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

RELAP5/MOD3.2 validation using BETHSY test 6.9a

S. 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

EPR, l'impasse nucléaire

Frédéric Marillier

Akushidento manejimento chishiki bēsu seibi ni kansuru hōkokusho.

Akushidento manejimento chishiki bēsu seibi ni kansuru hōkokusho.

Roshin sonshō ni taisuru risuku jūyōdo ni motoduku haikan no bunrui to taiōsuru kensa ni kansuru kentō (PWR).

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).

Study of hydride blisters grown on Zr-2.5Nb pressure tube spool piece under simulated condition of in-reactor pressure and temperature

Istorii︠a︡ sozdanii︠a︡ reaktornykh ustanovok VVĖR dli︠a︡ atomnykh ėlektrostant︠s︡iĭ

V. P. Denisov

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions

S. Majumdar

U.S. operating experience with thermally treated Alloy 600 steam generator tubes

K. J. Karwoski

GSI-191 technical assessment

Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant

C. Llopis

Standard technical specifications

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

Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA

V. A Vinogradov

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data

F. Odar

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data

F Odar

Voltage-based alternative repair criteria

Voltage-based alternative repair criteria

RELAP5/MOD3.2 validation using BETHSY test 6.9a

S. Bouabdallah

Simulation of LOCA 6" and LOCA 2" transients in the RHR of a PWR under low power conditions using RELAP5/MOD3.2

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

RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44

F D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44

F. D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03

F. D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44

F. D'Auria

Test LOBI-BL06

T Fiore

Analysis of the critical flow model in TRAC-BF1

M Gómez

RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03

F D'Auria

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

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

Estimating probable flaw distributions in PWR steam generator tubes

Study of transients related to AMSAC actuation, sensitivity analysis

Resolution of the direct containment heating issue for combustion engineering p and Babcock & Wilcox plants

Result of BETHSY test 9.1.b using RELAP5/MOD2

Assessment of pressurized water reactor primary system leaks

Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments

G. Th Analytis

Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01

Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant

C. Llopis

Evaluation of ultrasonic inspection techniques for coarse-grained materials

Final safety evaluation report related to certification of the AP600 standard design docket no. 52-003

Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS

Study of transients related to AMSAC actuation, sensitivity analysis

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6

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

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

Low pCo₂ concentrator development

F. H. Schubert

Estimated net value and uncertainty for automating ECCS switchover at PWRs

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

Thermal analysis of pressurized water reactors

L. S. Tong

Applications of reliability degradation analysis

W. E. Vesley