widely used for time series prediction, ... Keywords: evaluation methods, model input selection, neural networks, nuclear power plant, one-step ahead prediction

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-09-01T23:59:59.000Z

140

Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant,  

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

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

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

Regulatory guidance for lightning protection in nuclear power plants  

SciTech Connect

Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects. (authors)

Kisner, R. A.; Wilgen, J. B.; Ewing, P. D.; Korsah, K. [Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN 37831-6007 (United States); Antonescu, C. E. [U.S. Nuclear Regulatory Commission, Washington, DC 20555 (United States)

2006-07-01T23:59:59.000Z

142

Regulatory Guidance for Lightning Protection in Nuclear Power Plants  

SciTech Connect

Abstract - Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects.

Kisner, Roger A [ORNL; Wilgen, John B [ORNL; Ewing, Paul D [ORNL; Korsah, Kofi [ORNL; Antonescu, Christina E [ORNL

2006-01-01T23:59:59.000Z

143

QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY OCTOBER 2013 News Updates  

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

3 3 News Updates ï‚« Dominion has filed an updated integrated resource plan with Virginia and North Carolina State regulators; the plan sets an "earliest possible" in- service date of October 2024 for North Anna 3. Earlier this year, the company announced its intention to return to the General Electric-Hitachi (GEH) ESBWR reactor design with an amended Combined Operating License (COL) to be filed by the end of 2013. ï‚« Entergy announced that it will close its single unit Vermont Yankee nuclear power plant in late 2014; sustained low natural gas prices, financial impacts of cumulative regulations, and the wholesale market structure all contributed to the company's decision to shutter the plant. This is the fourth plant this year to announce decommissioning plans. Dominion's closure of its single unit Kewaunee plant also followed from low wholesale

144

The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units  

Science Journals Connector (OSTI)

The article describes the “Virtual Digital VVER-Based Nuclear Power Plant” computerized system comprising a totality of verified ... a model intended for describing the behavior of nuclear power plant (NPP) syste...

G. V. Arkadov; A. P. Zhukavin; A. E. Kroshilin; I. A. Parshikov…

2014-10-01T23:59:59.000Z

145

The Next Generation Nuclear Plant (NGNP) Project  

SciTech Connect

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

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

146

US nuclear power plant operating cost and experience summaries  

SciTech Connect

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

147

Nuclear Power Plant NDE Challenges - Past, Present, and Future  

SciTech Connect

The operating fleet of U.S. nuclear power plants was built to fossil plant standards (of workmanship, not fitness for service) and with good engineering judgment. Fortuitously, those nuclear power plants were designed using defense-in-depth concepts, with nondestructive examination (NDE) an important layer, so they can tolerate almost any component failure and still continue to operate safely. In the 30+ years of reactor operation, many material failures have occurred. Unfortunately, NDE has not provided the reliability to detect degradation prior to initial failure (breaching the pressure boundary). However, NDE programs have been improved by moving from prescriptive procedures to performance demonstrations that quantify inspection effectiveness for flaw detection probability and sizing accuracy. Other improvements include the use of risk-informed strategies to ensure that reactor components contributing the most risk receive the best and most frequent inspections. Another challenge is the recent surge of interest in building new nuclear power plants in the United States to meet increasing domestic energy demand. New construction will increase the demand for NDE but also offers the opportunity for more proactive inspections. This paper reviews the inception and evolution of NDE for nuclear power plants over the past 40 years, recounts lessons learned, and describes the needs remaining as existing plants continue operation and new construction is contemplated.

Doctor, S. R. [Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352 (United States)

2007-03-21T23:59:59.000Z

148

Review of the natural circulation effect in the Vermont Yankee spent-fuel pool  

SciTech Connect

A 7429-node, three-dimensional computer model of the Vermont Yankee spent-fuel pool was set up and run using the porous media model of the TEMPEST computer code. The results of this analysis show that natural circulation is sufficient to ensure adequate cooling, regardless of the loading pattern used or the orientation of the cooling system discharge nozzle.

Wheeler, C.L.

1988-01-01T23:59:59.000Z

149

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

E-Print Network (OSTI)

in Nuclear Power Plants via Symbolic Dynamic Filtering Xin Jin, Student Member, IEEE, Yin Guo, Soumik Sarkar detection algorithm for condition monitoring of nuclear power plants, where symbolic feature extraction Innova- tive & Secure (IRIS) simulator of nuclear power plants, and its per- formance is evaluated

Ray, Asok

150

Quarterly Nuclear Deployment Scorecard - October 2013 | Department of  

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

October 2013 October 2013 Quarterly Nuclear Deployment Scorecard - October 2013 News Updates Dominion has filed an updated integrated resource plan with Virginia and North Carolina State regulators; the plan sets an "earliest possible" in-service date of October 2024 for North Anna 3. Earlier this year, the company announced its intention to return to the General Electric-Hitachi (GEH) ESBWR reactor design with an amended Combined Operating License (COL) to be filed by the end of 2013. Entergy announced that it will close its single unit Vermont Yankee nuclear power plant in late 2014; sustained low natural gas prices, financial impacts of cumulative regulations, and the wholesale market structure all contributed to the company's decision to shutter the plant.

151

Safety system augmentation at Russian nuclear power plants  

SciTech Connect

This paper describes the design and procurement of a Class IE DC power supply system to upgrade plant safety at the Kola Nuclear Power Plant (NPP). Kola NPP is located above the Arctic circle at Polyarnie Zorie, Murmansk, Russia. Kola NPP consists of four units. Units 1 and 2 have VVER-440/230 type reactors: Units 3 and 4 have VVER-440/213 type reactors. The VVER-440 reactor design is similar to the pressurized water reactor design used in the US. This project provided redundant, Class 1E DC station batteries and DC switchboards for Kola NPP, Units 1 and 2. The new DC power supply system was designed and procured in compliance with current nuclear design practices and requirements. Technical issues that needed to be addressed included reconciling the requirements in both US and Russian codes and satisfying the requirements of the Russian nuclear regulatory authority. Close interface with ATOMENERGOPROEKT (AEP), the Russian design organization, KOLA NPP plant personnel, and GOSATOMNADZOR (GAN), the Russian version of US Nuclear Regulatory Commission, was necessary to develop a design that would assure compliance with current Russian design requirements. Hence, this project was expected to serve as an example for plant upgrades at other similar VVER-440 nuclear plants. In addition to technical issues, the project needed to address language barriers and the logistics of shipping equipment to a remote section of the Former Soviet Union (FSU). This project was executed by Burns and Roe under the sponsorship of the US DOE as part of the International Safety Program (INSP). The INSP is a comprehensive effort, in cooperation with partners in other countries, to improve nuclear safety worldwide. A major element within the INSP is the improvement of the safety of Soviet-designed nuclear reactors.

Scerbo, J.A.; Satpute, S.N.; Donkin, J.Y.; Reister, R.A. [Burns and Roe, Oradell, NJ (United States); [Department of Energy, Germantown, MD (United States)

1996-12-31T23:59:59.000Z

152

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

153

20 - Licensing for nuclear power plant siting, construction and operation  

Science Journals Connector (OSTI)

Abstract: This chapter addresses the need for licensing of nuclear power plants, and how such licenses can be requested by an applicant and granted by a regulatory authority. The licensing process is country dependent, although based on the common principle that the applicant must demonstrate that the proposed nuclear power plant will comply with the established regulations, and that it will operate safely without undue risks to the health and safety of plant personnel, the population and the environment. During the construction and operational phases the regulatory authority ensures compliance with the the license conditions through evaluation, monitoring and inspection. The license may be a single document covering all the phases in the life of the plant, or a set of consecutive documents requested and issued for different phases, which may include design certification, site approval, design and construction, commissioning and operation, design changes during operation, life extension and, finally, decommissioning.

A. Alonso; S.K. Sharma; D.F. Torgerson

2012-01-01T23:59:59.000Z

154

Developing new methodology for nuclear power plants vulnerability assessment  

Science Journals Connector (OSTI)

The fundamental aim of an efficient regulatory emergency preparedness and response system is to provide sustained emergency readiness and to prevent emergency situations and accidents. But when an event occurs, the regulatory mission is to mitigate consequences and to protect people and the environment against nuclear and radiological damage. The regulatory emergency response system, which would be activated in the case of a nuclear and/or radiological emergency and release of radioactivity to the environment, is an important element of a comprehensive national regulatory system of nuclear and radiation safety. In the past, national emergency systems explicitly did not include vulnerability assessments of the critical nuclear infrastructure as an important part of a comprehensive preparedness framework. But after the huge terrorist attack on 11/09/2001, decision-makers became aware that critical nuclear infrastructure could also be an attractive target to terrorism, with the purpose of using the physical and radioactive properties of the nuclear material to cause mass casualties, property damage, and detrimental economic and/or environmental impacts. The necessity to evaluate critical nuclear infrastructure vulnerability to threats like human errors, terrorist attacks and natural disasters, as well as preparation of emergency response plans with estimation of optimized costs, are of vital importance for assurance of safe nuclear facilities operation and national security. In this paper presented new methodology and solution methods for vulnerability assessment can help the overall national energy sector to identify and understand the terrorist threats to and vulnerabilities of its critical infrastructure. Moreover, adopted methodology could help national regulators and agencies to develop and implement a vulnerability awareness and education programs for their critical assets to enhance the security and a safe operation of the entire energy infrastructure. New methods can also assist nuclear power plants to develop, validate, and disseminate assessment and surveys of new efficient countermeasures. Consequently, concise description of developed new quantitative method and adapted new methodology for nuclear regulatory vulnerability assessment of nuclear power plants are presented.

Venceslav Kostadinov

2011-01-01T23:59:59.000Z

155

Long range planning at former nuclear weapon plants  

SciTech Connect

This paper discusses the approach to planning the cleanup of former nuclear weapon manufacturing plants. The limit of backward planning is the knowledge horizon. Extension of backward planning beyond this horizon is futile. Forward planning is the customary method for planning missions extending beyond that horizon. Planning the future of former plant sites is a political activity by political decision makers. Scientists, professional planners, and public interest groups have an advisory role in this activity.

Vrouwes, J.H. [EG & G Rocky Flats, Inc., Golden, CO (United States)

1994-12-31T23:59:59.000Z

156

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)

in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

Nero, A.V.

2010-01-01T23:59:59.000Z

157

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

Nero, A.V.

2010-01-01T23:59:59.000Z

158

Seismic functionality of essential relays in operating nuclear plants  

Science Journals Connector (OSTI)

The regulatory criteria for licensing of nuclear power plants require that certain safety-related equipment and systems be designed to function during and following a postulated, design basis earthquake. Demonstration of seismic adequacy must be performed and formally documented by shake-table testing, analysis or other specified methods. Since many older, operating nuclear power plants were designed and constructed prior to the issuance of the current seismic qualification criteria, the NRC has questioned whether the seismic adequacy of the essential equipment has been adequately demonstrated and documented. This concern is identified in Unresolved Safety Issue A-46, “Seismic Qualification of Equipment in Operating Nuclear Power Plants”. In response to this concern, a group of affected plant owners, the Seismic Qualification Utility Group (SQUG), with support from the Electric Power Research Institute (EPRI), has undertaken a program to demonstrate the seismic adequacy of essential equipment by the use of actual experience with such equipment in plants which have undergone significant earthquakes and by the use of available seismic qualification data for similar equipment. An important part of this program is the development of data and the methodology for verifying the functionality of electrical relays used in essential circuits needed for plant shutdown during a seismic event. This paper describes this part of the Seismic Qualification Utility Group program. The relay functionality evaluation methodology is being developed under EPRI Project No. RP2849-1.

W.R. Schmidt; R.P. Kassawara

1988-01-01T23:59:59.000Z

159

Liquid metal cooled nuclear reactor plant system  

DOE Patents (OSTI)

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

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

1993-01-01T23:59:59.000Z

160

Maintaining plant safety margins  

SciTech Connect

The Final Safety Analysis Report Forms the basis of demonstrating that the plant can operate safely and meet all applicable acceptance criteria. In order to assure that this continues through each operating cycle, the safety analysis is reexamined for each reload core. Operating limits are set for each reload core to assure that safety limits and applicable acceptance criteria are not exceeded for postulated events within the design basis. These operating limits form the basis for plant operation, providing barriers on various measurable parameters. The barriers are refereed to as limiting conditions for operation (LCO). The operating limits, being influenced by many factors, can change significantly from cycle to cycle. In order to be successful in demonstrating safe operation for each reload core (with adequate operating margin), it is necessary to continue to focus on ways to maintain/improve existing safety margins. Existing safety margins are a function of the plant type (boiling water reactor/pressurized water reactor (BWR/PWR)), nuclear system supply (NSSS) vendor, operating license date, core design features, plant design features, licensing history, and analytical methods used in the safety analysis. This paper summarizes the experience at Yankee Atomic Electric Company (YAEC) in its efforts to provide adequate operating margin for the plants that it supports.

Bergeron, P.A.

1989-01-01T23:59:59.000Z

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

Aging management guideline for commercial nuclear power plants - heat exchangers  

SciTech Connect

This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers 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 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.; Lehnert, D.; Daavettila, N.; Palop, E.

1994-06-01T23:59:59.000Z

162

Case studies in magnetics and ground penetrating radar, Shreveport Convention Center, Shreveport, LA and Yankee Boy Rock Glacier, Ouray, CO  

E-Print Network (OSTI)

CASE STUDIES IN MAGNETICS AND GROUND PENETRATING RADAR, SHREVEPORT CONVENTION CENTER, SHREVEPORT, LA AND YANKEE BOY ROCK GLACIER, OURAY, CO A Thesis by CARL J. PIERCE, JR Submitted to the Office of Graduate Studies of Texas A&M University... in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2002 Major Subject: Geophysics CASE STUDIES IN MAGNETICS AND GROUND PENETRATING RADAR, SHREVEPORT CONVENTION CENTER, SHREVEPORT, LA AND YANKEE BOY ROCK GLACIER...

Pierce, Carl J

2012-06-07T23:59:59.000Z

163

City-Sponsored Health Research Eludes New York Budget Ax  

Science Journals Connector (OSTI)

...1112) seem to have pushed the Vermont Yankee nuclear plant further into legal...issue in the state. Even if the Vermont Yankee plant went on line schedule and...increasing consumption. The new Vermont Yankee nuclear plant on the Connecticut...

Robert J. Bazell

1971-09-17T23:59:59.000Z

164

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

165

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

166

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

167

A New Life Adaptive Reuse and Redevelopment of Decommissioned Commercial Nuclear Power Plants.  

E-Print Network (OSTI)

??My study analyzed the challenges and opportunities faced in the historic preservation and adaptive reuse of decommissioned commercial nuclear power plants. While operating, these plants… (more)

Farrow, Elizabeth

2008-01-01T23:59:59.000Z

168

Department of Mechanical and Nuclear Engineering Spring 2012 Automatic Plant Watering System  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical and Nuclear Engineering Spring 2012 Automatic Plant Watering/or audio communication notifications when the product needs maintenance, such as refilling the plant water

Demirel, Melik C.

169

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)

Response Planning for Nuclear Power Plants in California",and Related Standards for Nuclear Power Plants", Lawrencejected lifetime for a nuclear power plant is 40 years, a

Nero, jA.V.

2010-01-01T23:59:59.000Z

170

Enhancement of NRC station blackout requirements for nuclear power plants  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to enhance core and spent fuel pool cooling, reactor coolant system integrity, and containment integrity. (authors)

McConnell, M. W. [United States Nuclear Regulatory Commission, Mail Stop: 012-H2, Washington, DC 20555 (United States)

2012-07-01T23:59:59.000Z

171

Operating nuclear plant feedback to ASME and French codes  

SciTech Connect

The French have an advantage in nuclear plant operating experience feedback due to the highly centralized nature of their nuclear industry. There is only one utility in charge of design as well as operations (EDF) and only one reactor vendor (Framatome). The ASME Code has played a key role in resolving technical issues in the design and operation of nuclear plants since the inception of nuclear power. The committee structure of the Code brings an ideal combination of senior technical people with both broad and specialized experience to bear on complex how safe is safe enough technical issues. The authors now see an even greater role for the ASME Code in a proposed new regulatory era for the US nuclear industry. The current legalistic confrontational regulatory era has been quite destructive. There now appears to be a real opportunity to begin a new era of technical consensus as the primary means for resolving safety issues. This change can quickly be brought about by having the industry take operating plant problems and regulatory technical issues directly to the ASME Code for timely resolution. Surprisingly, there is no institution in the US nuclear industry with such a mandate. In fact, the industry is organized to feedback through the Nuclear Regulatory Commission issues which could be far better resolved through the ASME Code. Major regulatory benefits can be achieved by closing this loop and providing systematic interaction with the ASME Code. The essential elements of a new regulatory era and ideas for organizing US institutional industry responsibilities, taken from the French experience, are described in this paper.

Journet, J. [Electricite de France, Clamart (France); O`Donnell, W.J. [O`Donnell Consulting Engineers, Bethel Park, PA (United States)

1996-12-01T23:59:59.000Z

172

Transients Analysis of a Nuclear Power Plant Component for Fault Diagnosis  

E-Print Network (OSTI)

Transients Analysis of a Nuclear Power Plant Component for Fault Diagnosis Piero Baraldia.baraldi@polimi.it, We analyze signal data collected during 148 shut-down transients of a nuclear power plant (NPP

Paris-Sud XI, Université de

173

Innovative applications of technology for nuclear power plant productivity improvements  

SciTech Connect

The nuclear power industry in several countries is concerned about the ability to maintain high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, and new requirements and commitments. Current plant operations are labor-intensive due to the vast number of operational and support activities required by commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the goal to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New plants are expected to perform more productively than current plants. In order to achieve and increase high productivity, it is necessary to look at innovative applications of modern technologies and new concepts of operation. The Electric Power Research Inst. is exploring and demonstrating modern technologies that enable cost-effectively maintaining current performance levels and shifts to even higher performance levels, as well as provide tools for high performance in new plants. Several modern technologies being explored can provide multiple benefits for a wide range of applications. Examples of these technologies include simulation, visualization, automation, human cognitive engineering, and information and communications technologies. Some applications using modern technologies are described. (authors)

Naser, J. A. [Electric Power Research Inst., 3420 Hillview Avenue, Palo Alto, CA 94303 (United States)

2012-07-01T23:59:59.000Z

174

Yankee hood performance studies; The effect of air balance on thermal efficiency  

SciTech Connect

With today's ever-increasing production rates on tissue-grade machines, many mills experience a need to increase the contribution of Yankee hoods to drying. Until the cylinder is replaced, its contribution to drying is fixed at its maximum drying rate. Consequently, the hoods should be checked routinely to ensure that they run optimally. Most air systems are not gas-or oil-fired, in contrast to the original steam-heated designs. As a result, Yankee air systems are energy intensive. A proper hood balance ensures minimum thermal consumption, or optimum thermal efficiency. Thermal efficiency is defined as the Btu's consumed by the burner per pound of water evaporated by hood. A simple engineering survey, or system examination, allows the papermaker to verify hood performance and balance the air system. In this paper typical data from a such a survey are shown. These surveys can often lead to considerably savings in burner fuel.

Schukov, V. (Yankee Air Systems (US)); Wozny, J. (Enerquin Air Inc., Montreal, Quebec (CA))

1991-04-01T23:59:59.000Z

175

Indicator system for advanced nuclear plant control complex  

DOE Patents (OSTI)

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

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

1993-01-01T23:59:59.000Z

176

Nuclear Power Plant Components Condition Monitoring by Probabilistic Support Vector , Redouane Seraouib  

E-Print Network (OSTI)

Nuclear Power Plant Components Condition Monitoring by Probabilistic Support Vector Machine Jie.zio@ecp.fr Abstract In this paper, an approach for the prediction of the condition of Nuclear Power Plant (NPP monitoring, Nuclear power plant, Point prediction hal-00790421,version1-12Jun2013 Author manuscript

Boyer, Edmond

177

Childhood leukaemia incidence below the age of 5 years near French nuclear power plants  

E-Print Network (OSTI)

Childhood leukaemia incidence below the age of 5 years near French nuclear power plants D Laurier 1 living in the vicinity of nuclear power plants in Germany. We present herein results about the incidence of childhood leukaemia in the vicinity of nuclear power plants in France for the same age range. These results

Paris-Sud XI, Université de

178

Energy Spectra of Stray Neutron Fields at PWR Nuclear Power Plants  

Science Journals Connector (OSTI)

......Protection Dosimetry Article Energy Spectra of Stray Neutron Fields at PWR Nuclear Power Plants P. ~Jujak...equivalent to workers at nuclear power plants are discussed...The measured spectra of energy distribution of neutron...protection of the staff at nuclear power plants are presented......

P. ~Jujak; P. Carný; Z. Prouza; J. Hermanská

1987-07-01T23:59:59.000Z

179

Vermont Yankee's benefits and concerns operating with Axially zoned GE9 fuel  

SciTech Connect

Vermont Yankee (VY) is a 368-assembly, D-lattice, boiling water reactor (BWR)/4. The current cycle 16 contains 252 GE9 assemblies with axial zoning of gadolinium and enrichment, 112 GE8 assemblies with axially zoned gadolinium, and 4 Siemens 9 x 9-IX lead qualification assemblies. In this paper, the performance of the GE9-dominated core is evaluated against previous cores containing less sophisticated fuel designs.

Woehlke, R.A. (Yankee Atomic Electric Co., Bolton, MA (United States))

1993-01-01T23:59:59.000Z

180

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

Reports and Publications (EIA)

Nuclear power plants generate approximately 20% 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 greenhouse gas 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.

2010-01-01T23:59:59.000Z

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

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

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

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

182

Nuclear Fuels Storage & Transportation Planning Project | Department of  

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

Nuclear Fuels Storage & Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut Yankee (http://www.connyankee.com/html/fuel_storage.html). Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel

183

Infrastructure development assistance modeling for nuclear power plant  

SciTech Connect

The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to make the model more sophisticated as a 'semi-tailored model' so that it can be applied to a certain country reflecting its unique conditions. In accordance with its degree of established infrastructure, we can adjust or modify the model. Despite lots of benefits of using this model, there remain limitations such as time and budget constraints. These problems, however, can be addressed by cooperating with international organization such as the IAEA and other companies that share the same goal of helping newcomer countries introduce nuclear power. (authors)

Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M. [Korea Hydro and Nuclear Power Co., LTD, 23, 106 gil, Yeongdong-daero, Gangnam-gu, 153-791 (Korea, Republic of)

2012-07-01T23:59:59.000Z

184

Vermont: Forced to Figure in Big Power Picture  

Science Journals Connector (OSTI)

...because of the delay in getting the Vermont Yankee nuclear plant into operation...by the regional situation. The Vermont Yankee nuclear plant at Vernon has encount-ered...re-sources authorities to allow Vermont Yankee to raise water temperatures by...

John Walsh

1971-10-01T23:59:59.000Z

185

Effect of the Fukushima nuclear accident on the risk perception of residents near a nuclear power plant in China  

Science Journals Connector (OSTI)

...political anchoring”: The case of nuclear power in the United Kingdom . Risk Anal...social-cognitive perspective of terrorism risk perception and individual...just global warming and fear of a nuclear power plant accident? Risk Anal 31 ( 5...

Lei Huang; Ying Zhou; Yuting Han; James K. Hammitt; Jun Bi; Yang Liu

2013-01-01T23:59:59.000Z

186

Regression analysis of technical parameters affecting nuclear power plant performances  

SciTech Connect

Since the 80's many studies have been conducted in order to explicate good and bad performances of commercial nuclear power plants (NPPs), but yet no defined correlation has been found out to be totally representative of plant operational experience. In early works, data availability and the number of operating power stations were both limited; therefore, results showed that specific technical characteristics of NPPs were supposed to be the main causal factors for successful plant operation. Although these aspects keep on assuming a significant role, later studies and observations showed that other factors concerning management and organization of the plant could instead be predominant comparing utilities operational and economic results. Utility quality, in a word, can be used to summarize all the managerial and operational aspects that seem to be effective in determining plant performance. In this paper operational data of a consistent sample of commercial nuclear power stations, out of the total 433 operating NPPs, are analyzed, mainly focusing on the last decade operational experience. The sample consists of PWR and BWR technology, operated by utilities located in different countries, including U.S. (Japan)) (France)) (Germany)) and Finland. Multivariate regression is performed using Unit Capability Factor (UCF) as the dependent variable; this factor reflects indeed the effectiveness of plant programs and practices in maximizing the available electrical generation and consequently provides an overall indication of how well plants are operated and maintained. Aspects that may not be real causal factors but which can have a consistent impact on the UCF, as technology design, supplier, size and age, are included in the analysis as independent variables. (authors)

Ghazy, R.; Ricotti, M. E.; Trueco, P. [Politecnico di Milano, Via La Masa, 34, 20156 Milano (Italy)

2012-07-01T23:59:59.000Z

187

Impacts of the Fukushima Nuclear Power Plants on Marine Radioactivity  

Science Journals Connector (OSTI)

Impacts of the Fukushima Nuclear Power Plants on Marine Radioactivity ... Discussion of these data has involved many of our colleagues in Japan, including M. Uematsu (Atmosphere and Ocean Research Institute, University of Tokyo), M. Honda and T. Kawano (Research Institute for Global Change, Japan Agency for Marine Earth Science and Technology) and D. Tsumune (Environmental Science Research Laboratory, Central Research Institute of Electric Power Industry). ...

Ken Buesseler; Michio Aoyama; Masao Fukasawa

2011-10-20T23:59:59.000Z

188

Understanding the nature of nuclear power plant risk  

SciTech Connect

This paper describes the evolution of understanding of severe accident consequences from the non-mechanistic assumptions of WASH-740 to WASH-1400, NUREG-1150, SOARCA and today in the interpretation of the consequences of the accident at Fukushima. As opposed to the general perception, the radiological human health consequences to members of the Japanese public from the Fukushima accident will be small despite meltdowns at three reactors and loss of containment integrity. In contrast, the radiation-related societal impacts present a substantial additional economic burden on top of the monumental task of economic recovery from the nonnuclear aspects of the earthquake and tsunami damage. The Fukushima accident provides additional evidence that we have mis-characterized the risk of nuclear power plant accidents to ourselves and to the public. The human health risks are extremely small even to people living next door to a nuclear power plant. The principal risk associated with a nuclear power plant accident involves societal impacts: relocation of people, loss of land use, loss of contaminated products, decontamination costs and the need for replacement power. Although two of the three probabilistic safety goals of the NRC address societal risk, the associated quantitative health objectives in reality only address individual human health risk. This paper describes the types of analysis that would address compliance with the societal goals. (authors)

Denning, R. S. [Ohio State Univ., 201 West 19th Avenue, Columbus, OH 43210-1142 (United States)

2012-07-01T23:59:59.000Z

189

Leukemia, Lymphomas, and Myeloma Mortality in the Vicinity of Nuclear Power Plants and Nuclear Fuel Facilities in Spain  

Science Journals Connector (OSTI)

...patterns in the Denver metropolitan area in relation to the Rocky Flats plant. Am. J. Epidemiol., 126: 127-135, 1987...the Hanford Site, Oak Ridge National Laboratory, and Rocky Flats Nuclear Weapons Plant. Radiat. Res., 120: 19-35...

Gonzalo López-Abente; Nuria Aragonés; Marina Pollán; María Ruiz; and Ana Gandarillas

1999-10-01T23:59:59.000Z

190

The development of KM portals for nuclear power plants  

Science Journals Connector (OSTI)

This paper has been prepared with close collaboration between the International Atomic Energy Agency (IAEA)'s International Nuclear Information System (INIS) and Nuclear Knowledge Management Section and representatives of several Nuclear Power Plants (NPPs) and other supporting organisations (IAEA, 2009). The practical experiences of different NPPs show that the development and existence of a knowledge portal for NPPs help to keep the staff informed and the sharing of information helps to maintain safety at a high level. Some examples show that, if the process management is also integrated into the portal system, it helps the organisation to achieve its goals more easily. In this paper we introduce a general concept of designing of a knowledge portal and also a typical content. We are not going to show any examples of IT support systems, because their availability is quite variable in different NPPs and the development stage of the integrated management system (IAEA, 2006a).

A. Kosilov; Z. Pasztory

2009-01-01T23:59:59.000Z

191

Hydrogen Production from the Next Generation Nuclear Plant  

SciTech Connect

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

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

192

Can Yankee ingenuity keep US physics on the ball?  

Science Journals Connector (OSTI)

... to sit back while their European colleagues using new facilities such as the super proton-synchroton (SPS) at the European Centre for Nuclear Research (CERN) and the proposed LEP ...

David Dickson

1979-11-01T23:59:59.000Z

193

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

194

An expert display system and nuclear power plant control rooms  

SciTech Connect

An expert display system controls automatically the display of segments on a cathode ray tube's screen to form an image of plant operations. The image consists of an icon of: 1) the process (heat engine cycle), 2) plant control systems, and 3) safety systems. A set of data-driven, forward-chaining computer stored rules control the display of segments. As plant operation changes, measured plant data are processed through the rules, and the results control the deletion and addition of segments to the display format. The icon contains information needed by control rooms operators to monitor plant operations. One example of an expert display is illustrated for the operator's task of monitoring leakage from a safety valve in a steam line of a boiling water reactor (BWR). In another example, the use of an expert display to monitor plant operations during pre-trip, trip, and post-trip operations is discussed as a universal display. The viewpoints and opinions expressed herein are the author's personal ones, and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, or guidelines.

Beltracchi, L.

1988-04-01T23:59:59.000Z

195

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

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

Mark Holbrook

2010-09-01T23:59:59.000Z

196

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

197

Environmental noise of a nuclear power plant and its substations  

Science Journals Connector (OSTI)

In order to fulfill government requirements for construction of a nuclear power plant an environmental noiseimpact as?assessment has been conducted. Ambient noise was measured continuously for 24 hour periods at the plant and substation sites and in the vicinity. Week long surveys were performed in each of the four seasons. A statistical interpretation of construction noise accounts for variability of construction equipment usage its location and range of sound pressure levels. Histograms of construction noise and measured ambient noise are added to obtain the statistical representation of the predicted construction ambient noise. Operational noise of the plant is similarly predicted. The predicted noise contours of both operation and construction noise are formulated on the topographic maps. Meteorologic and topographic effects on the noise data are discussed.

E. E. Dennison; R. E. Maier; J. W. McGaughey; S. P. Ying

1976-01-01T23:59:59.000Z

198

France to host world's first nuclear fusion plant swissinfo June 28, 2005 3:35 PM  

E-Print Network (OSTI)

France to host world's first nuclear fusion plant swissinfo June 28, 2005 3:35 PM France to host world's first nuclear fusion plant By Guy Faulconbridge MOSCOW (Reuters) - Science's quest to find-nation consortium chose France to host the world's first nuclear fusion reactor. After months

199

Wednesday, November 17, 2004 EU proposes nuclear fusion plant without Japan if there's no accord  

E-Print Network (OSTI)

Wednesday, November 17, 2004 EU proposes nuclear fusion plant without Japan if there's no accord by itself in building a nuclear fusion plant if no agreement is reached with Japan, according to a report, the United States, Russia, China and South Korea are collaborating on the international nuclear fusion

200

A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo  

E-Print Network (OSTI)

A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo Div, conducted using a nuclear power plant shutdown system being developed in Korea, demonstrated (2001~2008) is to develop a suite of I&C software for use in the next generation Korean nuclear power

Jee, Eunkyoung

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

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

E-Print Network (OSTI)

Condition monitoring of motor-operated valves in nuclear power plants Pierre Granjon Gipsa of nuclear power plants. Unfortunately, today's policies present a major drawback. Indeed, these monitoring is illustrated through experimental data. 1. Introduction Nuclear power provides about 14% of the world

Boyer, Edmond

202

Nuclear Regulatory Commission issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders, July 1, 1990--December 31, 1990: Volume 32  

SciTech Connect

This thirty-second volume of issuances (1--496) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Appeal Boards, Atomic Safety and Licensing Boards, and Administrative Law Judges it covers the period from July 1, 1990 to December 31, 1990. The hardbound edition of the Nuclear Regulatory commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Appeal Boards--ALAB, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors`Decisions--DD, and Denial of Petitions for Rulemaking--DPRM. Specific facilities discussed are: Carroll County Nuclear Station; Palo Verde Nuclear Generating Station; Perry Nuclear Power Plant; Quad Cities Nuclear Power Stations; Seabrook Station; Shoreham Nuclear Generating Plant; Vermont Yankee Nuclear Power Station; and Vogtle Electric Generating Plant.

Not Available

1990-12-31T23:59:59.000Z

203

Management of radioactive waste from nuclear power plants: An overview  

SciTech Connect

The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation`s energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse.

Devgun, J.S.

1994-07-01T23:59:59.000Z

204

Fiber optic sensors for nuclear power plant applications  

SciTech Connect

Studies have been carried out for application of Raman Distributed Temperature Sensor (RDTS) in Nuclear Power Plants (NPP). The high temperature monitoring in sodium circuits of Fast Breeder Reactor (FBR) is important. It is demonstrated that RDTS can be usefully employed in monitoring sodium circuits and in tracking the percolating sodium in the surrounding insulation in case of any leak. Aluminum Conductor Steel Reinforced (ACSR) cable is commonly used as overhead power transmission cable in power grid. The suitability of RDTS for detecting defects in ACSR overhead power cable, is also demonstrated.

Kasinathan, Murugesan; Sosamma, Samuel; BabuRao, Chelamchala; Murali, Nagarajan; Jayakumar, Tammana [Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu-603102 (India)

2012-05-17T23:59:59.000Z

205

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

206

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

207

A proposal of nuclear fusion power plant equipped with SMES  

Science Journals Connector (OSTI)

When we intend to operate the nuclear fusion power plant (NFPP) under the economically efficient conditions as an independent power plant, it is desirable that the generated electric power should be sent to network according to the power demand. With such strategy being expanded, some energy storage system is available. In this paper, NFPP equipped with the superconducting magnetic energy storage system (SMES) as electric power storage device is proposed. The advantages of NFPP equipped with SMES are discussed and a case study of 500 MW NFPP equipped with 6 \\{GWh\\} SMES is done with estimating its operational value. For SMES coil, the concept of Force Balanced Coil (FBC) is applied and 6 \\{GWh\\} class FBC is briefly designed.

Tatsuya Natsukawa; Hirokazu Makamura; Marta Molinas; Shinichi Nomura; Shunji Tsuji-Iio; Ryuichi Shimada

2000-01-01T23:59:59.000Z

208

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

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

Lynne M. Stevens

2010-07-01T23:59:59.000Z

209

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.

210

Effect of the Fukushima nuclear accident on the risk perception of residents near a nuclear power plant in China  

Science Journals Connector (OSTI)

...favored the use of nuclear energy (21). A 2009 research...nuclear power is a viable energy option again...nuclear power plant. In Japan, Katsuya (25) found...residential communities. Households within each community...Forty-three percent had a household income between 2,000...

Lei Huang; Ying Zhou; Yuting Han; James K. Hammitt; Jun Bi; Yang Liu

2013-01-01T23:59:59.000Z

211

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

212

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

E-Print Network (OSTI)

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago Representatives of more than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor

213

An Evaluation of Our National Policy to Manage Nuclear Waste from Power Plants  

Science Journals Connector (OSTI)

The current national policy to manage nuclear waste from power plants is to dispose ... of the analysis strongly suggest that our national policy to manage nuclear waste should be changed.

Ralph L. Keeney; Detlof von Winterfeldt

1997-01-01T23:59:59.000Z

214

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

215

Incremental costs and optimization of in-core fuel management of nuclear power plants  

E-Print Network (OSTI)

This thesis is concerned with development of methods for optimizing the energy production and refuelling decision for nuclear power plants in an electric utility system containing both nuclear and fossil-fuelled stations. ...

Watt, Hing Yan

1973-01-01T23:59:59.000Z

216

Fuzzy Failure Rate for Nuclear Power Plant Probabilistic Safety Assessment by Fault Tree Analysis  

Science Journals Connector (OSTI)

Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tree analysis ... a failure possibility-based reliability algorithm to assess nuclear event reliability data from f...

Julwan Hendry Purba; Jie Lu; Guangquan Zhang

2012-01-01T23:59:59.000Z

217

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

218

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

219

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

220

A Participatory Design Framework: Incorporating Public Views into the Design of Nuclear Power Plants.  

E-Print Network (OSTI)

??This thesis presents a participatory systems design framework for the design of a nuclear power plant. The work begins with a review of the so-called… (more)

Goodfellow, Martin J

2013-01-01T23:59:59.000Z

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

Resilience and Procedure Use in the Training of Nuclear Power Plant Operating Crews.  

E-Print Network (OSTI)

?? Control room operating crews are a crucial component in maintaining the safety of nuclear power plants. The primary support to operators during disturbances or… (more)

Gustavsson, Pär

2011-01-01T23:59:59.000Z

222

Alternative off-site power supply improves nuclear power plant safety  

Science Journals Connector (OSTI)

Abstract A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source.

Blaže Gjorgiev; Andrija Volkanovski; Duško Kan?ev; Marko ?epin

2014-01-01T23:59:59.000Z

223

Feature Extraction for Data-Driven Fault Detection in Nuclear Power Plants Xin Jin, Robert M. Edwards and Asok Ray  

E-Print Network (OSTI)

Feature Extraction for Data-Driven Fault Detection in Nuclear Power Plants Xin Jin, Robert M monitoring of nuclear power plants (NPP) is one of the key issues addressed in nuclear energy safety research is performed during each nuclear power plant refueling outage, which may not be cost effective [1

Ray, Asok

224

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

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

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

225

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

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

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

226

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

E-Print Network (OSTI)

of the Decommissioning of the Phénix Nuclear Power Plant Melchior Pelleterat de Borde, MINES ParisTech, Christophe Martin looks at the effect of ongoing organisational changes taking place in a nuclear power plant being campaigns, the Phénix nuclear power plant was taken out of service at the end of 2009. The plant has two

Paris-Sud XI, Université de

227

A critical review of nuclear power plant decommissioning planning studies  

Science Journals Connector (OSTI)

During the past decade there have been at least ten major efforts to perform comprehensive, analytical studies of the complex issues associated with decommissioning civilian nuclear power plants. These planning efforts are reviewed, using the standard framework of technology assessment. In particular, each study is analysed to determine the degree to which formal methods of decision analysis have been employed to evaluate options and make recommendations and the degree to which formal methods of consensus have been employed to engage citizen involvement and promote public acceptance. Not unexpectedly, we find that the greatest strides in decommissioning analyses have been made in forecasting the economic costs of decommissioning to licensees. Comparatively few improvements have been made in the processes used to compare the impacts of alternative technologies more broadly, or to address the legitimate concerns of interested parties more widely.

W.Timothy Lough; K.Preston White Jr.

1990-01-01T23:59:59.000Z

228

Numerical study and prediction of nuclear contaminant transport from Fukushima Daiichi nuclear power plant in the North Pacific Ocean  

Science Journals Connector (OSTI)

On March 11, 2011, a large earthquake and subsequent tsunami near the east coast of Japan destroyed the Fukushima Daiichi nuclear power plant (FD-NPP), causing a massive ... Pacific circulation model, based on th...

Hui Wang; ZhaoYi Wang; XueMing Zhu; DaKui Wang; GuiMei Liu

2012-09-01T23:59:59.000Z

229

Review and evaluation of the RELAP5YA computer code and the Vermont Yankee LOCA (Loss-of-Coolant Accident) licensing analysis model for use in small and large break BWR (Boiling Water Reactor) LOCAS  

SciTech Connect

A review has been completed of the RELAP5YA computer code to determine its acceptability for performing licensing analyses. The review was limited to Boiling Water Reactor (BWR) reactor applications. In addition, a Loss-Of-Coolant Accident (LOCA) licensing analysis method, using the RELAP5YA computer code, has been reviewed. This method is applicable to the Vermont Yankee Nuclear Power Station to perform full break spectra LOCA and fuel cycle independent analyses. The review of the RELAP5YA code consisted of an evaluation of all Yankee Atomic Electric Company (YAEC) incorporated modifications to the RELAP5/MOD1 Cycle 18 computer code from which the licensing version of the code originated. Qualifying separate and integral effects assessment calculations were reviewed to evaluate the validity and proper implementation of the various added models. The LOCA licensing method was assessed by reviewing two RELAP5YA system input models and evaluating several small and large break qualifying transient calculations. A review of the RELAP5YA code modifications and their assessments, as well as the submitted LOCA licensing method, is given and the results of the review are provided.

Jones, J.L.

1987-01-01T23:59:59.000Z

230

Pacific Basin Nuclear Conference (PBNC 2012), BEXCO, Busan, Korea, March 18 ~ 23, 2012 CHALLENGES OF CYBER SECURITY FOR NUCLEAR POWER PLANTS  

E-Print Network (OSTI)

PBNC 2012 CHALLENGES OF CYBER SECURITY FOR NUCLEAR POWER PLANTS Kwangjo Kim KAIST, Daejeon, Korea.kim@kustar.ac.ae Abstract Nuclear Power Plants (NPPs) become one of the most important infrastructures in providing improvement. 1. Introduction Nuclear Power Plants (NPPs) become one of the most important infrastructures

Kim, Kwangjo

231

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.

232

Association between thyroid cancer incidence and the distance from nuclear power plants in the U.S.  

E-Print Network (OSTI)

??Concerns have been widespread that living near nuclear power plants might increase the risk of cancer in surrounding communities. Nuclear power generation is still the… (more)

Watase, Hiroko

2012-01-01T23:59:59.000Z

233

BWR radiation control: plant demonstration  

SciTech Connect

The first year's progress is presented for a four-year program intended to implement and evaluate BRAC radiation reduction operational guidelines at the Vermont Yankee BWR and to document the results in sufficient detail to provide guidance to other BWR owners. Past operational, chemistry and radiation level data have been reviewed to provide a historical base of reference. Extensive sampling and chemistry monitoring systems have been installed to evaluate plant chemistry status and the effects of program implemented changes. Radiation surveys and piping gamma scans are being performed at targeted locations to quantify radiation level trends and to identify and quantify piping isotopics. Contact radiation levels on the recirculation line at Vermont Yankee have been increasing at a rate of 175 mR/h-EFPY since 1978. A materials survey of feedwater and reactor components in contact with the process liquid has been performed to identify sources of corrosion product release, particularly cobalt and nickel. A feedwater oxygen injection system has been installed to evaluate the effects of oxygen control on feedwater materials corrosion product releases. A baseline performance evaluation of the condensate treatment and reactor water cleanup systems has been completed. Data on organics and ionics at Vermont Yankee have been obtained. A methodology of BWR feedwater system layup during extended outages was developed, and an evaluation performed of layup and startup practices utilized at Vermont Yankee during the fall 1980 and 1981 refueling outages.

Palino, G.F.; Hobart, R.L.; Wall, P.S.; Sawochka, S.G.

1982-11-01T23:59:59.000Z

234

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

235

Current Concentration of Artificial Radionuclides and Estimated Radiation Doses from 137Cs around the Chernobyl Nuclear Power Plant, the Semipalatinsk Nuclear Testing Site, and in Nagasaki  

Science Journals Connector (OSTI)

......137Cs around the Chernobyl Nuclear Power Plant, the Semipalatinsk Nuclear Testing Site, and in Nagasaki...the Chernobyl accident and nuclear tests at SNTS were simultaneously...from sev- eral statistical datasets, as there were no detailed......

Yasuyuki Taira; Naomi Hayashida; Gopalganapathi M. Brahmanandhan; Yuji Nagayama; Shunichi Yamashita; Jumpei Takahashi; Alexander Gutevitc; Alexander Kazlovsky; Marat Urazalin; Noboru Takamura

2011-01-01T23:59:59.000Z

236

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

237

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

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

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

238

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

239

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

240

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

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

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

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

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)

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

Nero, A.V.

2010-01-01T23:59:59.000Z

242

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing Plant  

E-Print Network (OSTI)

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing: There is concern about the health of populations living close to nuclear waste reprocessing plants. We conducted a comparative study on reproductive life events in the general population living near the nuclear waste

Paris-Sud XI, Université de

243

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

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

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

244

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

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

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

245

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

246

Example G Cost of construction of nuclear power plants Description of data  

E-Print Network (OSTI)

Example G Cost of construction of nuclear power plants Description of data Table G.1 gives data) power plants constructed in USA. It is required to predict the capital cost involved in the construction of further LWR power plants. The notation used in Table G.1 is explained in Table G.2. The final 6 lines

Reid, Nancy

247

Example G Cost of construction of nuclear power plants Description of data  

E-Print Network (OSTI)

1 Example G Cost of construction of nuclear power plants Description of data Table G.1 gives reactor (LWR) power plants constructed in USA. It is required to predict the capital cost involved in the construction of further LWR power plants. The notation used in Table G.1 is explained in Table G.2. The final 6

Reid, Nancy

248

Department of Mechanical and Nuclear Engineering Spring 2012 East Campus Power Plant Deaerator Optimization  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical and Nuclear Engineering Spring 2012 East Campus Power Plant Deaerator Optimization Overview In the East Campus Power plant a new Deaerator system has been installed. Approach Understand the inner-workings and operations of the power plant and the Deaerator system. Visit

Demirel, Melik C.

249

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010  

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

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010

250

Safeguards Issues at Nuclear Reactors and Enrichment Plants  

SciTech Connect

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

Boyer, Brian D [Los Alamos National Laboratory

2012-08-15T23:59:59.000Z

251

Two novel procedures for aggregating randomized model ensemble outcomes for robust signal reconstruction in nuclear power plants monitoring systems  

E-Print Network (OSTI)

reconstruction in nuclear power plants monitoring systems P. Baraldi1 , E. Zio1,* , G. Gola2 , D. Roverso2 , M importance for the safe and reliable operation of nuclear power plants. Auto-associative regression models of nuclear power plants for it allows the timely detection of malfunctions and anomalies during operation

Paris-Sud XI, Université de

252

Abstract--Resins are used in nuclear power plants for water ultrapurification. Two approaches are considered in this work  

E-Print Network (OSTI)

Abstract--Resins are used in nuclear power plants for water ultrapurification. Two approaches in manufacturing ultrapure water for nuclear power plants. Resins allow the removal of ionic impurities to subparts-per-million. Thereby in nuclear power plants, resins contribute to guarantee personnel safety, to control feed system

Paris-Sud XI, Université de

253

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

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

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

254

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

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

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

255

Applications of neural networks to monitoring and decision making in the operation of nuclear power plants  

SciTech Connect

Application of neural networks to monitoring and decision making in the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (1) diagnosing specific abnormal conditions or problems in nuclear power plants, (2) detection of the change of mode of operation of the plant, (3) validating signals coming from detectors, (4) review of noise'' data from TVA's Sequoyah Nuclear Power Plant, and (5) examination of the NRC's database of Letter Event Reports'' for correlation of sequences of events in the reported incidents. Each of these projects and its status are described briefly in this paper. This broad based program has as its objective the definition of the state-of-the-art in using neural networks to enhance the performance of commercial nuclear power plants.

Uhrig, R.E. (Tennessee Univ., Knoxville, TN (United States) Oak Ridge National Lab., TN (United States))

1990-01-01T23:59:59.000Z

256

Dynamic safeguard assessment of terror attacks using system dynamics method for nuclear power plants  

Science Journals Connector (OSTI)

For the minimisation of the damage in possible terror attacks on the nuclear power plants and other nuclear facilities, a dynamic assessment is performed in the aspects of nuclear safeguard. The incidents against nuclear facilities are modelled by the time-step scenario. Several cases are explained for the illicit trafficking of radioactive material. The dynamic simulation is examined by the system dynamics method. In the modelling, there are three major models that include the nuclear insider terror, the reaction control and the nuclear forensic steps. The risk increases slowly and decreases rapidly in the result. This is the similar pattern of the September 2001 terror where many lives were lost.

Tae-Ho Woo; Un-Chul Lee; Yun-Il Kim

2010-01-01T23:59:59.000Z

257

Quiz # 7, STAT 383, Prof. Suman Sanyal, April 8, 2009 (Q2, Page 354) To decide whether the pipe welds in a nuclear power plant meet  

E-Print Network (OSTI)

welds in a nuclear power plant meet specifications, a random sample of welds is to be selected : µ nuclear power plants is to determine if welds

Sanyal, Suman

258

Status of radioiodine control for nuclear fuel reprocessing plants  

SciTech Connect

This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used.

Burger, L.L.; Scheele, R.D.

1983-07-01T23:59:59.000Z

259

Advanced ultrasonic imaging of piping in Dresden and Vermont Yankee reactors  

SciTech Connect

Pacific Northwest Laboratory (PNL) has been developing the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT) for the US Nuclear Regulatory Commission (NRC). Objectives are to make a real-time field system for performing all required inservice inpsections on nuclear power plants. The NRC funded the laboratory phase of the work at the University of Michigan. The PNL role is to transfer the technology to the field. This paper reports on the experience gained during 1984 involving the inspection of two boiling water reactor (BWR) plants in the United States. These field trials were very successful and demonstrated the advantages of using a flexible, high resolution imaging system to aid in detecting and interpreting ultrasonic reflectors.

Doctor, S.R.; Hall, T.E.; Crawford, S.L.

1985-03-01T23:59:59.000Z

260

Confirmation of the seismic resistance of nuclear power plant equipment after assembly  

SciTech Connect

It is shown that the natural frequencies and damping decrements of nuclear power plant equipment can only be determined experimentally and directly at the power generation units (reactors) of nuclear power plants under real disassembly conditions for the equipment, piping network, thermal insulation, etc. A computational experimental method is described in which the natural frequencies and damping decrements are determined in the field and the seismic resistance is reevaluated using these values. This method is the basis of the standards document 'Methods for confirming the dynamic characteristics of systems and components of the generating units of nuclear power plants which are important for safety' prepared and introduced in 2012.

Kaznovsky, P. S.; Kaznovsky, A. P.; Saakov, E. S.; Ryasnyj, S. I. [JSC 'Atomtehenergo' (Russian Federation)

2013-05-15T23:59:59.000Z

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

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

262

Behavior of a Nuclear Power Plant Ventilation Stack for Wind Loads  

Science Journals Connector (OSTI)

This paper describes behavior of self supporting tall reinforced concrete (RC) ventilation stack of a nuclear power plant (NPP) for wind loads. Since the static and equivalent dynamic wind loads are inter-dependa...

V. Venkatachalapathy

2012-05-01T23:59:59.000Z

263

Episode Analysis of Deposition of Radiocesium from the Fukushima Daiichi Nuclear Power Plant Accident  

Science Journals Connector (OSTI)

Episode Analysis of Deposition of Radiocesium from the Fukushima Daiichi Nuclear Power Plant Accident ... Center for Regional Environment Research, National Institute for Environmental Studies, 16-2, Onogawa, Tsukuba, Ibaraki, 305-8506, Japan ...

Yu Morino; Toshimasa Ohara; Mirai Watanabe; Seiji Hayashi; Masato Nishizawa

2013-02-07T23:59:59.000Z

264

137Cs Trapped by Biomass within 20 km of the Fukushima Daiichi Nuclear Power Plant  

Science Journals Connector (OSTI)

137Cs Trapped by Biomass within 20 km of the Fukushima Daiichi Nuclear Power Plant ... † Department of Health and Environmental Sciences, Graduate School of Medicine, Kyoto University, Kyoto 606-8501, Japan ...

Akio Koizumi; Tamon Niisoe; Kouji H. Harada; Yukiko Fujii; Ayumu Adachi; Toshiaki Hitomi; Hirohiko Ishikawa

2013-07-26T23:59:59.000Z

265

A modeling and control approach to advanced nuclear power plants with gas turbines  

Science Journals Connector (OSTI)

Abstract Advanced nuclear power plants are currently being proposed with a number of various designs. However, there is a lack of modeling and control strategies to deal with load following operations. This research investigates a possible modeling approach and load following control strategy for gas turbine nuclear power plants in order to provide an assessment way to the concept designs. A load frequency control strategy and average temperature control mechanism are studied to get load following nuclear power plants. The suitability of the control strategies and concept designs are assessed through linear stability analysis methods. Numerical results are presented on an advanced molten salt reactor concept as an example nuclear power plant system to demonstrate the validity and effectiveness of the proposed modeling and load following control strategies.

Günyaz Ablay

2013-01-01T23:59:59.000Z

266

Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants?  

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

Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants? Javad Moslemian Sargent & Lundy, LLC U. S. Department of Energy Natural Phenomena Hazards Meeting October 21-22, 2014

267

Power System Frequency Control Characteristics as a Function of Nuclear Power Plant Participation  

Science Journals Connector (OSTI)

When the participation of nuclear power plants in electric power system increases then they have to be ... take an increasing part in the frequency and power control of the power system. However there are specifi...

Z. Domachowski

1988-01-01T23:59:59.000Z

268

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

Science Journals Connector (OSTI)

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

LUIGI DEBARBERIS; KAISA SIMOLA…

2006-01-01T23:59:59.000Z

269

Brackish groundwater as an alternative source of cooling water for nuclear power plants in Israel  

Science Journals Connector (OSTI)

Because of a high population density in the coastal plain, any future nuclear power plants will be located in the sparsely ... no surface water, the only alternatives to cooling water are piped-in Mediterranean. ...

A. Arad; A. Olshina

1984-01-01T23:59:59.000Z

270

Radionuclides in the Natural–Anthropogenic System Comprising a Nuclear Power Plant and a Cooling Reservoir  

Science Journals Connector (OSTI)

The sources of technological radionuclides coming into the ecosystem of a nuclear power plant (NPP) cooling reservoir are considered and estimated. The information ... The activity reserve in the ecosystems of th...

Yu. A. Egorov

2002-07-01T23:59:59.000Z

271

Impact assessment of nuclear and thermal power plants on zooplankton in cooling ponds  

Science Journals Connector (OSTI)

The current state of assessment of nuclear and thermal power plant toxic effects on zooplankton entrained in ... particular emphasis is given to specific features of cooling reservoirs and their ecosystems. Compl...

N. V. Kartasheva; D. V. Fomin; A. V. Popov…

2008-09-01T23:59:59.000Z

272

U.S. Energy Information Administration (EIA) - Issuestrends  

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

with the start of the fall refueling season September 13, 2013 electricityoutages Vermont Yankee nuclear plant closure in 2014 will challenge New England energy markets...

273

Trait, state or artefact? Assessing experts' regulatory focus in nuclear power plant control  

Science Journals Connector (OSTI)

We apply the theory of regulatory focus in the field of nuclear power plant (NPP) control. The first pilot study was conducted at the German simulator centre for NPPs. Here, we tested the influence of accident training lessons on the experts' regulatory ... Keywords: Experts, Human factors, Nuclear, Regulatory focus, Self-report measures

Johannes Beck, Armin Eichinger, Klaus Bengler

2014-11-01T23:59:59.000Z

274

Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants - Final Technical Report  

SciTech Connect

OAK B188 Summary of methods proposed for risk informing the design and regulation of future nuclear power plants. All elements of the historical design and regulation process are preserved, but the methods proposed for new plants use probabilistic risk assessment methods as the primary decision making tool.

Ritterbusch, Stanley; Golay, Michael; Duran, Felicia; Galyean, William; Gupta, Abhinav; Dimitrijevic, Vesna; Malsch, Marty

2003-01-29T23:59:59.000Z

275

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

SciTech Connect

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

M. J. Russell

2006-06-01T23:59:59.000Z

276

The Fukushima Disaster and Japan’s Nuclear Plant Vulnerability in Comparative Perspective  

Science Journals Connector (OSTI)

Off-site power can be severed by a variety of events, such as terrorism, tornadoes, hurricanes, and other disasters. ... Figure 1 plots base plant elevation, seawall height, emergency power system elevation, and waterproofing of backup power systems for nuclear plants according to country. ...

Phillip Y. Lipscy; Kenji E. Kushida; Trevor Incerti

2013-05-16T23:59:59.000Z

277

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

E-Print Network (OSTI)

Jan 21, 2009 ... We write both problems as matrix-rank minimization and then relax them using the nuclear norm. This technique, which may be regarded as a ...

2009-01-21T23:59:59.000Z

278

Radiation-proof windows for nuclear-power plants  

Science Journals Connector (OSTI)

This paper presents a brief analysis of the main technical characteristics of means of direct observation and biological protection for this country’s nuclear-power...

Belousov, S P; Golikov, D A; Ignatov, A N; Kuznetsov, S A; Kuleshov, N P

2013-01-01T23:59:59.000Z

279

Simultaneous Sampling of Indoor and Outdoor Airborne Radioactivity after the Fukushima Daiichi Nuclear Power Plant Accident  

Science Journals Connector (OSTI)

Simultaneous Sampling of Indoor and Outdoor Airborne Radioactivity after the Fukushima Daiichi Nuclear Power Plant Accident ... Large amts. of radioactive substances were released into the environment from the Fukushima Dai-ichi Nuclear Power Plants in eastern Japan as a consequence of the great earthquake (M 9.0) and tsunami of 11 March 2011. ... Proceedings of the International Symposium on Environmental Monitoring and Dose Estimation of Residents after Accident of TEPCO’s Fukushima Daiichi Nuclear Power Station; Shiran Hall, Kyoto, Japan, Dec 14, 2012; http://www.rri.kyoto-u.ac.jp/anzen_kiban/outcome/. ...

Tetsuo Ishikawa; Atsuyuki Sorimachi; Hideki Arae; Sarata Kumar Sahoo; Miroslaw Janik; Masahiro Hosoda; Shinji Tokonami

2014-01-22T23:59:59.000Z

280

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

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

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

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

DATA-DRIVEN ON-LINE PREDICTION OF THE AVAILABLE RECOVERY TIME IN NUCLEAR POWER PLANT FAILURE SCENARIOS  

E-Print Network (OSTI)

1 DATA-DRIVEN ON-LINE PREDICTION OF THE AVAILABLE RECOVERY TIME IN NUCLEAR POWER PLANT FAILURE-XADS). Key Words: Recovery Time, Emergency Accident Management, Nuclear Power Plant, Lead- Bismuth Eutectic e-26Jul2012 Author manuscript, published in "ESREL 2010 (2010) 1 - 8" #12;2 1. Introduction Nuclear Power

Boyer, Edmond

282

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

SciTech Connect

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

283

Sensitivity analysis for the outages of nuclear power plants  

E-Print Network (OSTI)

Feb 17, 2012 ... Energy generation in France is a competitive market, whereas ... from wind farms, solar energy or run of river plant without pondage.

2012-02-17T23:59:59.000Z

284

Dynamic alarm presentation in a nuclear plant control room  

DOE Patents (OSTI)

The alarm activation set point and priority for a given, spatially fixed alarm tile can vary depending in part on the mode of plant operation.

Kenneth, Scarola (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

285

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

National Nuclear Security Administration (NNSA)

0/01/2010 to 09/30/2013 | National Nuclear Security 0/01/2010 to 09/30/2013 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Kansas City Plant - 10/01/2010 to 09/30/2013 Home > About Us > Our Operations > Acquisition and Project Management > M & O Support Department > Kansas City Plant - 10/01/2010 to 09/30/2013 Kansas City Plant - 10/01/2010 to 09/30/2013

286

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

287

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

288

The assessment of the absorbed dose of radiation around a nuclear fuel manufacturing plant  

Science Journals Connector (OSTI)

The estimation of the absorbed dose of radiation by the public around a nuclear plant is a substantial issue for nuclear industries and serves as an essential factor in radiation protection. In this study, the absorbed dose of radiation by the individuals living around a nuclear fuel manufacturing plant was calculated. The Atomic Force Microscopy (AFM) code, which is the generalised version of the AIREM program manual – a computer code for calculating doses, population doses, and ground depositions due to atmospheric emissions of radionuclides – was used to investigate the following pathways: cloud immersion, ground deposition, inhalation and ingestion. The study was carried out in 16 geographical directions over an 80 km radius. The experimental results demonstrate that the maximum dose is absorbed at 800 m distance from the nuclear plant stack in the east southeast (ESE) direction and is equal to 3.7 × 10³ ?Sv, which is negligible in comparison with the background radiation.

Seyed Mahmoud Reza Aghamiri; Neda Bostani; Manuchehr Roshanzamir

2009-01-01T23:59:59.000Z

289

Economic feasibility of heat supply from nuclear power plants in the United States  

SciTech Connect

Nuclear energy is regarded as competitive for urban district heating applications. Hot water heat transport systems of up to 50 miles are feasible for heat loads over 1500 MWt, and heat load density of over 130 MWt/mi/sup 2/is most suitable for nuclear applications. An incremental approach and a nuclear plant design provision for future heat extraction are recommended. Nuclear district heating technology status is discussed, particularly turbine design. Results of a study for retrofitting a major existing nuclear power plant to cogeneration operation are presented. The study indicates that for transmission distances up to 20 miles it is economical to generate and transport between 600 and 1200 MWt of district heat.

Roe, K.K.; Oliker, I.

1988-01-01T23:59:59.000Z

290

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

291

Modelling Power Output at Nuclear Power Plant by Neural Networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. N...

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-01-01T23:59:59.000Z

292

Nuclear Power Plant NDE Challenges - Past, Present, and Future  

SciTech Connect

This is a paper that covers the major thrust of NDE work that PNNL has conducted for the U.S. Nuclear Regulatory Commission from 1977 to the present.

Doctor, Steven R.

2007-01-01T23:59:59.000Z

293

Use of neural networks in the operation of nuclear power plants  

SciTech Connect

Application of neural networks to the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (a) diagnosing specific abnormal conditions, (b) detection of the change of mode of operation, (c) signal validation, (d) monitoring of check valves, (e) modeling of the plant thermodynamics, (f) emulation of core reload calculations, (g) analysis of temporal sequences in NRC's licensee event report,'' (h) monitoring of plant parameters, and (i) analysis of plant vibrations. Each of these projects and its status are described briefly in this article. the objective of each of these projects is to enhance the safety and performance of nuclear plants through the use of neural networks. 6 refs.

Uhrig, R.E. (Tennessee Univ., Knoxville, TN (USA) Oak Ridge National Lab., TN (USA))

1990-01-01T23:59:59.000Z

294

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

295

Social Decision-making Processes in Local Contexts: An STS Case Study on Nuclear Power Plant Siting in Japan  

Science Journals Connector (OSTI)

This is an STS case study of the social decision-making process on the siting of a nuclear power plant in Japan, from the point of view of a ... and the phase involving introduction into society. Nuclear power te...

Kohta Juraku; Tatsujiro Suzuki; Osamu Sakura

2007-12-01T23:59:59.000Z

296

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

297

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

298

Initiating Event Rates at U.S. Nuclear Power Plants 1988–2013  

SciTech Connect

Analyzing initiating event rates is important because it indicates performance among plants and also provides inputs to several U.S. Nuclear Regulatory Commission (NRC) risk-informed regulatory activities. This report presents an analysis of initiating event frequencies at U.S. commercial nuclear power plants since each plant’s low-power license date. The evaluation is based on the operating experience from fiscal year 1988 through 2013 as reported in licensee event reports. Engineers with nuclear power plant experience staff reviewed each event report since the last update to this report for the presence of valid scrams or reactor trips at power. To be included in the study, an event had to meet all of the following criteria: includes an unplanned reactor trip (not a scheduled reactor trip on the daily operations schedule), sequence of events starts when reactor is critical and at or above the point of adding heat, occurs at a U.S. commercial nuclear power plant (excluding Fort St. Vrain and LaCrosse), and is reported by a licensee event report. This report displays occurrence rates (baseline frequencies) for the categories of initiating events that contribute to the NRC’s Industry Trends Program. Sixteen initiating event groupings are trended and displayed. Initiators are plotted separately for initiating events with different occurrence rates for boiling water reactors and pressurized water reactors. p-values are given for the possible presence of a trend over the most recent 10 years.

John A. Schroeder; Gordon R. Bower

2014-02-01T23:59:59.000Z

299

Evaluation of an advanced fault detection system using Koeberg nuclear power plant data / H.L. Pelo.  

E-Print Network (OSTI)

??The control and protection system of early nuclear power plants (Generation II) have been designed and built on the then reliable analog system. Technology has… (more)

Pelo, Herbert Leburu

2013-01-01T23:59:59.000Z

300

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

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

Health Risks of Accidents at Nuclear Power Plants  

Science Journals Connector (OSTI)

To the Editor: Christodouleas et al. (June 16 issue) discuss the health risks of nuclear accidents but do not include the psychological and social effects of such events. Such casualties in Fukushima will far exceed any cases of physical illness. Having just returned from the region to assess mental... To the Editor: Christodouleas et al. (June 16 issue)1 discuss the health risks of nuclear accidents but do not include the psychological and social effects of such events. Such casualties in Fukushima will far exceed any cases of physical illness. Having ...

2011-09-08T23:59:59.000Z

302

Decommissioning of Large Components as an Example of Steam Generator from PWR Nuclear Power Plants  

SciTech Connect

This paper describes the procedure for the qualification of large components (Steam Generators) as an IP-2 package, the ship transport abroad to Sweden and the external treatment of this components to disburden the Nuclear Power Plant from this task, to assure an accelerated the deconstruction phase and to minimize the amount of waste. In conclusion: The transport of large components to an external treatment facility is linked with many advantages for a Nuclear Power Plant: - Disburden of the Nuclear Power Plant from the treatment of such components, - no timely influence on the deconstruction phase of the power reactor and therewith an accelerated deconstruction phase and - minimization of the waste to be returned and therewith less demand of required waste storage capacity. (authors)

Beverungen, M. [GNS Gesellschaft fur Nuklear-Service mbH, Hollestrabe 7A (Germany)

2008-07-01T23:59:59.000Z

303

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

304

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

SciTech Connect

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

Robert Bean; Casey Durst

2009-10-01T23:59:59.000Z

305

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

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

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

306

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)

Yankee, Dresden, and Indian Point) relied mainly on basicareas such as those around Indian Point. present a differentdensity sites such as Indian lO Point and Zion. However,

Yen, W.W.S.

2010-01-01T23:59:59.000Z

307

Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant  

SciTech Connect

This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

Sheaffer, M.K.; Keeton, S.C.

1993-09-20T23:59:59.000Z

308

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.

NONE

1995-04-21T23:59:59.000Z

309

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

SciTech Connect

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

310

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

SciTech Connect

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

Kocsis, F.J. III

1994-12-31T23:59:59.000Z

311

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

SciTech Connect

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

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

1998-11-01T23:59:59.000Z

312

The influence of condenser cooling seawater fouling on the thermal performance of a nuclear power plant  

Science Journals Connector (OSTI)

Abstract This study performs a thermodynamic analysis and energy balance to study the effect of fouling change on the thermal performance of the condenser and the thermal efficiency of a proposed nuclear power plant. The study is carried out on a pressurized water reactor nuclear power plant. The results of the study show that the increasing of fouling factor decreases the power output and the thermal efficiency of the nuclear power plant. The main results of this study is that the impact of an increase in the condenser cooling seawater fouling factor in the range 0.00015–0.00035 m2 K/W is led to a decrease in the plant output power and thermal efficiency of 1.36% and 0.448%, respectively. The present paper researches into a real practical factor that has significant negative effect on the thermal efficiency of the nuclear power plants, which is fouling of condenser cooling seawater. This is abundantly important since one of the top goals of new power stations are to increase their thermal efficiency, and to prevent or minimize the reasons that lead to loss of output power.

Said M.A. Ibrahim; Sami I. Attia

2015-01-01T23:59:59.000Z

313

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

314

Next Generation Nuclear Plant Project 2009 Status Report  

SciTech Connect

The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

2010-05-01T23:59:59.000Z

315

Detection of radioxenon in Darwin, Australia following the Fukushima Dai-ichi nuclear power plant accident  

Science Journals Connector (OSTI)

Abstract A series of 133Xe detections in April 2011 made at the Comprehensive Nuclear-Test-Ban Treaty Organisation (CTBTO) International Monitoring System noble gas station in Darwin, Australia, were analysed to determine the most likely source location. Forward and backwards atmospheric transport modelling simulations using FLEXPART were conducted. It was shown that the most likely source location was the Fukushima Dai-ichi nuclear power plant accident. Other potential sources in the southern hemisphere were analysed, including the Australian Nuclear Science and Technology Organisation (ANSTO) radiopharmaceutical facility, but it was shown that sources originating from these locations were highly unlikely to be the source of the observed 133Xe Darwin detections.

Blake Orr; Michael Schöppner; Rick Tinker; Wolfango Plastino

2013-01-01T23:59:59.000Z

316

Engineering and planning for decommissioning of nuclear power plants  

SciTech Connect

With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania.

Gans, G.M. Jr.

1982-01-01T23:59:59.000Z

317

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

318

Analysis of population radiation dose from a postulated nuclear power plant complex  

E-Print Network (OSTI)

CALCULATIONS Plant Complex Layout Site Of Study The site was chosen to coincide with the current site of the A. W. Vogtle Nuclear Plant (VNP) of Georgia Power Company. This site is located in Burke County, Georgia on the western bank of the Savannah River... mile from neighboring power plants. All eight facilities were sited collinearly along a NW to SE line through site number 4. This approximately parallels the Savannah River. A diagram of this layout is given in Figure 3. As may be seen in Figure 4...

Williford, John Michael

2012-06-07T23:59:59.000Z

319

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

SciTech Connect

Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs.

Seidensticker, R.W.; Chang, Y.W.

1990-01-01T23:59:59.000Z

320

The integrated workstation: A common, consistent link between nuclear plant personnel and plant information and computerized resources  

SciTech Connect

The increasing use of computer technology in the US nuclear power industry has greatly expanded the capability to obtain, analyze, and present data about the plant to station personnel. Data concerning a power plant`s design, configuration, operational and maintenance histories, and current status, and the information that can be derived from them, provide the link between the plant and plant staff. It is through this information bridge that operations, maintenance and engineering personnel understand and manage plant performance. However, it is necessary to transform the vast quantity of data available from various computer systems and across communications networks into clear, concise, and coherent information. In addition, it is important to organize this information into a consolidated, structured form within an integrated environment so that various users throughout the plant have ready access at their local station to knowledge necessary for their tasks. Thus, integrated workstations are needed to provide the inquired information and proper software tools, in a manner that can be easily understood and used, to the proper users throughout the plant. An effort is underway at the Oak Ridge National Laboratory to address this need by developing Integrated Workstation functional requirements and implementing a limited-scale prototype demonstration. The integrated Workstation requirements will define a flexible, expandable computer environment that permits a tailored implementation of workstation capabilities and facilitates future upgrades to add enhanced applications. The functionality to be supported by the integrated workstation and inherent capabilities to be provided by the workstation environment win be described. In addition, general technology areas which are to be addressed in the Integrated Workstation functional requirements will be discussed.

Wood, R.T.; Knee, H.E.; Mullens, J.A.; Munro, J.K. Jr.; Swail, B.K.; Tapp, P.A.

1993-05-01T23:59:59.000Z

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

BWR radiation control: plant demonstration. Volume 2. Appendixes  

SciTech Connect

The first year's progress is presented for a four-year program intended to implement and evaluate BRAC radiation reduction operational guidelines at the Vermont Yankee BWR and to document the results in sufficient detail to provide guidance to other BWR owners. Past operational, chemistry and radiation level data have been reviewed to provide a historical base of reference. Extensive sampling and chemistry monitoring systems have been installed to evaluate plant chemistry status and the effects of program implemented changes. Radiation surveys and piping gamma scans are being performed at targeted locations to quantify radiation level trends and to identify and quantify piping isotopics. Contact radiation levels on the recirculation line at Vermont Yankee have been increasing at a rate of 175 mR/h-EFPY since 1978. A materials survey of feedwater and reactor components in contact with the process liquid has been performed to identify sources of corrosion product release, particularly cobalt and nickel. A feedwater oxygen injection system has been installed to evaluate the effects of oxygen control on feedwater materials corrosion product releases. A baseline performance evaluation of the condensate treatment and reactor water cleanup systems has been completed. Data on organics and ionics at Vermont Yankee have been obtained. A methodology of BWR feedwater system layup during extended outages was developed, and an evaluation performed of layup and startup practices utilized at Vermont Yankee during the fall 1980 and 1981 refueling outages.

Palino, G.F.; Hobart, R.L.; Wall, P.S.; Sawochka, S.G.

1982-11-01T23:59:59.000Z

322

Materials characterization capabilities at DOE Nuclear Weapons Laboratories and Production Plants  

SciTech Connect

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

Pyper, J.W.

1984-06-01T23:59:59.000Z

323

PLC-Based Safety Critical Software Development for Nuclear Power Plants  

E-Print Network (OSTI)

PLC-Based Safety Critical Software Development for Nuclear Power Plants Junbeom Yoo1 , Sungdeok Cha}@kaeri.re.kr Abstract. This paper proposes a PLC(Programmable Logic Controller)-based safety critical software(FBD), a widely used PLC programming language. Finally, we manually refine the FBD programs so that redundant

324

Survey of thermal-hydraulic models of commercial nuclear power plants  

SciTech Connect

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC`s current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

Determan, J.C.; Hendrix, C.E.

1992-12-01T23:59:59.000Z

325

Survey of thermal-hydraulic models of commercial nuclear power plants  

SciTech Connect

A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

Determan, J.C.; Hendrix, C.E.

1992-12-01T23:59:59.000Z

326

A formal software requirements specification method for digital nuclear plant protection systems  

E-Print Network (OSTI)

of Electrical Engineering and Computer Science, Korea Advanced Institute of Science and Technology (KAIST those in aerospace, satellite and nuclear power plants, whose failure could result in danger to human life, property or environment. It is recently becoming more important due to the increase

327

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

328

An evaluation of the dismantling technologies for decommissioning of nuclear power plants  

Science Journals Connector (OSTI)

Abstract This paper is to suggest an evaluation method on the dismantling technologies for decommissioning of nuclear power plants. The parameters of evaluation are performance impacts, site-specific impacts, safety impacts, and cost impacts. The evaluation model was provided and applied for dismantling of a steam generator.

KwanSeong Jeong; ByungSeon Choi; Jeikwon Moon; Dongjun Hyun; JongHwan Lee; IkJune Kim; GeunHo Kim; JaeSeok Seo

2014-01-01T23:59:59.000Z

329

Design issues concerning Iran`s Bushehr nuclear power plant VVER-1000 conversion  

SciTech Connect

On January 8, 1995, the Atomic Energy Organization of Iran (AEOI) signed a contract for $800 million with the Russian Federation Ministry for Atomic Energy (Minatom) to complete Bushehr nuclear power plant (BNPP) unit 1. The agreement called for a Russian VVER-1000/320 pressurized water reactor (PWR) to be successfully installed into the existing German-built BNPP facilities in 5 yr. System design differences, bomb damage, and environmental exposure are key issues with which Minatom must contend in order to fulfill the contract. The AEOI under the Shah of Iran envisioned Bushehr as the first of many nuclear power plants, with Iran achieving 24 GW(electric) by 1993 and 34 GW(electric) by 2000. Kraftwerk Union AG (KWU) began construction of the two-unit plant near the Persian Gulf town of Halileh in 1975. Unit 1 was {approx}80% complete and unit 2 was {approx}50% complete when construction was interrupted by the 1979 Iranian Islamic revolution. Despite repeated AEOI attempts to lure KWU and other companies back to Iran to complete the plant, Western concerns about nuclear proliferation in Iran and repeated bombings of the plant during the 1980-1988 Iran-Iraq war dissuaded Germany from resuming construction.

Carson, C.F. [Lawrence Livermore National Laboratory, CA (United States)

1996-12-31T23:59:59.000Z

330

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

331

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

332

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

SciTech Connect

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

333

EU could go it alone on nuclear fusion plant 29.11.2004 -10:02 CET | By Richard Carter  

E-Print Network (OSTI)

EU could go it alone on nuclear fusion plant 29.11.2004 - 10:02 CET | By Richard Carter The EU research ministers. Talks over the world's first nuclear fusion reactor have stalled because Japan apart, the fusion technique binds atoms together to produce energy. But to produce nuclear fusion

334

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-NUCLEAR 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.

335

France clings to fusion dreams Paris is demanding that Europe go ahead with plans to build a nuclear fusion plant,  

E-Print Network (OSTI)

a nuclear fusion plant, even if it misses out on international funding. Cadarache in the south of France" but cautioned that the ¤10 billion needed was "a significant amount of money". Supporters of nuclear fusion say are in plentiful supply, and fusion reactors would not produce fissile materials that could be used in nuclear

336

The integrated workstation: A common, consistent link between nuclear plant personnel and plant information and computerized resources  

SciTech Connect

The increasing use of computer technology in the US nuclear power industry has greatly expanded the capability to obtain, analyze, and present data about the plant to station personnel. Data concerning a power plant's design, configuration, operational and maintenance histories, and current status, and the information that can be derived from them, provide the link between the plant and plant staff. It is through this information bridge that operations, maintenance and engineering personnel understand and manage plant performance. However, it is necessary to transform the vast quantity of data available from various computer systems and across communications networks into clear, concise, and coherent information. In addition, it is important to organize this information into a consolidated, structured form within an integrated environment so that various users throughout the plant have ready access at their local station to knowledge necessary for their tasks. Thus, integrated workstations are needed to provide the inquired information and proper software tools, in a manner that can be easily understood and used, to the proper users throughout the plant. An effort is underway at the Oak Ridge National Laboratory to address this need by developing Integrated Workstation functional requirements and implementing a limited-scale prototype demonstration. The integrated Workstation requirements will define a flexible, expandable computer environment that permits a tailored implementation of workstation capabilities and facilitates future upgrades to add enhanced applications. The functionality to be supported by the integrated workstation and inherent capabilities to be provided by the workstation environment win be described. In addition, general technology areas which are to be addressed in the Integrated Workstation functional requirements will be discussed.

Wood, R.T.; Knee, H.E.; Mullens, J.A.; Munro, J.K. Jr.; Swail, B.K.; Tapp, P.A.

1993-01-01T23:59:59.000Z

337

Covert plant detection - Excerpt from Nuclear Engineering International (Nov. 2007)  

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

NOVEMBER 2007 NOVEMBER 2007 I N T E R N A T I O N A L 6 www.neimagazine.com [ .ol52 No 640 November 2007 CONTENTS b . . - . 4 First full COL application; Scotland rejects new build; EPR state aid ruling; GNEP swells; U S risk ' urance conditional agreement - . - - - - -- - -- - - s I N T E R N A T I O N A L I COMPANY NEWS 6 The latest company news and contract results Editor: COMMENT > . 12 Developing nations must take the lead on new Editorial Assistants: Tracey Honney Elaine Sneath nuclear build 14 AECL has optimised instrumentation for its ACR-1000 reactor I Group Advertisement Mana Scott Calvin European Sales Executive: Journal Secretary: ' - I . i RADIATION MONITORING & ALARA . % * - 17 lonising radiation for medical diagnosis contributes 90% of the total exposure of the UK population to

338

Nuclear safeguard protocol construction for nuclear power plants using analytic hierarchy process with zero-sum method  

Science Journals Connector (OSTI)

A nuclear safeguard protocol (NSP) is constructed for the nuclear material flow in the operation of nuclear power plants (NPPs). Secure plant operation is one of critical issues against the risk of possible terrorism. The basic event of the related incidents is quantified by the random sampling of the Monte-Carlo method incorporating a zero-sum method. The analytic hierarchy process is developed as the maximum pair values with multiplications which are decided by the matrix-form analysis used to compare five types of NPPs of interest. Using the life cycle of 60 years, the range of the secure operation is between 0.0166000 and 0.0209531 as relative numbers. This means that the highest value in the range of secure power operation is about 1.26 times higher than the lowest one in this study. Consistency in terms of Consistency Index (CI) and Consistency Ratio (CR) is the highest in the 24th and the 54th years. Therefore, the NSP is constructed for successful safe operation.

Taeho Woo

2011-01-01T23:59:59.000Z

339

Next Generation Nuclear Plant Defense-in-Depth Approach  

SciTech Connect

The purpose of this paper is to (1) document the definition of defense-in-depth and the pproach that will be used to assure that its principles are satisfied for the NGNP project and (2) identify the specific questions proposed for preapplication discussions with the NRC. Defense-in-depth is a safety philosophy in which multiple lines of defense and conservative design and evaluation methods are applied to assure the safety of the public. The philosophy is also intended to deliver a design that is tolerant to uncertainties in knowledge of plant behavior, component reliability or operator performance that might compromise safety. This paper includes a review of the regulatory foundation for defense-in-depth, a definition of defense-in-depth that is appropriate for advanced reactor designs based on High Temperature Gas-cooled Reactor (HTGR) technology, and an explanation of how this safety philosophy is achieved in the NGNP.

Edward G. Wallace; Karl N. Fleming; Edward M. Burns

2009-12-01T23:59:59.000Z

340

The Relationship of Science Knowledge, Attitude and Decision Making on Socio-scientific Issues: The Case Study of Students’ Debates on a Nuclear Power Plant in Korea  

Science Journals Connector (OSTI)

In line with their attitude toward radioactivity, the students felt that accidents in nuclear power plants would become more frequent. They stated that nuclear power plants are not safe from terrorism or natural ...

Hunkoog Jho; Hye-Gyoung Yoon; Mijung Kim

2014-05-01T23:59:59.000Z

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

Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site  

Science Journals Connector (OSTI)

Equipping new-generation nuclear power plants with passive means for controlling unanticipated ... design for the site of the Leningradskaya nuclear power plant. An urgent problem is to obtain ... validation of t...

A. M. Bakhmet’ev; M. A. Bol’shukhin; V. V. Vakhrushev; A. M. Khizbullin…

2009-03-01T23:59:59.000Z

342

High Energy Utilization, Co-Generation Nuclear power Plants With Static Energy Conversion  

SciTech Connect

In addition to being cost effective, very small nuclear power plants with static energy conversion could meet the needs and the energy mix in underdeveloped countries and remote communities, which may include electricity, residential and industrial space heating, seawater desalination, and/or high temperature process heat or steam for industrial uses. These plants are also an attractive option in naval, marine, and undersea applications, when the absence of a sound signature is highly desirable. An Analysis is performed of Gas Cooled Reactor (CGR) and Liquid Metal Cooled Reactor (LMR), very small nuclear power plants with static energy conversion, using a combination of options. These include Alkali Metal Thermal-to-Electric Converters (AMTECs) and both single segment and segmented thermoelectric converters. The total energy utilization of these plants exceeds 88%. It includes the fraction of the reactor's thermal power converted into electricity and delivered to the Grid at 6.6 kVA and those used for residential and industrial space heating at {approx}370 K, seawater desalination at 400 K, and/or high temperature process heat or steam at {approx}850 K. In addition to its inherently high reliability, modularity, low maintenance and redundancy, static energy conversion used in the present study could deliver electricity to the Grid at a net efficiency of 29.5%. A LMR plant delivers 2-3 times the fraction of the reactor thermal power converted into electricity in a GCR plant, but could not provide for both seawater desalination and high temperature process heat/steam concurrently, which is possible in GCR plants. The fraction of the reactor's thermal power used for non-electrical power generation in a GCR plant is {approx} 10 - 15% higher than in a LMR plant. (authors)

El-Genk, Mohamed S.; Tournier, Jean-Michel P. [Institute for Space and Nuclear Power Studies and Chemical and Nuclear Engineering Department, The University of New Mexico, Albuquerque, NM (United States)

2002-07-01T23:59:59.000Z

343

Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson 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. 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. H. B. Robinson was selected as one of a series of plants 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 NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant.

Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States); Garner, L.W. [Nuclear Regulatory Commission, Washington, DC (United States)

1993-08-01T23:59:59.000Z

344

Auxiliary feedwater system risk-based inspection guide for the McGuire 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. 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. McGuire was selected as one of a series of plants 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 NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant.

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

1994-05-01T23:59:59.000Z

345

Auxiliary feedwater system risk-based inspection guide for the South Texas Project 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. 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

346

Nuclear-power-plant perimeter-intrusion alarm systems  

SciTech Connect

Timely intercept of an intruder requires the examination of perimeter barriers and sensors in terms of reliable detection, immediate assessment and prompt response provisions. Perimeter security equipment and operations must at the same time meet the requirements of the Code of Federal Regulations, 10 CFR 73.55 with some attention to the performance and testing figures of Nuclear Regulatory Guide 5.44, Revision 2, May 1980. A baseline system is defined which recommends a general approach to implementing perimeter security elements: barriers, lighting, intrusion detection, alarm assessment. The baseline approach emphasizes cost/effectiveness achieved by detector layering and logic processing of alarm signals to produce reliable alarms and low nuisance alarm rates. A cost benefit of layering along with video assessment is reduction in operating expense. The concept of layering is also shown to minimize testing costs where detectability performance as suggested by Regulatory Guide 5.44 is to be performed. Synthesis of the perimeter intrusion alarm system and limited testing of CCTV and Video Motion Detectors (VMD), were performed at E-Systems, Greenville Division, Greenville, Texas during 1981.

Halsey, D.J.

1982-04-01T23:59:59.000Z

347

Experience in operating and upgrading the No. 5 unit of the Novovoronezh nuclear power plant – practical base for developing a reliable source of nuclear energy  

Science Journals Connector (OSTI)

The No. 5 unit of the Novovoronezh nuclear power plant, starting commercial operations on September 26, 1980, is the first power-generating unit with a 1000 MW VVER in our country. The assimilation of its power g...

I. L. Vitkovskii

2011-03-01T23:59:59.000Z

348

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

349

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

350

Redundant Sensor Calibration and Estimation for Monitoring and Control of Nuclear Power Plants Xin Jin, Asok Ray and Robert M. Edwards  

E-Print Network (OSTI)

Redundant Sensor Calibration and Estimation for Monitoring and Control of Nuclear Power Plants Xin@engr.psu.edu INTRODUCTION Performance, reliability and safety of nuclear power plants depend upon validity and accuracy are installed with redundancy in nuclear power plants. Redundancy can be classified into two groups: direct

Ray, Asok

351

Applications of neural networks to monitoring and decision making in the operation of nuclear power plants. Summary  

SciTech Connect

Application of neural networks to monitoring and decision making in the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (1) diagnosing specific abnormal conditions or problems in nuclear power plants, (2) detection of the change of mode of operation of the plant, (3) validating signals coming from detectors, (4) review of ``noise`` data from TVA`s Sequoyah Nuclear Power Plant, and (5) examination of the NRC`s database of ``Letter Event Reports`` for correlation of sequences of events in the reported incidents. Each of these projects and its status are described briefly in this paper. This broad based program has as its objective the definition of the state-of-the-art in using neural networks to enhance the performance of commercial nuclear power plants.

Uhrig, R.E. [Tennessee Univ., Knoxville, TN (United States)]|[Oak Ridge National Lab., TN (United States)

1990-12-31T23:59:59.000Z

352

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

Science Journals Connector (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.

2010-01-01T23:59:59.000Z

353

Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant  

SciTech Connect

The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey.

Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

2006-05-01T23:59:59.000Z

354

Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants  

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. 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. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants 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 Byron/Braidwood plants. 23 refs., 1 fig., 1 tab.

Moffitt, N.E.; Gore, B.F.: Vo, T.V. (Pacific Northwest Lab., Richland, WA (USA))

1991-07-01T23:59:59.000Z

355

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

356

Release of Pu Isotopes from the Fukushima Daiichi Nuclear Power Plant Accident to the Marine Environment Was Negligible  

Science Journals Connector (OSTI)

Release of Pu Isotopes from the Fukushima Daiichi Nuclear Power Plant Accident to the Marine Environment Was Negligible ... On 11 March 2011, a massive earthquake with a magnitude of M 9.0 occurred in the western North Pacific about 180 km off the Fukushima Daiichi Nuclear Power Plant (FDNPP) in the northeast coast of Japan and it was followed by gigantic tsunami. ... Since the accident at Fukushima Daiichi Nuclear Power Plant (1FNPP), significant levels of anthropogenic radionuclides have been detected in seabed sediments off the east coast of Japan. ...

Wenting Bu; Miho Fukuda; Jian Zheng; Tatsuo Aono; Takashi Ishimaru; Jota Kanda; Guosheng Yang; Keiko Tagami; Shigeo Uchida; Qiuju Guo; Masatoshi Yamada

2014-07-22T23:59:59.000Z

357

Summary and analysis of public comments on NUREG-1317: Regulatory options for nuclear plant license renewal: Final report  

SciTech Connect

On August 29, 1988, the US Nuclear Regulatory Commission (NRC) issued an Advance Notice of Proposed Rulemaking on nuclear plant license renewal and solicited public comments on NUREG-1317, ''Regulatory Options for Nuclear Plant License Renewal.'' NUREG-1317 presents a discussion of fifteen topics involving technical, environmental, and procedural issues and poses a set of related questions. As part of its ongoing task for the NRC, The MITRE Corporation has summarized and analyzed the public comments received. Fifty-three written comments were received. Of these, 83 percent were from nuclear industry representatives; the remaining comments represented federal and state agencies, public interest groups, and a private citizen.

Ligon, D.M.; Seth, S.S.

1989-03-01T23:59:59.000Z

358

Aerial radiation monitoring around the Fukushima Dai-ichi nuclear power plant using an unmanned helicopter  

Science Journals Connector (OSTI)

Abstract The Great East Japan Earthquake on March 11, 2011 generated a series of large tsunami that seriously damaged the Fukushima Dai-ichi Nuclear Power Plant (FDNPP), which resulted in the release of radioactive materials into the environment. To provide further details regarding the distribution of air dose rate and the distribution of radioactive cesium (134Cs and 137Cs) deposition on the ground within a radius of approximately 5 km from the nuclear power plant, we carried out measurements using an unmanned helicopter equipped with a radiation detection system. The distribution of the air dose rate at a height of 1 m above the ground and the radioactive cesium deposition on the ground was calculated. Accordingly, the footprint of radioactive plumes that extended from the FDNPP was illustrated.

Yukihisa Sanada; Tatsuo Torii

2015-01-01T23:59:59.000Z

359

Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants  

SciTech Connect

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 [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Lin, Guang [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Crawford, Susan L. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Konomi, Bledar A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Braatz, Brett G. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Coble, Jamie B. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Shumaker, Brent [Analysis and Measurement Services Corp., Knoxville, TN (United States); Hashemian, Hash [Analysis and Measurement Services Corp., Knoxville, TN (United States)

2013-09-01T23:59:59.000Z

360

Nuclear power plant on-line sensor calibration monitoring implementation issues  

Science Journals Connector (OSTI)

The use of empirical models for on-line monitoring (OLM) of safety-critical instrumentation for calibration reduction has been investigated for over a decade. To help support the regulatory review of possible licence amendments for US nuclear power plants, a series of three NUREG/CRs is being developed for the US Nuclear Regulatory Commission. The third of these volumes, entitled 'Limiting Case Studies', presents the results of applying OLM models to a wide variety of plant data. Specifically, Volume III summarises seven case studies investigating the effects of model development and data assumptions on model performance, and offers recommendations for identifying and handling these limiting cases. This paper discusses the seven case studies. Although this study is not an exhaustive review of the many issues in OLM system development, it provides a base set of considerations that must be accounted for and a method for testing these considerations with other model architectures.

Jamie Garvey; Dustin Garvey; Rebecca Seibert; J. Wesley Hines

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "yankee nuclear plant" from the National Library of EnergyBeta (NLEBeta).
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361

Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants  

SciTech Connect

This report describes 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.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

2014-04-30T23:59:59.000Z

362

Devices and methods for managing noncombustible gasses in nuclear power plants  

DOE Patents (OSTI)

Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.

Marquino, Wayne; Moen, Stephan C; Wachowiak, Richard M; Gels, John L; Diaz-Quiroz, Jesus; Burns, Jr., John C

2014-12-23T23:59:59.000Z

363

A survey of repair practices for nuclear power plant containment metallic pressure boundaries  

SciTech Connect

The Nuclear Regulatory Commission has initiated a program at the Oak Ridge National Laboratory to provide assistance in their assessment of the effects of potential degradation on the structural integrity and leaktightness of metal containment vessels and steel liners of concrete containments in nuclear power plants. One of the program objectives is to identify repair practices for restoring metallic containment pressure boundary components that have been damaged or degraded in service. This report presents issues associated with inservice condition assessments and continued service evaluations and identifies the rules and requirements for the repair and replacement of nonconforming containment pressure boundary components by welding or metal removal. Discussion topics include base and welding materials, welding procedure and performance qualifications, inspection techniques, testing methods, acceptance criteria, and documentation requirements necessary for making acceptable repairs and replacements so that the plant can be returned to a safe operating condition.

Oland, C.B.; Naus, D.J. [Oak Ridge National Lab., TN (United States)

1998-05-01T23:59:59.000Z

364

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

SciTech Connect

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

Doctor, Steven R.

2009-04-01T23:59:59.000Z

365

Survey of insulation used in nuclear power plants and the potential for debris generation. Technical report  

SciTech Connect

In support of Unresolved Safety Issue A-43, 'Containment Emergency Sump Performance,' 11 nuclear power plants representative of different U.S. reactor manufacturers and architect-engineers were surveyed to identify and document the types and amounts of insulation used, location within containment, components insulated, material characteristics, and methods of installation and attachment. A preliminary assessment was made of the potential effects of insulation debris generated as the result of a loss-of-coolant accident (pipe break).

Reyer, R.; Gahan, E.; Riddington, J.W.

1981-10-01T23:59:59.000Z

366

Dose-projection considerations for emergency conditions at nuclear power plants  

SciTech Connect

The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided.

Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

1983-05-01T23:59:59.000Z

367

Reviewing PSA-based analyses to modify technical specifications at nuclear power plants  

SciTech Connect

Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant`s probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed.

Samanta, P.K.; Martinez-Guridi, G. [Brookhaven National Lab., Upton, NY (United States); Vesely, W.E. [Science Applications International Corporation, Dublin, OH (United States)

1995-12-01T23:59:59.000Z

368

Seamless remote dismantling system for heavy and highly radioactive components of Korean nuclear power plants  

Science Journals Connector (OSTI)

Abstract A seamless remote system for dismantling heavy and highly radioactive components during the decommissioning of a nuclear power plant is proposed. The originality of the dismantling system is in its ability to handle all the processes involved in the dismantling of major components of a nuclear power plant without external intervention. Previous types of dismantling equipment were designed for specific components or a particular process, which required time consuming and risky equipment replacement tasks between different processes. The proposed dismantling system was designed and verified by simulation of all the processes for dismantling the major components of a Korean nuclear power plant. Several challenges such as working in confined spaces and with complex movement lines as well as interference between components were overcome. The proposed system is capable of handling all the dismantling processes without equipment replacement tasks or the need to drain the reactor pool. The system is expected to considerably reduce the time and cost of the entire decommissioning process while also improving safety.

Dongjun Hyun; Sung-Uk Lee; Yong-Chil Seo; Geun-Ho Kim; Jonghwan Lee; Kwan-Seong Jeong; Byung-Seon Choi; Jei-Kwon Moon

2014-01-01T23:59:59.000Z

369

Informing the next nuclear generation - how does the Ginna plant branch do it?  

SciTech Connect

Most of us are familiar with the latest advertising phrase, ``Our children are our future.`` This phrase has been used in so many instances - from concerns about waste, Social Security, and the federal deficit to drug abuse and violence. One more area can be added to the list and advertised nuclear power. Since the establishment of the Ginna plant branch (GPB) in 1992, our target audience has been the next nuclear generation (our children), but our vehicle for dissemination has been the current generation (the adults). Have you ever thought about how often your opinions affect the children you come in contact with? One of GPB`s goals is to provide as much information as possible to teachers, neighbors, and civic organizations of our community so that there is a nuclear future that can be carried on by the next generation.

Saavedra, A. [Rochester Gas and Electric Corporation, Ontario, NY (United States)

1995-12-31T23:59:59.000Z

370

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

371

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

372

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

373

Numerical simulation of the thermal conditions in a sea bay water area used for water supply to nuclear power plants  

SciTech Connect

Consideration is given to the numerical simulation of the thermal conditions in sea water areas used for both water supply to and dissipation of low-grade heat from a nuclear power plant on the shore of a sea bay.

Sokolov, A. S. [JSC 'B. E. Vedeneev All-Russia Research Institute of Hydraulic Engineering (VNIIG)' (Russian Federation)] [JSC 'B. E. Vedeneev All-Russia Research Institute of Hydraulic Engineering (VNIIG)' (Russian Federation)

2013-07-15T23:59:59.000Z

374

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

375

Numerical simulation of propagation of radioactive pollution in the ocean from the Fukushima Dai-ichi nuclear power plant  

Science Journals Connector (OSTI)

Numerical simulation of the large-scale horizontal mixing and transport of radioactive water from the Fukushima Dai-ichi nuclear power plant (NPP) (141°02? E, 37°27? N, east coast of Honshu Island, Japan) and ...

S. V. Prants; M. Yu. Uleysky; M. V. Budyansky

2011-08-01T23:59:59.000Z

376

Aging Management Guideline for commercial nuclear power plants: Power and distribution transformers  

SciTech Connect

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG 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 which 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. [Sandia National Labs., Albuquerque, NM (United States)

1994-05-01T23:59:59.000Z

377

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

378

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

379

4 - Hydrogen production in conventional, bio-based and nuclear power plants  

Science Journals Connector (OSTI)

Abstract: A hydrogen economy advent cannot be based on the current processes and plants, but will need to take advantage of distributed generation systems and to exploit the potential of hydrogen generation in synergy with large electricity or heat generation plants, provided their CO2 emissions are intrinsically low or are abated by means of carbon capture and/or sequestration (CCS) systems. This chapter will focus on real carbon-based energy process appliances and new business cases. A section is also devoted to CCS technologies. Finally, the simultaneous production of hydrogen and power from nuclear plants will be reviewed from a technical point of view, and its future potential impact on the hydrogen economy will be evaluated.

D. Fino

2014-01-01T23:59:59.000Z

380

Flow Noise Prediction and Control in Steam Piping Systems for Nuclear Power Plants  

Science Journals Connector (OSTI)

The flow noise of steam in pipe lines particularly in power plants is a major noise source and contributor to OSHA noise problems. The ability to predict flow noise levels is vital to efficient and economical noise control. Octave?band measurements of flow noise in the main steam piping system of a nuclear power plant were made. To determine the effect of velocity measurements were conducted for a wide range of velocities during plant start?up. Results in the form of plots of measured flow noise as a function of velocity were compared with limited data that have been recently published. An empirical formula for prediction of flow noise and corresponding design techniques for control of noise by proper pipe sizing have been developed. Alternate methods of noise control are reviewed.

F. H. Brittain; S. W. Giampapa

1973-01-01T23:59:59.000Z

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

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

382

AGE-RELATED DEGRADATION OF NUCLEAR POWER PLANT STRUCTURES AND COMPONENTS.  

SciTech Connect

This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what are the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk.

BRAVERMAN,J.

1999-03-29T23:59:59.000Z

383

Age-Related Degradation of Nuclear Power Plant Structures and Components  

SciTech Connect

This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what was the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk.

Braverman, J.; Chang, T.-Y.; Chokshi, N.; Hofmayer, C.; Morante, R.; Shteyngart, S.

1999-03-29T23:59:59.000Z

384

Aging Management Guideline for commercial nuclear power plants: Electrical switchgear. Final report  

SciTech Connect

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG 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 which 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.; Schuler, K. [Ogden Environmental and Energy Services Co., Inc., Blue Bell, PA (United States)

1993-07-01T23:59:59.000Z

385

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

SciTech Connect

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

386

Operational air pollution prediction and doses calculation in case of nuclear emergency at Krško Nuclear Power Plant  

Science Journals Connector (OSTI)

The paper presents fully operational air pollution prediction and doses calculation system working in 2/24/7/365 mode for more than a decade in Krško Nuclear Power Plant (NPP). Krško NPP lies in complex terrain in Slovenia very close to Croatia border. A dedicated software is available for detailed estimation of possible radioactive emission (source term). This part of the procedure is used by trained NPP operators and then automatically coupled with dilution coefficients to obtain radionuclide air pollution concentrations. As radioactive material causes dose also with distant cloud shine not only by direct touch or inhalation, special procedure is implemented for dose estimation. We present in detail our algorithm for distant cloud shine estimation based on dilution coefficients calculation. The paper concludes by stressing the importance of correct air pollution prediction with best possible modelling techniques where achieving time and space accurate modelling is required for proper population protection.

Primož Mlakar; Marija Zlata Božnar; Borut Breznik

2014-01-01T23:59:59.000Z

387

Evaluation criteria and procedure for nuclear power plant temporary loads/temporary conditions  

SciTech Connect

Operating nuclear power plants frequently encounter temporary loads/temporary conditions in plant normal operation and maintenance (O and M). The most obvious examples are installation of temporary shielding and scaffolding, or removal of certain supports, to facilitate plant refueling and maintenance outage activities. Short-term operability calls such as those due to snubber failures or unanticipated transients also create temporary loads/temporary conditions. These temporary situations often generate loads that are outside the original plant design basis. Consequently, separate evaluations are needed to ensure that plant structures, systems and components (SSCs) maintain their integrity and functionality while these temporary loads are active. Also, the temporary structures and components need to be evaluated to ensure their integrity during the temporary duration of use. Three types of approaches are normally adopted either individually or in combination to perform needed evaluations: relax the design allowables, use a more refined analysis model but retain the design basis acceptance criteria, or offset temporary loads by eliminating or reducing part of the design basis loads based on short duration considerations. This paper reviews temporary loading/temporary condition issues and the current industry criteria and procedures proposed in dealing with these issues. Where appropriate, regulatory positions on temporary loads/temporary conditions are discussed.

Tang, H.T. [Electric Power Research Inst., Palo Alto, CA (United States); Minichiello, J.C. [Commonwealth Edison Co., Downers Grove, IL (United States); Olson, D.E. [Sargent and Lundy, Chicago, IL (United States)

1996-12-01T23:59:59.000Z

388

An Accelerated Aging Analysis Method Based on Local Data for Components and Materials in Nuclear Power Plants  

Science Journals Connector (OSTI)

In nuclear power plants, accelerated aging of certain components can lead to reduction of their service life, which has potential impact on the safety and economics of the whole plant. In order to effectively manage the accelerated aging of critical ... Keywords: accelerated aging, life estimation, accelerating factor, performance degradation data

Zeng Yuyun; Liu Jingquan; Huang Weigang

2013-07-01T23:59:59.000Z

389

Feasibility study of a small-sized nuclear heat-only plant dedicated to desalination in the UAE  

Science Journals Connector (OSTI)

Abstract The development of a small-sized nuclear heat-only plant with maximized safety features dedicated to seawater thermal desalination was proposed to address both a serious water crisis and nuclear safety issues, which continue to be perennial problems. In this study, the feasibility of a dedicated nuclear heat-only desalination system for a target country was evaluated in comparison with a target nuclear thermal desalination system. First, the target country was selected, and its current energy and desalination status was investigated. The suitable nuclear desalination options for the target country were then selected. Finally, using corresponding analysis tools, performance and economic analyses were conducted for a dedicated nuclear heat-only desalination system and the target nuclear thermal desalination system. The results of the analyses indicate that operating the small-sized nuclear heat-only plant at low pressures coupled with a seawater thermal desalination plant will considerably improve both the safety and economy without a significant loss in desalination performance. In conclusion, the proposed dedicated nuclear heat-only desalination system is expected to have high potential for solving both problems.

Yong Hun Jung; Yong Hoon Jeong; Jinyoung Choi; Andhika F. Wibisono; Jeong Ik Lee; Hee Cheon No

2014-01-01T23:59:59.000Z

390

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.

Farfan, E.

2009-09-30T23:59:59.000Z

391

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.

Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

2009-11-09T23:59:59.000Z

392

Protection of Nuclear Plants Against Vehicular Bombs Via Full Spectrum Risk Assessment  

SciTech Connect

A more urgent need now exists since 9/11 to protect vital assets at nuclear plants from physical security threats. Any approach to successful defense must result in the best possible risk profile , while also performing this defense against credible threats within the context of limited personnel and materiel resources. Engineered solutions need to be well thought out, and take advantage of each plant's available organic strengths and opportunities. A robust, well trained/equipped highly motivated protective force will help reduce concerns where there are weaknesses making the plant vulnerable to threats. A thorough risk assessment takes into account the proper combination of both deterministic and probabilistic application of resources as a most advantageous approach; this is postulated to be development of integrated protection methods and plans, which blend solid engineering design with the highest caliber of protection forces. By setting a clear and ambitious objective to shield the nuclear assets with this type of dynamic full spectrum defense in depth, the risk of harm-breach or likelihood of any opponent's threat being realized should be reduced to the lowest practicable levels.

Campagna, M. S.; Sawruk, W.

2003-02-25T23:59:59.000Z

393

A practical approach to risk-based inservice inspection in U.S. nuclear power plants  

SciTech Connect

To provide guidelines for practical implementation of risk-based ISI, EPRI sponsored work to develop evaluation procedures and criteria for defining risk-based inservice inspection programs for nuclear power plant piping. These procedures and criteria include efficient means to identify risk significant piping segments, inspection locations, and available inspection techniques. These procedures were applied in a pilot study to assess the feasibility of successfully implementing risk-based inservice inspection programs at nuclear plants. The results from the pilot study indicate that implementation of risk-based inservice inspection programs can reduce the cost and radiation exposure associated with inservice inspection, while maintaining a high level of safety. The list of references provides additional details of these procedures and plant-specific applications. Also, an EPRI technical report has been published to document these procedures. Software has been developed to support and fully document this procedure. Additional development is adding an expert system to the present data base system. The approach compares well to approaches used (or being considered) in other industries and can easily be adapted to these other industries and to address economic and personnel safety in addition to public safety measures.

Gosselin, S.R. [Electric Power Research Inst., Charlotte, NC (United States); Gamble, R. [Sartrex Corp., Rockville, MD (United States); Dimitrijevic, V.B.; O`Regan, P.J.; Chapman, J.R. [Yankee Atomic Electric Co., Bolton, MS (United States)

1996-12-01T23:59:59.000Z

394

An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin Jin, Robert M. Edwards and Asok Ray  

E-Print Network (OSTI)

An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin.edu INTRODUCTION Nuclear Power Plants (NPPs) are complex systems with many variables that require adjustment to the NPP. METHODOLOGY This proposed integrated scheme consists of three inter-related subsystems: Nuclear

Ray, Asok

395

Formation of hot particles during the Chernobyl nuclear power plant accident  

SciTech Connect

The oxidation of irradiated Chernobyl nuclear fuel at 670 to 1,170 K for 3 to 21 h resulted in its destruction into fine particles, the dispersal composition of which is well described by lognormal distribution regularity. The median radius of the formed particles does not depend on the annealing temperature and decreases with the increase of the annealing period from 10 to 3 {micro}m. Proceeding from the dispersal composition and matrix composition of the Chernobyl hot fuel particles, it can be concluded that the oxidation of nuclear fuel was one of the basic mechanisms of hot fuel particle formation during the accident at the Chernobyl nuclear power plant. With oxidation in air and the dispersal of irradiated oxide nuclear fuel at as low as 670 K, ruthenium, located on the granular borders, is released. Ruthenium is oxidized to volatile RuO{sub 4}, sublimated, and condensed on materials of iron. Nickel and stainless steel can be efficiently used at high temperatures (tested to 1,200 K) for radioruthenium adsorption in accidents and for some technological operations. As the temperature of hot fuel particles annealed in inert media increases from 1,270 to 2,270 K, the relative release of radionuclides increases in the following sequence: cesium isotopes; europium isotopes; cerium isotopes; americium isotopes; and ruthenium, plutonium, and curium isotopes.

Kashparov, V.A.; Ivanov, Y.A.; Zvarisch, S.I.; Protsak, V.P.; Khomutinin, Y.V.; Kurepin, A.D.; Pazukhin, E.M. [Ukrainian Inst. of Agricultural Radiology, Chabany (Ukraine)

1996-05-01T23:59:59.000Z

396

Privatization of the gaseous diffusion plants and impacts on nuclear criticality safety administration  

SciTech Connect

The Energy Policy Act of 1992 created the United States Enrichment Corporation (USEC) on July 1, 1993. The USEC is a government-owned business that leases those Gaseous Diffusion Plant (GDP) facilities at the Portsmouth, Ohio, and Paducah, Kentucky, sites from the U.S. Department of Energy (DOE) that are required for enriching uranium. Lockheed Martin Utility Services is the operating contractor for the USEC-leased facilities. The DOE has retained use of, and regulation over, some facilities and areas at the Portsmouth and Paducah sites for managing legacy wastes and environmental restoration activities. The USEC is regulated by the DOE, but is currently changing to regulation under the U.S. Nuclear Regulatory Commission (NRC). The USEC is also preparing for privatization of the uranium enrichment enterprise. These changes have significantly affected the nuclear criticality safety (NCS) programs at the sites.

D`Aquila, D.M.; Holliday, R.T. [Lockheed Martin Utility Services, Inc., Piketon, OH (United States); Dean, J.C. [Lockheed Martin Utility Services, Inc., Paducah, KY (United States)

1996-12-31T23:59:59.000Z

397

Dynamical safety assessment of hydrogen production nuclear power plants using system dynamics method  

Science Journals Connector (OSTI)

Nuclear power plants for hydrogen production are investigated in the aspect of nuclear safety. The non-linear dynamical safety assessment is introduced for the analysis of the high temperature gas cooled reactor (HTGR) which is used for hydrogen production as well as electricity generation. The dynamical algorithm is adjusted for the safety assessment with an easier and reliable output. A feedback of power increase affects to the temperature decrease. The top event of the event is power and temperature stable. It is affected by the human factor, poison, and some other physical variables. There are several factors including the economic and safety factors which are considered for the reliability of the modelling simulations. Using the system dynamics (SD) method, the event quantification is performed for the event flows, stocks, and feedback by the single and double arrow lines.

Taeho Woo; Soonho Lee

2013-01-01T23:59:59.000Z

398

Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)  

Science Journals Connector (OSTI)

Abstract The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs.

Tae Ho Woo

2013-01-01T23:59:59.000Z

399

21 - Plant life management (PLiM) practices for pressurised heavy water nuclear reactors (PHWR)  

Science Journals Connector (OSTI)

Abstract: The chapter begins with the history of evolution of pressurised heavy water reactor (PHWR) technology in Canada and India and its importance to the three stage Indian Nuclear Power Programme. An insight into the technology and its variants in use in Canada and India has been provided. Regulatory practices followed in India for renewal of operating licences and also for re-licensing of older plants have been highlighted. Several technological advancements, both in the inspection technology and reactor design concepts have been briefly described to give a glimpse of development trends in future.

R.K. Sinha; S.K. Sinha; K.B. Dixit; A.K. Chakrabarty; D.K. Jain

2010-01-01T23:59:59.000Z

400

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

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

Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants  

SciTech Connect

The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act.

O'Brien, J.; Kim, T.J.; Reynolds, S.

1991-08-01T23:59:59.000Z

402

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

403

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

404

Detecting Structural Damage of Nuclear Power Plant by Interactive Data Mining Approach  

SciTech Connect

This paper presents a nonlinear structural damage identification technique, based on an interactive data mining approach, which integrates a human cognitive model in a data mining loop. A mining control agent emulating human analysts is developed, which directly interacts with the data miner, analyzing and verifying the output of the data miner and controlling the data mining process. Additionally, an artificial neural network method, which is adopted as a core component of the proposed interactive data mining method, is evolved by adding a novelty detecting and retraining function for handling complicated nuclear power plant quake-proof data. Plant quake-proof testing data has been applied to the system to show the validation of the proposed method. (author)

Yufei Shu [Japan Atomic Energy Agency (Japan)

2006-07-01T23:59:59.000Z

405

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report  

SciTech Connect

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

John Saurwein

2011-07-15T23:59:59.000Z

406

A Siting Policy for an Acceptable Nuclear Future  

Science Journals Connector (OSTI)

...457 Maine Yankee 781 Richmond 0 Yankee Rowe 176 Pilgrim 670 Montague...Sterling 0 NEPCO 0 (Charlestown) Vermont 524 Yankee 7,730 575 1,900 2,641 2...obtainable. Two sites, Bailly and Vermont Yankee, are hemmed in and more land...

C. C. Burwell; M. J. Ohanian; A. M. Weinberg

1979-06-08T23:59:59.000Z

407

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

408

Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities  

SciTech Connect

The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage managers are concerned with schedule and cost, union workers are concerned with performing work that is commensurate with their trade, and support functions (safety, quality assurance, and radiological controls, etc.) are concerned with performing the work within the plants controls and procedures. Approaches to outage management should be designed to increase the active participation of work groups and managers in making decisions that closed the gap between competing objectives and the potential for error and process inefficiency.

Gregory Weatherby

2012-05-01T23:59:59.000Z

409

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

SciTech Connect

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

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

1995-06-01T23:59:59.000Z

410

Power to the People or Regulatory Ratcheting? Explaining the Success (or Failure) of Attempts to Site Commercial U.S. Nuclear Power Plants: 1954 -19961  

E-Print Network (OSTI)

to Site Commercial U.S. Nuclear Power Plants: 1954 - 19961 7 April 2014 Eric Berndt2 and Daniel P. Aldrich3 Abstract: Between 1954 and 1996, more than 200 nuclear power projects were publically announced to revitalize the nuclear industry in the US and abroad. Keywords: nuclear power, siting decisions, regulatory

411

The Application of Risk-Based Cost-Benefit Analysis in the Assessment of Acceptable Public Safety for Nuclear Power Plants  

Science Journals Connector (OSTI)

In 1982, the U.S. Nuclear Regulatory Commission issued, for public comment, proposed safety goals for commercial nuclear power plants. In an effort to quantitatively evaluate these proposed goals, a methodolog...

Thomas A. Morgan; Alfred J. Unione; George Sauter

1985-01-01T23:59:59.000Z

412

Evaluation and Numerical Simulation of Tsunami for Coastal Nuclear Power Plants of India  

SciTech Connect

Recent tsunami generated on December 26, 2004 due to Sumatra earthquake of magnitude 9.3 resulted in inundation at the various coastal sites of India. The site selection and design of Indian nuclear power plants demand the evaluation of run up and the structural barriers for the coastal plants: Besides it is also desirable to evaluate the early warning system for tsunami-genic earthquakes. The tsunamis originate from submarine faults, underwater volcanic activities, sub-aerial landslides impinging on the sea and submarine landslides. In case of a submarine earthquake-induced tsunami the wave is generated in the fluid domain due to displacement of the seabed. There are three phases of tsunami: generation, propagation, and run-up. Reactor Safety Division (RSD) of Bhabha Atomic Research Centre (BARC), Trombay has initiated computational simulation for all the three phases of tsunami source generation, its propagation and finally run up evaluation for the protection of public life, property and various industrial infrastructures located on the coastal regions of India. These studies could be effectively utilized for design and implementation of early warning system for coastal region of the country apart from catering to the needs of Indian nuclear installations. This paper presents some results of tsunami waves based on different analytical/numerical approaches with shallow water wave theory. (authors)

Sharma, Pavan K.; Singh, R.K.; Ghosh, A.K.; Kushwaha, H.S. [Bhabha Atomic Research Centre-Trombay, Mumbai 400 085 (India)

2006-07-01T23:59:59.000Z

413

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

414

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

SciTech Connect

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

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

2012-04-26T23:59:59.000Z

415

Application of EPRI risk-based inservice inspection procedure to combustion engineering design of nuclear power plant  

SciTech Connect

The EPRI developed risk-based inservice inspection procedure is used to select the elements for inservice inspection on a section of the high pressure safety injection system of the Entergy Operations ANO2 nuclear plant. This plant is the pilot plant in a six utility-eleven plant EPRI tailored collaboration program to apply the general EPRI procedures to Combustion Engineering NSSS designs. The procedure results in a reduction of candidate inspection locations from 14, based on current ASME Section XI rules for B-J welds to 3, based on the risk-based selection criteria.

Lubin, B.T. [ABB Combustion Engineering, Windsor, CT (United States). Nuclear Operations; Fourgerousse, R. [Entergy Operations-ANO2, Russellville, AR (United States)

1996-12-01T23:59:59.000Z

416

"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

417

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

418

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

SciTech Connect

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

419

Analysis of Improved Reference Design for a Nuclear-Driven High Temperature Electrolysis Hydrogen Production Plant  

SciTech Connect

The use of High Temperature Electrolysis (HTE) for the efficient production of hydrogen without the greenhouse gas emissions associated with conventional fossil-fuel hydrogen production techniques has been under investigation at the Idaho National Engineering Laboratory (INL) for the last several years. The activities at the INL have included the development, testing and analysis of large numbers of solid oxide electrolysis cells, and the analyses of potential plant designs for large scale production of hydrogen using an advanced Very-High Temperature Reactor (VHTR) to provide the process heat and electricity to drive the electrolysis process. The results of these system analyses, using the UniSim process analysis software, have shown that the HTE process, when coupled to a VHTR capable of operating at reactor outlet temperatures of 800 °C to 950 °C, has the potential to produce the large quantities of hydrogen needed to meet future energy and transportation needs with hydrogen production efficiencies in excess of 50%. In addition, economic analyses performed on the INL reference plant design, optimized to maximize the hydrogen production rate for a 600 MWt VHTR, have shown that a large nuclear-driven HTE hydrogen production plant can to be economically competitive with conventional hydrogen production processes, particularly when the penalties associated with greenhouse gas emissions are considered. The results of this research led to the selection in 2009 of HTE as the preferred concept in the U.S. Department of Energy (DOE) hydrogen technology down-selection process. However, the down-selection process, along with continued technical assessments at the INL, has resulted in a number of proposed modifications and refinements to improve the original INL reference HTE design. These modifications include changes in plant configuration, operating conditions and individual component designs. This paper describes the resulting new INL reference design and presents results of system analyses performed to optimize the design and to determine required plant performance and operating conditions.

Edwin A. Harvego; James E. O'Brien; Michael G. McKellar

2010-06-01T23:59:59.000Z

420

Application of EKIDESï¼Ergonomic Knowledge Intelligent DEsign Systemï¼to training and ergonomic evaluation of the instrument panel in nuclear power plant.  

E-Print Network (OSTI)

??The public security and working safety are the most important issue for technical engineers operated in nuclear power plant, to face the works with the… (more)

Lin, Tien-chi

2007-01-01T23:59:59.000Z

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421

Measurements of photon ionizing radiation fields in the reactor room of the 4th power-generating unit of the chernobyl nuclear power plant  

Science Journals Connector (OSTI)

A radiation examination of the reactor room of the damaged fourth unit of the Chernobyl nuclear power plant was performed. The most strongly radiating surfaces...

A. G. Volkovich; V. N. Potapov; S. V. Smirnov; L. I. Urutskoev…

2000-03-01T23:59:59.000Z

422

Hydrogen storage for mixed wind–nuclear power plants in the context of a Hydrogen Economy  

Science Journals Connector (OSTI)

A novel methodology for the economic evaluation of hydrogen production and storage for a mixed wind–nuclear power plant considering some new aspects such as residual heat and oxygen utilization is applied in this work. This analysis is completed in the context of a Hydrogen Economy and competitive electricity markets. The simulation of the operation of a combined nuclear–wind–hydrogen system is discussed first, where the selling and buying of electricity, the selling of excess hydrogen and oxygen, and the selling of heat are optimized to maximize profit to the energy producer. The simulation is performed in two phases: in a pre-dispatch phase, the system model is optimized to obtain optimal hydrogen charge levels for the given operational horizons. In the second phase, a real-time dispatch is carried out on an hourly basis to optimize the operation of the system as to maximize profits, following the hydrogen storage levels of the pre-dispatch phase. Based on the operation planning and dispatch results, an economic evaluation is performed to determine the feasibility of the proposed scheme for investment purposes; this evaluation is based on calculations of modified internal rates of return and net present values for a realistic scenario. The results of the present studies demonstrate the feasibility of a hydrogen storage and production system with oxygen and heat utilization for existent nuclear and wind power generation facilities.

Gregor Taljan; Michael Fowler; Claudio Cañizares; Gregor Verbi?

2008-01-01T23:59:59.000Z

423

OECD/NEA study on the economics of the long-term operation of nuclear power plants  

SciTech Connect

The OECD Nuclear Energy Agency (NEA) established the Ad hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (authors)

Lokhov, A.; Cameron, R. [OECD Nuclear Energy Agency, 12, boulevard des Iles, 92130 Issy-les-Moulineaux (France)

2012-07-01T23:59:59.000Z

424

Fair play in energy policy decisions: Procedural fairness, outcome fairness and acceptance of the decision to rebuild nuclear power plants  

Science Journals Connector (OSTI)

To raise public acceptance of new energy policies, promoting the fairness of the outcomes and of the decision-making procedure has been suggested. Very few studies have examined the role of fairness in public acceptance of rebuilding nuclear power plants. Therefore, using a large mail survey, we investigated the public’s acceptance of the decision to rebuild nuclear power plants in Switzerland by 2020. The study examined the influence of procedural fairness and outcome fairness on the acceptance of this decision, as well as other factors such as risk perception and benefit perception. Additionally, we investigated the moderating influence of general attitudes towards nuclear power on the relation between fairness and decision acceptance. Results indicated that outcome fairness strongly increased decision acceptance, along with general attitudes towards nuclear power and perceived economic benefits. Procedural fairness had only a small impact on decision acceptance. The influence of fairness on decision acceptance did not seem to depend on general nuclear attitudes. Our findings imply that, in the case of rebuilding nuclear power plants, perceived benefits and outcome fairness are important determinants of acceptance of the decision, while procedural fairness only has a limited impact.

Vivianne H.M. Visschers; Michael Siegrist

2012-01-01T23:59:59.000Z

425

System Simulation of Nuclear Power Plant by Coupling RELAP5 and Matlab/Simulink  

SciTech Connect

Since RELAP5 code has general and advanced features in thermal-hydraulic computation, it has been widely used in transient and accident safety analysis, experiment planning analysis, and system simulation, etc. So we wish to design, analyze, verify a new Instrumentation And Control (I and C) system of Nuclear Power Plant (NPP) based on the best-estimated code, and even develop our engineering simulator. But because of limited function of simulating control and protection system in RELAP5, it is necessary to expand the function for high efficient, accurate, flexible design and simulation of I and C system. Matlab/Simulink, a scientific computation software, just can compensate the limitation, which is a powerful tool in research and simulation of plant process control. The software is selected as I and C part to be coupled with RELAP5 code to realize system simulation of NPPs. There are two key techniques to be solved. One is the dynamic data exchange, by which Matlab/Simulink receives plant parameters and returns control results. Database is used to communicate the two codes. Accordingly, Dynamic Link Library (DLL) is applied to link database in RELAP5, while DLL and S-Function is applied in Matlab/Simulink. The other problem is synchronization between the two codes for ensuring consistency in global simulation time. Because Matlab/Simulink always computes faster than RELAP5, the simulation time is sent by RELAP5 and received by Matlab/Simulink. A time control subroutine is added into the simulation procedure of Matlab/Simulink to control its simulation advancement. Through these ways, Matlab/Simulink is dynamically coupled with RELAP5. Thus, in Matlab/Simulink, we can freely design control and protection logic of NPPs and test it with best-estimated plant model feedback. A test will be shown to illuminate that results of coupling calculation are nearly the same with one of single RELAP5 with control logic. In practice, a real Pressurized Water Reactor (PWR) is modeled by RELAP5 code, and its main control and protection system is duplicated by Matlab/Simulink. Some steady states and transients are calculated under control of these I and C systems, and the results are compared with the plant test curves. The application showed that it can do exact system simulation of NPPs by coupling RELAP5 and Matlab/Simulink. This paper will mainly focus on the coupling method, plant thermal-hydraulic model, main control logics, test and application results. (authors)

Meng Lin; Dong Hou; Zhihong Xu; Yanhua Yang; Ronghua Zhang [Shanghai Jiao Tong University, Shanghai, 200030 (China)

2006-07-01T23:59:59.000Z

426

Radioactive contamination of fishes in lake and streams impacted by the Fukushima nuclear power plant accident  

Science Journals Connector (OSTI)

Abstract The Fukushima Daiichi Nuclear Power Plant (FDNPP) accident in March 2011 emitted radioactive substances into the environment, contaminating a wide array of organisms including fishes. We found higher concentrations of radioactive cesium (137Cs) in brown trout (Salmo trutta) than in rainbow trout (Oncorhynchus nerka), and 137Cs concentrations in brown trout were higher in a lake than in a stream. Our analyses indicated that these differences were primarily due to differences in diet, but that habitat also had an effect. Radiocesium concentrations (137Cs) in stream charr (Salvelinus leucomaenis) were higher in regions with more concentrated aerial activity and in older fish. These results were also attributed to dietary and habitat differences. Preserving uncontaminated areas by remediating soils and releasing uncontaminated fish would help restore this popular fishing area but would require a significant effort, followed by a waiting period to allow activity concentrations to fall below the threshold limits for consumption.

Mayumi Yoshimura; Tetsuya Yokoduka

2014-01-01T23:59:59.000Z

427

A Study on a Hybrid Approach for Diagnosing Faults in Nuclear Power Plant  

SciTech Connect

Proper and rapid identification of malfunctions is of premier importance for the safe operation of Nuclear Power Plants (NPP). Many monitoring or/and diagnosis methodologies based on artificial and computational intelligence have been proposed to aid operator to understand system problems, perform trouble-shooting action and reduce human error under serious pressure. However, because no single method is adequate to handle all requirements for diagnostic system, hybrid approaches where different methods work in conjunction to solve parts of the problem interest researchers greatly. In this study, Multilevel Flow Models (MFM) and Artificial Neural Network (ANN) are proposed and employed to develop a fault diagnosis system with the intention of improving the success rate of recognition on the one hand, and improving the understandability of diagnostic process and results on the other hand. Several simulation cases were conducted for evaluating the performance of the proposed diagnosis system. The simulation results validated the effectiveness of the proposed hybrid approach. (authors)

Yang, M.; Zhang, Z.J.; Peng, M.J.; Yan, S.Y.; Wang, H. [Harbin Engineering University, Harbin (China); Ouyang, J. [Graduate School of Energy Science, Kyoto University, Sakyo-ku, Kyoto 606-8501 (Japan)

2006-07-01T23:59:59.000Z

428

Minimization of formation of wastes from the operation of Czechoslovak nuclear power plants  

SciTech Connect

The problem of generation of liquid radioactive wastes at VVER 440 reactor type nuclear power plants at Jaslovske Bohunice, and Dukovany is discussed. Treatment processes at the NPPs are described. The process during which the operating liquid radioactive wastes emerge is analyzed and the major contributors are identified. The technical approaches to the optimization of the performance of the purification stations that have been implemented at the NPPs with the aim to reduce the generation of radioactive wastes are outlined. The basic results of investigation into the potential of membrane processes are given, as are the results of pilot scale experiments concerned with the use of reverse osmosis in the purification of selected water streams. Attention is also devoted to technical solutions that have been introduced in the design of the Temelin NPP. These solutions are based on the acquired experience and recommendations of foreign experts.

Stepanek, J.; Mohyla, O. [DIAMO, Prague (Czech Republic); Kniz, I.; Zboray, L. [Nuclear Power Plant, Jaslovske Bohunice (Slovakia); Cada, K.; Wild, J. [Nuclear Power Plant, Dukovany (Czech Republic); Seifert, P. [Nuclear Power Plant, Temelin (Czech Republic); Lastovicka, Z. [Energoproject Prague (Czech Republic)

1993-12-31T23:59:59.000Z

429

Integrated Diagnostic and Prognostic Tools for Residual Life Estimation in Aging Nuclear Power Plant Components  

SciTech Connect

Recent events in Japan have focused renewed attention on the safe operation of light water reactor (LWR) nuclear power plants (NPPs). A central issue in safe, long-term operations of existing and planned NPPs is the early detection and monitoring of significant materials degradation. Materials aging and degradation in passive components is expected to be the key factor in determining the operational life of an NPP and may limit long-term operations in the current LWR fleet. Methods for detecting and assessing the degradation state in NPP structural materials, followed by approaches to estimate the remaining useful life (RUL) of the component, are therefore necessary for safe, long-term operations. This paper explores advanced diagnostic and prognostic approaches to detecting material degradation, and then determining RUL given the current material state.

Ramuhalli, Pradeep; Meyer, Ryan M.; Bond, Leonard J.; Griffin, Jeffrey W.; Henager, Charles H.

2011-06-01T23:59:59.000Z

430

Human-centered HMI design to support cognitive process of operators in nuclear power plants  

SciTech Connect

In this study, an operation advisory system to aid cognitive process of operators is proposed for advanced main control rooms (MCRs) in future nuclear power plants (NPPs). As MCRs are fully digitalized and designed based on computer technologies, MCRs have much evolved by improving human-machine interface (HMI) design and by adapting automation or support systems for helping operator's convenient operation and maintenance. Various kinds of support systems for operators are developed or developing for advanced MCRs. The proposed system is suggesting a design basis about 'What kinds of support systems are most efficient and necessary for MCR operators ' and 'how to use them together.' In this paper, the operator's operation processes are analyzed based on a human cognitive process model and appropriate support systems that support each activity of the human cognitive process are suggested. Also, the proposed support system is evaluated using Bayesian belief network model and human error probabilities in order to estimate its effect. (authors)

Lee, S. J.; Seong, P. H. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

2006-07-01T23:59:59.000Z

431

Recommendations for damping and treatment of modeling uncertainty in seismic analysis of CANDU nuclear power plant  

SciTech Connect

The seismic analysis of the CANDU nuclear power plant is governed by Canadian Standard series N289. However, the dynamic analysis of some equipment and system such as the CANDU reactor and fueling machine must treat unique components not directly covered by the broad recommendations of these standards. This paper looks at the damping values and treatment of modeling uncertainty recommended by CSA N289.3, the current state of knowledge and expert opinion as reflected in several current standards, testing results, and the unique aspects of the CANDU system. Damping values are recommended for the component parts of the CANDU reactor and fueling machine system: reactor building, calandria vault, calandria, fuel channel, pressure tube, fueling machine and support structure. Recommendations for treatment of modeling and other uncertainties are also presented.

Usmani, S.A. [Atomic Energy of Canada, Ltd., Mississauga, Ontario (Canada); Baughman, P.D. [EQE International, Stratham, NH (United States)

1996-12-01T23:59:59.000Z

432

Historical Exposures to Chemicals at the Rocky Flats Nuclear Weapons Plant: A Pilot Retrospective Exposure Assessment  

SciTech Connect

In a mortality study of white males who had worked at the Rocky Flats Nuclear Weapons Plant between 1952 and 1979, an increased number of deaths from benign and unspecified intracranial neoplasms was found. A case-control study nested within this cohort investigated the hypothesis that an association existed between brain tumor death and exposure to either internally deposited plutonium or external ionizing radiation. There was no statistically significant association found between estimated radiation exposure from internally deposited plutonium and the development of brain tumors. Exposure by job or work area showed no significant difference between the cohort and the control groups. An update of the study found elevated risk estimates for (1) all lymphopoietic neoplasms, and (2) all causes of death in employees with body burdens greater than or equal to two nanocuries of plutonium. There was an excess of brain tumors for the entire cohort. Similar cohort studies conducted on worker populations from other plutonium handling facilities have not yet shown any elevated risks for brain tumors. Historically, the Rocky Flats Nuclear Weapons Plant used large quantities of chemicals in their production operations. The use of solvents, particularly carbon tetrachloride, was unique to Rocky Flats. No investigation of the possible confounding effects of chemical exposures was done in the initial studies. The objectives of the present study are to (1) investigate the history of chemical use at the Rocky Flats facility; (2) locate and analyze chemical monitoring information in order to assess employee exposure to the chemicals that were used in the highest volume; and (3) determine the feasibility of establishing a chemical exposure assessment model that could be used in future epidemiology studies.

Janeen Denise Robertson

1999-02-01T23:59:59.000Z

433

An experiment for urban energy autonomy in Seoul: The One ‘Less’ Nuclear Power Plant policy  

Science Journals Connector (OSTI)

Abstract This study examines an experiment in energy self-sufficiency in Seoul, Republic of Korea, through a particular energy policy called the One Less Nuclear Power Plant (OLNPP) policy. We define an urban energy experiment as a purposive intervention for energy transition from an energy system based on nuclear and fossil fuels to one based on renewable energy and energy demand management. We suggest three findings. First, we find that the themes of our theoretical framework policy backgrounds, governance and policy contents have played important roles for Seoul’s energy experiments aimed at urban energy autonomy. In particular, political leadership based on the mayor’s previous experiences contributed significantly to the formation and implementation of this policy. Second, the OLNPP policy adds a social or moral dimension to urban energy policies. The norm change from an environmental and economic focus to a focus on the combination of social, environmental, and economic considerations is a unique contribution of the OLNPP policy to urban experiments in energy transition. Third, we find that experiments through purposive interventions serve as a means for facilitating urban energy governance where the actors involved can communicate and enhance their new ideas and practices.

Taehwa Lee; Taedong Lee; Yujin Lee

2014-01-01T23:59:59.000Z

434

Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant  

SciTech Connect

The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

2009-03-01T23:59:59.000Z

435

U.S.-Russia MPC and A upgrades at the Beloyarsk Nuclear Power Plant  

SciTech Connect

During the January 1996 meeting of the Gore-Chernomyrdin Commission, the Beloyarsk Nuclear Power Plant (BNPP) was identified as one of the additional sites for cooperative projects on upgrading Materials Protection, Control and Accounting (MPC and A). Since June 1996, Sandia National Laboratories (SNL), Pacific Northwest National Laboratories (PNNL), and Los Alamos National Laboratory (LANL) have worked with BNPP to upgrade MPC and A at the facility. Some unique challenges were encountered because BNPP has an operating BN-600 600-Megawatt breeder reactor. SNL has been responsible for working with BNPP to implement physical protection upgrades to the Central Alarm Station, Fresh Fuel Storage building, Spent Fuel Storage Area, and Vehicle/Personnel Portal. In addition, improved communication equipment for the Ministry of the Interior (MVD) guards and training of personnel were provided. PNNL has been responsible for coordinating Material Control and Accounting (MC and A) upgrades at BNPP. PNNL, in conjunction with LANL, has implemented such MC and A upgrades as a computerized nuclear materials accounting system, training in MC and A elements, nondestructive assay instrumentation for fresh fuel, installation of a fork detector for measuring spent fuel, and installation of an underwater video camera for verification of spent fuel serial numbers.

Saraev, O. [Beloyarsk Nuclear Power Plant, Zarechny (Russian Federation); Haase, M.; Smarto, C. [Dept. of Energy, Washington, DC (United States); Mikkelsen, K.; Heinberg, C. [Pacific Northwest National Labs., Richland, WA (United States); Showalter, R.; Soo Hoo, M. [Sandia National Labs., Albuquerque, NM (United States); Hatcher, C.; Forehand, M. [Los Alamos National Lab., NM (United States)

1998-08-01T23:59:59.000Z

436

Blending mining and nuclear industries at the Waste Isolation Pilot Plant  

SciTech Connect

At the Waste Isolation Pilot Plant (WIPP) traditional procedures for underground mining activities have been significantly altered in order to assure underground safety and project adherence to numerous regulatory requirements. Innovative techniques have been developed for WIPP underground procedures, mining equipment, and operating environments. The mining emphasis at WIPP is upon the quality of the excavation, not (as in conventional mines) on the production of ore. The WIPP is a United States Department of Energy (DOE) project that is located 30 miles southeast of Carlsbad, New Mexico, where the nation's first underground engineered nuclear repository is being constructed. The WIPP site was selected because of its location amidst a 607 meter thick salt bed, which provides a remarkably stable rock formation for the permanent storage of nuclear waste. The underground facility is located 655 meters below the earth's surface, in the Salado formation, which comprises two-hundred million year old halites with minor amounts of clay and anhydrites. When completed, the WIPP underground facility will consist of two components: approximately 81 square kilometers of experimental areas, and approximately 405 square kilometers of repository. 3 figs.

Walls, J.R.

1990-01-01T23:59:59.000Z

437

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

438

Leukemia, Lymphomas, and Myeloma Mortality in the Vicinity of Nuclear Power Plants and Nuclear Fuel Facilities in Spain  

Science Journals Connector (OSTI)

...Douglas A. J. Mortality of workers at the Sellafield plant of...combined mortality data on workers at the Hanford Site, Oak Ridge National Laboratory, and Rocky...mortality and morbidity among workers at the Sellafield plant of...

Gonzalo López-Abente; Nuria Aragonés; Marina Pollán; María Ruiz; and Ana Gandarillas

1999-10-01T23:59:59.000Z

439

Agricultural approaches of remediation in the outside of the Fukushima Daiichi nuclear power plant  

SciTech Connect

This paper outlines agricultural approaches of remediation activity done in contaminated areas around the Fukushima Daiichi Nuclear Power Plant. About the decontamination examination of contaminated areas, we have tried the land scale test of a rice field before and after planting by the use of currently recommended methods. Since farmers would carry out the land preparation by themselves, generation of secondary radioactive waste should be as low as possible through the decontamination works. For the radioactive nuclide migration control of rice by wet rice production, several types of decontamination methods such as zeolite addition and potassium fertilization in the soil have been examined. The results are summarized in the 4 following points. 1) Plowing and water discharge are effective for removing radioactive cesium from rice field. 2) Additional potassium fertilization is effective for reducing cesium radioactivity in the product. 3) No significant difference is observed with or without the zeolite addition. 4) Very low transfer factor of cesium from soil to brown rice has been obtained compared with literature values.

Sato, Nobuaki [Tohoku University, 2-1-1 Katahira Aoba-ku, Sendai, Miyagi 980-8577 (Japan); Saso, Michitaka [Toshiba Corporation Power Systems Company: 2-1 Ukishima-cho, Kawasaki-ku, Kawasaki, Kanagawa 210-0862 (Japan); Umeda, Miki [Japan Atomic Energy Agency, 4-29 Muramatsu, Tokai, Ibaraki 319-1184 (Japan); Fujii, Yasuhiko [Tokyo Institute of Technology:2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan); Amemiya, Kiyoshi [Hazama Corporation: 2-2-5 Toranomon, Minato-ku, Tokyo 105-8479 (Japan)

2013-07-01T23:59:59.000Z

440

Comparative Evaluation of Cutting Methods of Activated Concrete from Nuclear Power Plant Decommissioning - 13548  

SciTech Connect

The amount of radioactive wastes from decommissioning of a nuclear power plant varies greatly depending on factors such as type and size of the plant, operation history, decommissioning options, and waste treatment and volume reduction methods. There are many methods to decrease the amount of decommissioning radioactive wastes including minimization of waste generation, waste reclassification through decontamination and cutting methods to remove the contaminated areas. According to OECD/NEA, it is known that the radioactive waste treatment and disposal cost accounts for about 40 percentage of the total decommissioning cost. In Korea, it is needed to reduce amount of decommissioning radioactive waste due to high disposal cost, about $7,000 (as of 2010) per a 200 liter drum for the low- and intermediate-level radioactive waste (LILW). In this paper, cutting methods to minimize the radioactive waste of activated concrete were investigated and associated decommissioning cost impact was assessed. The cutting methods considered are cylindrical and volume reductive cuttings. The study showed that the volume reductive cutting is more cost-effective than the cylindrical cutting. Therefore, the volume reductive cutting method can be effectively applied to the activated bio-shield concrete. (authors)

Kim, HakSoo; Chung, SungHwan; Maeng, SungJun [Central Research Institute, Korea Hydro and Nuclear Power Co. Ltd., 1312-70 Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)] [Central Research Institute, Korea Hydro and Nuclear Power Co. Ltd., 1312-70 Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "yankee nuclear plant" from the National Library of EnergyBeta (NLEBeta).
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441

New York Power Authority Uses Decision Analysis to Schedule Refueling of Its Indian Point 3 Nuclear Power Plant  

Science Journals Connector (OSTI)

The New York Power Authority (NYPA) wanted to develop a 10-year schedule for refueling its Indian Point 3 Nuclear Power Plant (IP3) that balanced fish protection, which occurs when IP3 is shut down for refueling, and the costs of buying and loading fuel. ... Keywords: DECISION ANALYSIS--APPLICATIONS, INDUSTRIES--ELECTRIC ENVIRONMENT

Dennis J. Dunning; Steve Lockfort; Quentin E. Ross; Phillip C. Beccue; Jeffrey S. Stonebraker

2001-09-01T23:59:59.000Z

442

Summary of the historical development of seismic design of nuclear power plants in Japan and the U.S.  

Science Journals Connector (OSTI)

Abstract Over the past 50 years seismic design of nuclear power plants in Japan and the U.S. have undergone very significant changes in the three activities associated with design:• Quantification of seismic load and other applicable loads and specification of their load combinations to be considered in design. • Analysis methods and procedures necessary to convert input earthquake motions and loads normally expressed in the form of acceleration to resultant seismic dynamic or equivalent static forces, moments or stresses, fms in structures, systems and components, SSC. • Codes or standards acceptance criteria used to evaluate resultant forces, moments or stresses, fms in nuclear safety SSC to determine design adequacy. These applications to the historical development of Nuclear Power Plant, NPP designs in Japan and U.S. are summarized.

John D. Stevenson

2014-01-01T23:59:59.000Z

443

Interim storage of dismantled nuclear weapon components at the U.S. Department of Energy Pantex Plant  

SciTech Connect

Following the events of 1989 and the subsequent cessation of production of new nuclear weapons by the US, the mission of the Department of Energy (DOE) Nuclear Weapons Complex has shifted from production to dismantlement of retired weapons. The sole site in the US for accomplishing the dismantlement mission is the DOE Pantex Plant near Amarillo, Texas. Pending a national decision on the ultimate storage and disposition of nuclear components form the dismantled weapons, the storage magazines within the Pantex Plant are serving as the interim storage site for pits--the weapon plutonium-bearing component. The DOE has stipulated that Pantex will provide storage for up to 12,000 pits pending a Record of Decision on a comprehensive site-wide Environmental Impact Statement in November 1996.

Guidice, S.J.; Inlow, R.O. [USDOE Albuquerque Operations Office, NM (United States)

1995-12-31T23:59:59.000Z

444

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs  

SciTech Connect

Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) version [a prismatic-core modular reactor (PMR)] or a pebble-bed modular reactor (PBMR) version [a pebble bed reactor (PBR)] design, with either a direct- or indirect-cycle gas turbine (Brayton cycle) system for electric power production, and an indirect-cycle component for hydrogen production. NGNP design options with a high-pressure steam generator (Rankine cycle) in the primary loop are not considered in this PIRT. This graphite PIRT was conducted in parallel with four other NRC PIRT activities, taking advantage of the relationships and overlaps in subject matter. The graphite PIRT panel identified numerous phenomena, five of which were ranked high importance-low knowledge. A further nine were ranked with high importance and medium knowledge rank. Two phenomena were ranked with medium importance and low knowledge, and a further 14 were ranked medium importance and medium knowledge rank. The last 12 phenomena were ranked with low importance and high knowledge rank (or similar combinations suggesting they have low priority). The ranking/scoring rationale for the reported graphite phenomena is discussed. Much has been learned about the behavior of graphite in reactor environments in the 60-plus years since the first graphite rectors went into service. The extensive list of references in the Bibliography is plainly testament to this fact. Our current knowledge base is well developed. Although data are lacking for the specific grades being considered for Generation IV (Gen IV) concepts, such as the NGNP, it is fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain graphite behavior have been postulated and, in many cases, shown to represent experimental data well. However, these theories need to be tested against data for the new graphites and extended to higher neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.

Burchell, Timothy D [ORNL; Bratton, Rob [Idaho National Laboratory (INL); Marsden, Barry [University of Manchester, UK; Srinivasan, Makuteswara [U.S. Nuclear Regulatory Commission; Penfield, Scott [Technology Insights; Mitchell, Mark [PBMR (Pty) Ltd.; Windes, Will [Idaho National Laboratory (INL)

2008-03-01T23:59:59.000Z

445

A Safer Nuclear Enterprise  

Science Journals Connector (OSTI)

...2012 at the Nuclear Security...leadership in nuclear enterprise...multinational assessment of emerging risks and consequences...to assess nuclear risks in...or nuclear terrorism. States...and nuclear power. Since 1945...nuclear power plant can mean...

Sidney D. Drell; George P. Shultz; Steven P. Andreasen

2012-06-08T23:59:59.000Z

446

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)

nuclear, geothermal, and fossil-fuel power plants. However,power plants, which are reviewed and licensed by the Nuclear Regulatory Commission (NRC), and relatively few areas of geothermal and

Nero, A.V.

2010-01-01T23:59:59.000Z

447

Regulatory analysis for the resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants  

SciTech Connect

Generic Safety Issue (GSI)-29 deals with staff concerns about public risk due to degradation or failure of safety-related bolting in nuclear power plants. The issue was initiated in November 1982. Value-impact studies of a mandatory program on safety-related bolting for operating plants were inconclusive: therefore, additional regulatory requirements for operating plants could not be justified in accordance with provisions of 10 CFR 50.109. In addition, based on operating experience with bolting in both nuclear and conventional power plants, the actions already taken through bulletins, generic letters, and information notices, and the industry-proposed actions, the staff concluded that a sufficient technical basis exists for the resolution of GSI-29. The staff further concluded that leakage of bolted pressure joints is possible but catastrophic failure of a reactor coolant pressure boundary joint that will lead to significant accident sequences is highly unlikely. For future plants, it was concluded that a new Standard Review Plant section should be developed to codify existing bolting requirements and industry-developed initiatives. 9 refs., 1 tab.

Chang, T.Y.

1991-09-01T23:59:59.000Z

448

RELIABLE CONTROL AND ONLINE MONITORING DESIGN FOR NUCLEAR POWER PLANT WITH IRIS DEMONSTRATION.  

E-Print Network (OSTI)

??Development and deployment of small-scale nuclear power reactors and their autonomous control and monitoring is part of the mission under the Global Nuclear Energy Partnership… (more)

Guo, Yin

2010-01-01T23:59:59.000Z

449

An investigation of temperature measurement methods in nuclear power plant reactor pressure vessel annealing  

SciTech Connect

The objective of this project was to provide an assessment of several methods by which the temperature of a commercial nuclear power plant reactor pressure vessel (RPV) could be measured during an annealing process. This project was a coordinated effort between DOE`s Office of Nuclear Energy, Science and Technology; DOE`s Light Water Reactor Technology Center at Sandia National Laboratories; and the Electric Power Research Institute`s Non- Destructive Evaluation Center. Ball- thermocouple probes similar to those described in NUREG/CR-5760, spring-loaded, metal- sheathed thermocouple probes, and 1778 air- suspended thermocouples were investigated in experiments that heated a section of an RPV wall to simulate a thermal annealing treatment. A parametric study of ball material, emissivity, thermal conductivity, and thermocouple function locations was conducted. Also investigated was a sheathed thermocouple failure mode known as shunting (electrical breakdown of insulation separating the thermocouple wires). Large errors were found between the temperature as measured by the probes and the true RPV wall temperature during heat-up and cool-down. At the annealing soak temperature, in this case 454{degrees}C [850`F], all sensors measured the same temperature within about {plus_minus}5% (23.6{degrees}C [42.5{degrees}F]). Because of these errors, actual RPV wall heating and cooling rates differed from those prescribed (by up to 29%). Shunting does not appear to be a problem under these conditions. The large temperature measurement errors led to the development of a thermal model that predicts the RPV wall temperature from the temperature of a ball- probe. Comparisons between the model and the experimental data for ball-probes indicate that the model could be a useful tool in predicting the actual RPV temperature based on the indicated ball- probe temperature. The model does not predict the temperature as well for the spring-loaded and air suspended probes.

Acton, R.U.; Gill, W.; Sais, D.J.; Schulze, D.H.; Nakos, J.T. [Sandia National Labs., Albuquerque, NM (United States)

1996-05-01T23:59:59.000Z

450

An Empirical Study on Ultrasonic Testing in Lieu of Radiography for Nuclear Power Plants  

SciTech Connect

Research is being conducted for the U.S. Nuclear Regulatory Commission (NRC) at the Pacific Northwest National Laboratory (PNNL) to assess the capability, effectiveness, and reliability of ultrasonic testing (UT) as a replacement method for radiographic testing (RT) for inspecting nuclear power plant (NPP) components. A primary objective of this work is to evaluate UT techniques to assess their ability to detect, locate, size, and characterize fabrication flaws in typical NPP weldments. This particular study focused on the evaluation of four carbon steel pipe-to-pipe welds on specimens that ranged in thicknesses from 19.05 mm (0.75 in.) to 27.8 mm (1.094 in.) and were 355.6 mm (14.0 in.) or 406.4 mm (16.0 in.) in diameter. The pipe welds contained both implanted (intentional) fabrication flaws as well as bonus (unintentional) flaws throughout the entire thickness of the weld and the adjacent base material. The fabrication flaws were a combination of planar and volumetric flaw types, including incomplete fusion, incomplete penetration, cracks, porosity, and slag inclusions. The examinations were conducted using phased-array UT (PA UT) techniques applied primarily for detection and length sizing of the flaws. Radiographic examinations were also conducted on the specimens with RT detection and length sizing results being used to establish true state. This paper will discuss the comparison of UT and RT (true state) detection results conducted to date along with a discussion on the technical gaps that need to be addressed before these methods can be used interchangeably for repair and replacement activities for NPP components.

Moran, Traci L.; Pardini, Allan F.; Ramuhalli, Pradeep; Prowant, Matthew S.; Mathews, Royce

2012-09-01T23:59:59.000Z

451

Regulatory analysis for amendments to regulations for the environmental review for renewal of nuclear power plant operating licenses. Final report  

SciTech Connect

This regulatory analysis provides the supporting information for a proposed rule that will amend the Nuclear Regulatory Commission`s environmental review requirements for applications for renewal of nuclear power plant operating licenses. The objective of the proposed rulemaking is to improve regulatory efficiency by providing for the generic evaluation of certain environmental impacts associated with nuclear plant license renewal. After considering various options, the staff identified and analyzed two major alternatives. With Alternative A, the existing regulations would not be amended. This option requires that environmental reviews be performed under the existing regulations. Alternative B is to assess, on a generic basis, the environmental impacts of renewing the operating license of individual nuclear power plants, and define the issues that will need to be further analyzed on a case-by-case basis. In addition, Alternative B removes from NRC`s review certain economics-related issues. The findings of this assessment are to be codified in 10 CFR 51. The staff has selected Alternative B as the preferred alternative.

NONE

1996-05-01T23:59:59.000Z

452

COMPUTER-BASED PROCEDURE FOR FIELD ACTIVITIES: RESULTS FROM THREE EVALUATIONS AT NUCLEAR POWER PLANTS  

SciTech Connect

Nearly all activities that involve human interaction with the systems of a nuclear power plant are guided by procedures. The paper-based procedures (PBPs) currently used by industry have a demonstrated history of ensuring safety; however, improving procedure use could yield tremendous savings in increased efficiency and safety. One potential way to improve procedure-based activities is through the use of computer-based procedures (CBPs). Computer-based procedures provide the opportunity to incorporate context driven job aids, such as drawings, photos, just-in-time training, etc into CBP system. One obvious advantage of this capability is reducing the time spent tracking down the applicable documentation. Additionally, human performance tools can be integrated in the CBP system in such way that helps the worker focus on the task rather than the tools. Some tools can be completely incorporated into the CBP system, such as pre-job briefs, placekeeping, correct component verification, and peer checks. Other tools can be partly integrated in a fashion that reduces the time and labor required, such as concurrent and independent verification. Another benefit of CBPs compared to PBPs is dynamic procedure presentation. PBPs are static documents which limits the degree to which the information presented can be tailored to the task and conditions when the procedure is executed. The CBP system could be configured to display only the relevant steps based on operating mode, plant status, and the task at hand. A dynamic presentation of the procedure (also known as context-sensitive procedures) will guide the user down the path of relevant steps based on the current conditions. This feature will reduce the user’s workload and inherently reduce the risk of incorrectly marking a step as not applicable and the risk of incorrectly performing a step that should be marked as not applicable. As part of the Department of Energy’s (DOE) Light Water Reactors Sustainability Program, researchers at Idaho National Laboratory (INL) along with partners from the nuclear industry have been investigating the design requirements for computer-based work instructions (including operations procedures, work orders, maintenance procedures, etc.) to increase efficiency, safety, and cost competitiveness of existing light water reactors.

Oxstrand, Johanna [Idaho National Laboratory; Bly, Aaron [Idaho National Laboratory; LeBlanc, Katya [Idaho National Laboratory

2014-09-01T23:59:59.000Z

453

Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants  

SciTech Connect

This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented.

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

1994-03-01T23:59:59.000Z

454

Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites  

SciTech Connect

The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

Maheras, Steven J. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Best, Ralph [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River National Laboratory, Aiken, SC (United States); McConnell, Paul [Sandia National Laboratories, Albuquerque, NM (United States)

2013-04-30T23:59:59.000Z

455

Effect of the Fukushima nuclear accident on the risk perception of residents near a nuclear power plant in China  

Science Journals Connector (OSTI)

...Societal risk as seen by the French public . Risk Anal 13 ( 3 ): 253 – 258...electricity supply. Perspective on public opinion (May). Nuclear Energy Institute...1168 – 1169 . 24 Renn O ( 1990 ) Public response to the Chernobyl accident...

Lei Huang; Ying Zhou; Yuting Han; James K. Hammitt; Jun Bi; Yang Liu

2013-01-01T23:59:59.000Z

456

Leukemia, Lymphomas, and Myeloma Mortality in the Vicinity of Nuclear Power Plants and Nuclear Fuel Facilities in Spain  

Science Journals Connector (OSTI)

...study among workers at two nuclear...mortality near Oak Ridge, Tennessee...leukaemia in Europe after Chernobyl...Mortality, 1950-1978: Part...Mortality of workers at the Sellafield...Hanford Site, Oak Ridge National Laboratory...

Gonzalo López-Abente; Nuria Aragonés; Marina Pollán; María Ruiz; and Ana Gandarillas

1999-10-01T23:59:59.000Z

457

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 test 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 litre-scale air samples (corresponding to about 100 mBq/m$^3$) is achievable. Our results provide 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 at high altitude over Germany occurred several days before the ground level plume.

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

2014-12-05T23:59:59.000Z

458

Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project  

SciTech Connect

At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest – i.e., within the next 10-15 years.

L.E. Demick

2010-09-01T23:59:59.000Z

459

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

SciTech Connect

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

460

Small modular HTGR nuclear power plant concept to meet the total energy needs of the developing nations  

SciTech Connect

In this paper, a small modular High-Temperature Gas-Cooled Reactor (HTGR) is described that can support the total energy needs of the developing nations by supplying electrical power, process steam, low-grade heat for desalination, and hydrogen production. Major features of the nuclear power plant concept, currently under development by GA Technologies Inc. (GA), are discussed with emphasis on (1) plant simplicity, (2) inherent safety, (3) ease of operation, (4) design and licensing standardization, and (5) acceptable power generation economics.

McDonald, C.F.

1983-09-26T23:59:59.000Z

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461

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

SciTech Connect

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

MM Hall

2006-01-31T23:59:59.000Z

462

Issues arising with the application of optical fiber transmission in class 1E systems in nuclear power plants  

SciTech Connect

The application of fiber optic links and networks in safety-critical systems in the next generation of nuclear power plants, as well as in some digital upgrades in present-day plants, will mean that these links must be highly reliable and able to withstand the effect of environmental stressors present at the installation location. This paper discusses the failure modes and age-related mechanisms of fiber optic transmission components and identifies environmental stressors that could adversely affect their reliability over the long term. Some of the standards that could be used in their qualification for safety-critical applications are also discussed briefly.

Korsah, K. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research

1993-12-31T23:59:59.000Z

463

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

464

RADIOACTIVE WASTE MANAGEMENT IN THE CHERNOBYL EXCLUSION ZONE - 25 YEARS SINCE THE CHERNOBYL NUCLEAR POWER PLANT ACCIDENT  

SciTech Connect

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures of fuel containing materials can be fairly useful for the entire world's nuclear community and can help make nuclear energy safer.

Farfan, E.; Jannik, T.

2011-10-01T23:59:59.000Z

465

A real options approach to investing in the first nuclear power plant under cost uncertainty: comparison with natural gas power plant for the Tunisian case  

Science Journals Connector (OSTI)

This paper uses a real options approach to present a method for evaluating the first Nuclear Power Plant (NPP) investment in Tunisia in 2020. The evaluating model integrates the value of real options: option to wait in the standard discount cash flow analysis. According to the IAEA (2007), starting the first stage of a nuclear power programme makes it possible to construct the first NPP in second time. This study considers that the economic worth of the NPP investment depends on the production cost of the natural gas power plant. This study assumes that the profit realised by the NPP project, defined as the difference between natural gas and nuclear production costs, represented the cash flow of the NPP investment. However, the value of this cash flow is uncertain. This is an investment choice problem under uncertainty. The analysis proposes the optimal investment strategy in NPP project for the Tunisian government. Furthermore, the threshold value of investment cash flow defining the timing of starting NPP construction is calculated. [Received: July 10, 2008; Accepted: November 23, 2008

Mohamed Ben Abdelhamid; Chaker Aloui; Corinne Chaton

2009-01-01T23:59:59.000Z

466

Light Qualityâ??Dependent Nuclear Import of the Plant Photoreceptors Phytochrome A and B  

Science Journals Connector (OSTI)

...produced as described in . Handling of irradiated or dark-grown...according to . Plant Material and Growth Conditions...light microscopy, plant material was transferred to glass...pulse-treated plant material was manipulated under...Tobacco Plants. (A) Diagrams of PHYA-mGFP4 and...

Stefan Kircher; Laszlo Kozma-Bognar; Lana Kim; Eva Adam; Klaus Harter; Eberhard Schäfer; Ferenc Nagy

467

Ecological Half-Lives of Radiocesium in 16 Species in Marine Biota after the TEPCO’s Fukushima Daiichi Nuclear Power Plant Accident  

Science Journals Connector (OSTI)

The Fukushima Daiichi Nuclear Power Plant (FDNPP) accident of March 11, 2011 was the result of the Great East Japan Earthquake, a magnitude 9.0 earthquake, and the resultant tsunami, which severely damaged several reactors. ... Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear Safety—The Accident at TEPCO’s Fukushima Nuclear Power Stations; NERH: Tokyo, Japan, 2011; http://www.kantei.go.jp/foreign/kan/topics/201106/iaea_houkokusho_e.html ... Results of Simulation of the Atmospheric Behavior of Radioactive Materials Released from the Fukushima Daiichi Nuclear Power Plant; NIES, Tsukuba, Japan; http://www.nies.go.jp/whatsnew/2011/20110825/20110825.html ...

Kayoko Iwata; Keiko Tagami; Shigeo Uchida

2013-06-14T23:59:59.000Z

468

A view of treatment process of melted nuclear fuel on a severe accident plant using a molten salt system  

SciTech Connect

At severe accident such as Fukushima Daiichi Nuclear Power Plant Accident, the nuclear fuels in the reactor would melt and form debris which contains stable UO2-ZrO2 mixture corium and parts of vessel such as zircaloy and iron component. The requirements for solution of issues are below; -) the reasonable treatment process of the debris should be simple and in-situ in Fukushima Daiichi power plant, -) the desirable treatment process is to take out UO{sub 2} and PuO{sub 2} or metallic U and TRU metal, and dispose other fission products as high level radioactive waste; and -) the candidate of treatment process should generate the smallest secondary waste. Pyro-process has advantages to treat the debris because of the high solubility of the debris and its total process feasibility. Toshiba proposes a new pyro-process in molten salts using electrolysing Zr before debris fuel being treated.

Fujita, R.; Takahashi, Y.; Nakamura, H.; Mizuguchi, K. [Power and Industrial Research and Development Center, Toshiba Corporation Power Systems Company, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan); Oomori, T. [Chemical System Design and Engineering Department, Toshiba Corporation Power Systems Company, 8 Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan)

2013-07-01T23:59:59.000Z

469

Seismic fragility evaluation of a piping system in a nuclear power plant by shaking table test and numerical analysis  

SciTech Connect

In this study, a seismic fragility evaluation of the piping system in a nuclear power plant was performed. For the evaluation of seismic fragility of the piping system, this research was progressed as three steps. At first, several piping element capacity tests were performed. The monotonic and cyclic loading tests were conducted under the same internal pressure level of actual nuclear power plants to evaluate the performance. The cracks and wall thinning were considered as degradation factors of the piping system. Second, a shaking tale test was performed for an evaluation of seismic capacity of a selected piping system. The multi-support seismic excitation was performed for the considering a difference of an elevation of support. Finally, a numerical analysis was performed for the assessment of seismic fragility of piping system. As a result, a seismic fragility for piping system of NPP in Korea by using a shaking table test and numerical analysis. (authors)

Kim, M. K.; Kim, J. H.; Choi, I. K. [Korea Atomic Energy Research Inst., Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2012-07-01T23:59:59.000Z

470

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

471

A best estimate method for the diagnosis and mitigation of multiple-failure transients in nuclear power plants  

E-Print Network (OSTI)

, he only monitors one source, such as the pressurizer pressure indicator, rather than examining other instruments that can supply the same information, such as reactor vessel pressure or the pump outlet pressure. This procedure of monitoring on only..., concentrating on applying a themy of probability, However, the work presented herein is based on a different method involving "confidence levels". For this project a qualitative model of a nuclear power plant and the ATMS knowledge base of transient facts...

Martin, Robert Paul

2012-06-07T23:59:59.000Z

472

Mechanistic understanding of irradiation-induced corrosion of zirconium alloys in nuclear power plants: Stimuli, status, and outlook  

SciTech Connect

Failures in the basic materials used in nuclear power plants continue to be costly and insidious, despite increasing industry vigilance to catch failures before they degrade safety. For instance, the overall costs to the US industry from materials problems could amount to as much as $10 billion annually. Moreover, estimates indicate that the cost of a pipe failure in a nuclear plant is one hundred times greater than the cost of a similar failure in a coal-fired plant. There are important practical stimuli and much scope for further understanding of the effects of irradiation on Zr-alloys (and other materials used in nuclear installations) by careful experimentation. Moreover, these studies need to address the effect of irradiation on all components of heterogeneous systems: the metal, the oxide and the environment, and especially those processes recurring at the interphases between these components. The present paper is aimed at providing specialists with some systematic information on the subject and with important considerations on the key items for further experimentation.

Johnson, A.B. Jr.; Ishigure, K.; Nechaev, A.F.; Reznichenko, E.A.; Cox, B.; Lemaignan, C.; Petrik, N.G.

1990-05-01T23:59:59.000Z

473

Qualification issues associated with the use of advanced instrumentation and control systems hardware in nuclear power plants  

SciTech Connect

The instrumentation and control (I&C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and Tiber-optic transmission. Elements of these advances in I&C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying I&C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I&C for present-day plants was compared to that proposed for advanced light water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light water reactor. The template was then used to address reliability issues for microprocessor-based protection systems. Standards (or lack thereof) for the qualification of microprocessor-based safety I&C systems were also identified. This approach addresses in part issues raised in Nuclear Regulatory Commission policy document SECY-91-292. which recognizes that advanced I&C systems for the nuclear industry are ``being developed without consensus standards, as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.``

Korsah, K. [Oak Ridge National Lab., TN (United States); Antonescu, C. [Nuclear Regulatory Commission, Rockville, MD (United States). Office of Nuclear Regulatory Research

1993-10-01T23:59:59.000Z

474

Increasing the Work-Safety in Nuclear Power Plants through the Use of Preventive Maintenance Policies  

Science Journals Connector (OSTI)

Nuclear power is being used at an increasing rate as a substitute for scarce and expensive classical energy sources. Controlled nuclear fission generates energy but, at the same time, produces radioactive subs...

Dr. U. Pachow; Prof. Dr. H. Gehring; H. J. Rokohl

1982-01-01T23:59:59.000Z