The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA

Jong-Rong Wang

PWR no jiko shīkensu no shikaiseki

Final report on the PMK-2 projects.

The 2007-2012 World Outlook for Hand-Portable Foam, Halogenated Agent, and Pressurized Water Fire Extinguishers

Philip M. Parker

Kiki furajiriti hyōka (PWR puranto).

Istorii︠a︡ sozdanii︠a︡ reaktornykh ustanovok VVĖR dli︠a︡ atomnykh ėlektrostant︠s︡iĭ

V. P. Denisov

GSI-191 technical assessment

Voltage-based alternative repair criteria

RELAP5/MOD3.2 validation using BETHSY test 6.9a

S. Bouabdallah

RELAP5/MOD3.2 validation using BETHSY test 6.9a

S. Bouabdallah

RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA

W Tietsch

Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

Sarah E. Colpo

RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA

W. Tietsch

Action requirements for AFW system failures

Assessment of RELAP5/MOD3.2 with the semiscale natural circulation experiment, S-NC-8B

U.S. Department of Energy reactor core protection evaluation methodology for fires at Soviet-designed RBMK and VVER nuclear power plants

Two-phase fluid break flow measurements and scaling in the advanced plant experiment (APEX)

David Alan Pimentel

Effect of aging on the PWR chemical and volume control system

E. J. Grove

Integrated systems analysis of the PIUS reactor

Numerics and implementation of the UK horizontal stratification entrainment off-take model into RELAP5/MOD3

W. M. Bryce

Analysis of LOFT test L5-1 using RELAP5/MOD2

S. Cooper

Assessment of BETHSY test 9.1.b using RELAP5/MOD3

S. Lee

Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant

Anders Sjöberg

Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant

F Pelayo

Assessment of TRAC-PF1/MOD1 against an inadvertent steam line isolation valve closure in the Ringhals 2 power plant

F. Pelayo

Assessment of TRAC-PF1/MOD1 using Strathclyde 1/10 scale model refill tests

Post-test analysis of LOBI test BT-12 using RELAP5/MOD2

A. J. Smethurst

Auxiliary feedwater system risk-based inspection guide for the Virgil C. Summer Nuclear Power Plant

Aging assessment of the Westinghouse PWR control rod drive system

W. Gunther

RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01

P. C Hall

Generic risk insights for Westinghouse and Combustion Engineering pressurized water reactors

Analysis of H.B. Robinson PWR vessel fluence for cycle 10 utilizing partial length shield assemblies

M. L. Williams

Proceedings of the Third International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth

International Atomic Energy Agency Specialists' Meeting on Subcritical Crack Growth (3rd 1990 Moscow, R.S.F.S.R.)

Analysis of the THETIS boildown experiments using RELAP5/MOD2

M. G. Croxford

Thermal-hydraulic research plan for Babcock and Wilcox plants

R. Y Lee

British PWR.

Integrated plant safety assessment, systematic evaluation program

Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor

Wallis R. Cramond

Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting

Water Reactor Safety Information Meeting (15th 1987 Gaithersburg, Md.)

Sizewell B public inquiry

F. H. B. Layfield

Integrated plant safety assessment

Summary report for LOFT anticipated transient experiment series L6-8

Charles L. Nalezny

Assessment of selected TRAC and RELAP5 calculations for Oconee-1 pressurized thermal shock study

USI A-43 resolution positions

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

Mechanistic core-wide meltdown and relocation modeling for BWR applications

M. Podowski

Ya shui dui he dian zhan di yun xing

Jizhou Zhu

Critical flow modelling in nuclear safety

Study guide for Thermal analysis of pressurized water reactors

Joel Weisman

Standard technical specifications for Westinghouse pressurized water reactors

Need for the pressurised water reactor

Sam Goddard

Problems in modeling of small break LOCA

N. Zuber

Analysis of ECC bypass data

W. D Beckner

Draft environmental statement by the Directorate of Licensing, United States Atomic Energy Commission, related to the proposed Washington Public Power Supply System Nuclear Projects 1 and 4.

U.S. Atomic Energy Commission. Directorate of Licensing.

Mathematical model of the uncooled spherical surge tank pressurizer of a pressurized-water nuclear power plant.

Joseph Delta Lafleur

Avaliações

Livros semelhantes