RELAP5/MOD3.2 validation using BETHSY test 6.9a

Saving ourselves

Yacine Belhaj-Bouabdallah

RELAP5/MOD3.2 validation using BETHSY test 6.9a

S. Bouabdallah

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

Jong-Rong Wang

Final report on the PMK-2 projects.

Istorii︠a︡ sozdanii︠a︡ reaktornykh ustanovok VVĖR dli︠a︡ atomnykh ėlektrostant︠s︡iĭ

V. P. Denisov

Voltage-based alternative repair criteria

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

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

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 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

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.)

British PWR.

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.)

Integrated plant safety assessment

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

Critical flow modelling in nuclear safety

Standard technical specifications for Westinghouse pressurized water reactors

Problems in modeling of small break LOCA

N. Zuber

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