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Residual life assessment of major light water reactor components -

Residual life assessment of major light water reactor components

Heat release rates of electrical enclosure fires (HELEN-FIRE) - Kevin B. McGrattan

Heat release rates of electrical enclosure fires (HELEN-FIRE)

Kevin B. McGrattan

NRC reviewer aid for evaluating the human-performance aspects related to the design and operation of small modular reactors - John O'Hara

NRC reviewer aid for evaluating the human-performance aspects related to the design and operation of small modular reactors

John O'Hara

Mechanical fatigue testing of high-burnup fuel for transportation applications - Jy-An Wang

Mechanical fatigue testing of high-burnup fuel for transportation applications

Jy-An Wang

Testing to evaluate extended battery operation in nuclear power plants - W. Gunther

Testing to evaluate extended battery operation in nuclear power plants

W. Gunther

Nuclear power plant fire ignition frequency and non-suppression probability estimation using the updated fire events database - N. Melly

Nuclear power plant fire ignition frequency and non-suppression probability estimation using the updated fire events database

N. Melly

Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire detection systems in nuclear facilities (DELORES-VEWFIRE) - Gabriel D. Taylor

Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire detection systems in nuclear facilities (DELORES-VEWFIRE)

Gabriel D. Taylor

Rod bundle heat transfer facility steam cooling with droplet injection experiments data report - L. E. Hochreiter

Rod bundle heat transfer facility steam cooling with droplet injection experiments data report

L. E. Hochreiter

Consolidation of the 1985 Sandia National Laboratories/Factory Mutual Main Control Room and Electrical Cabinet Fire Test Data - F. Gonzalez

Consolidation of the 1985 Sandia National Laboratories/Factory Mutual Main Control Room and Electrical Cabinet Fire Test Data

F. Gonzalez

Uranium sequestration during biostimulated reduction and in response to the return of oxic conditions in shallow aquifers - C. C. Fuller

Uranium sequestration during biostimulated reduction and in response to the return of oxic conditions in shallow aquifers

C. C. Fuller

Transfer factors for contaminant uptake by fruit and nut trees - B. A. Napier

Transfer factors for contaminant uptake by fruit and nut trees

B. A. Napier

MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project - Kyle Ross

MELCOR best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project

Kyle Ross

Consequence study of a beyond-design-basis earthquake affecting the spent fuel pool for a U.S. Mark I boiling water reactor - Andrew Barto

Consequence study of a beyond-design-basis earthquake affecting the spent fuel pool for a U.S. Mark I boiling water reactor

Andrew Barto

Safety and regulatory issue of the thorium fuel cycle - Brian Ade

Safety and regulatory issue of the thorium fuel cycle

Brian Ade

A formalized approach for the collection of HRA data from nuclear power plant simulators - B. P. Hallbert

A formalized approach for the collection of HRA data from nuclear power plant simulators

B. P. Hallbert

Knowledge base report on emergency core cooling sump performance in operating light water reactors - K. Natesan

Knowledge base report on emergency core cooling sump performance in operating light water reactors

K. Natesan

MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project - N. E. Bixler

MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project

N. E. Bixler

Thermal analysis of horizontal storage casks for extended storage applications - Kaushik Das

Thermal analysis of horizontal storage casks for extended storage applications

Kaushik Das

The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model - Chunkuan Shih

The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model

Chunkuan Shih

VARSKIN 5 - D. M. Hamby

VARSKIN 5

D. M. Hamby

Risk informing emergency preparedness oversight - M. Azarm

Risk informing emergency preparedness oversight

M. Azarm

State-of-the-art-reactor consequence analyses project - Nathan Bixler

State-of-the-art-reactor consequence analyses project

Nathan Bixler

New source term model for the RESRAD-OFFSITE code version 3 - C. Yu

New source term model for the RESRAD-OFFSITE code version 3

C. Yu

Reliability of ultrasonic in-service inspection of welds in reactor internals of boiling water reactors / prepared by G.J. Schuster [and four others] - G. J. Schuster

Reliability of ultrasonic in-service inspection of welds in reactor internals of boiling water reactors / prepared by G.J. Schuster [and four others]

G. J. Schuster

Glossary of risk-related terms in support of risk-informed decisionmaking - M. Drouin

Glossary of risk-related terms in support of risk-informed decisionmaking

M. Drouin

Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2010 - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research

Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2010

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Fitness for duty in the nuclear power industry - K. Branch

Fitness for duty in the nuclear power industry

K. Branch

Development of quantitative software reliability models for digital protection systems of nuclear power plants - Tsong-Lun Chu

Development of quantitative software reliability models for digital protection systems of nuclear power plants

Tsong-Lun Chu

Early leak detection external to structures at nuclear power plants - Mark Fuhrmann

Early leak detection external to structures at nuclear power plants

Mark Fuhrmann

Laminar hydraulic analysis of a commercial pressurized water reactor fuel assembly - Eric R. Lindgren

Laminar hydraulic analysis of a commercial pressurized water reactor fuel assembly

Eric R. Lindgren

Development of a fault injection-based dependability assessment methodology for digital I & C systems - Carl R. Elks

Development of a fault injection-based dependability assessment methodology for digital I & C systems

Carl R. Elks

Computational fluid dynamics best practice guidelines for dry cask applications - Ghani Zigh

Computational fluid dynamics best practice guidelines for dry cask applications

Ghani Zigh

EPRI/NRC-RES fire human reliability analysis guidelines - S. Cooper

EPRI/NRC-RES fire human reliability analysis guidelines

S. Cooper

The estimation of very-low probability hurricane storm surges for design and licensing of nuclear power plants in coastal areas - Donald T. Resio

The estimation of very-low probability hurricane storm surges for design and licensing of nuclear power plants in coastal areas

Donald T. Resio

State-of-the-art-reactor consequence analyses (SOARCA) report - Richard Chang

State-of-the-art-reactor consequence analyses (SOARCA) report

Richard Chang

Evaluation of JNES equipment fragility tests for use in seismic probablilistic risk assessments for U.S. nuclear plants - R. P. Kennedy

Evaluation of JNES equipment fragility tests for use in seismic probablilistic risk assessments for U.S. nuclear plants

R. P. Kennedy

VARSKIN 4 - D. M. Hamby

VARSKIN 4

D. M. Hamby

Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors -

Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors

Review guidelines for field-programmable gate arrays in nuclear power plant safety systems - M. Bobrek

Review guidelines for field-programmable gate arrays in nuclear power plant safety systems

M. Bobrek

Nuclear power plant fire modeling application guide - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research

Nuclear power plant fire modeling application guide

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Recommended screening limits for pressurized thermal shock (PTS) - M. T. EricksonKirk

Recommended screening limits for pressurized thermal shock (PTS)

M. T. EricksonKirk

The Browns Ferry Nuclear Plant fire of 1975 and the history of NRC fire regulations -

The Browns Ferry Nuclear Plant fire of 1975 and the history of NRC fire regulations

Modeling a digital feedwater control system using traditional probabilistic risk assessment methods - T. L. Chu

Modeling a digital feedwater control system using traditional probabilistic risk assessment methods

T. L. Chu

Demonstrating the feasibility and reliability of operator manual actions in response to fire -

Demonstrating the feasibility and reliability of operator manual actions in response to fire

Common-cause failure database and analysis system - T. E. Wierman

Common-cause failure database and analysis system

T. E. Wierman

EPRI/NRC-RES fire PRA methodology for nuclear power facilities - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research

EPRI/NRC-RES fire PRA methodology for nuclear power facilities

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Technical basis for the NRC's guidelines for external risk communication - L. Peterson

Technical basis for the NRC's guidelines for external risk communication

L. Peterson

Air oxidation kinetics for Zr-based alloys - K. Natesan

Air oxidation kinetics for Zr-based alloys

K. Natesan

Generalized procedure for generating flaw-related inputs for the FAVOR code -

Generalized procedure for generating flaw-related inputs for the FAVOR code

Regulatory guide 1.168 (draft was issued as DG-1123) - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research.

Regulatory guide 1.168 (draft was issued as DG-1123)

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

Draft regulatory guide DG-7004 - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research.

Draft regulatory guide DG-7004

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents -

TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents

Draft regulatory guide DG-7004 - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research.

Draft regulatory guide DG-7004

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents -

TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents

Regulatory guide 1.168 (draft was issued as DG-1123) - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research.

Regulatory guide 1.168 (draft was issued as DG-1123)

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

Transactions of the 2004 Nuclear Safety Research Conference - Nuclear Safety Research Conference (2004 Washington D.C.)

Transactions of the 2004 Nuclear Safety Research Conference

Nuclear Safety Research Conference (2004 Washington D.C.)

Draft regulatory guide DG-7004 - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research.

Draft regulatory guide DG-7004

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

Regulatory analysis guidelines of the U.S. Nuclear Regulatory Commission - U.S. Nuclear Regulatory Commission. Division Of Systems Analysis And Regulatory Effectiveness

Regulatory analysis guidelines of the U.S. Nuclear Regulatory Commission

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness

EPRI/NRC-RES fire PRA methodology for nuclear power facilities - U.S. Nuclear Regulatory Commission. Office Of Nuclear Regulatory Research

EPRI/NRC-RES fire PRA methodology for nuclear power facilities

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Fort Saint Vrain gas cooled reactor operational experience - D. A. Copinger

Fort Saint Vrain gas cooled reactor operational experience

D. A. Copinger