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

Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors : Volume 1

Francesco D'Auria

Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors : Volume 2

Francesco D'Auria

Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors : Volume 3

Francesco D'Auria

Photochemistry of Heterocycles

Maurizio D'Auria

Photochemistry of Heterocycles

Maurizio D'Auria

Olga Kurylenko

Patrice D'AURIA

Dark Angel

Patrice D'AURIA

Silence the Birchwoods

Auria Jourdain

Visions and Ideas of Europe During the First World War

Matthew D'Auria

Jessica

Patrice D'AURIA

Jessica Alba

Patrice D'AURIA

Shaping of French National Identity

Matthew D'Auria

Ten Lessons in Leadership and Learning

John D'Auria

Infante Prodigi

Patrice D'AURIA

Shaping of French National Identity

Matthew D'Auria

Making Sense of Violence

Matthew D'Auria

Making Sense of Violence

Matthew D'Auria

Fills y Solos en Batería

Oscar D´Auria

Rileggere Pompei VI. la Casa Del Granduca Michele (VI,5,5) e le Case Di Livello Medio a Pompei in Eta Sannitica

Dora D'Auria

Visions and Ideas of Europe During the First World War

Matthew D'Auria

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Francesco D'Auria

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Francesco D'Auria

My Origami Ocean Kit

Pasquale D'Auria

Rosa Antica Di Pompei

Alessia D'Auria

From Special Relativity to Feynman Diagrams

Riccardo D'Auria

From Special Relativity to Feynman Diagrams

Riccardo D'Auria

Veli d'Arabia

Eugenio D'Auria

50 Most Secret Never To Know With Horse

Auria Bawdekar

50 Most Secret Never To Know With Elephant

Auria Bawdekar

La cara de la muerte

Verónica D'Auria

Francesco Mauro

Maurizio D'Auria

La vicenda umana e intellettuale di Ernst Hartwig Kantorowicz

Adelaide D'Auria

Architettura e arti applicate negli anni Cinquanta

Antonio D'Auria

From Special Relativity to Feynman Diagrams

R. D'Auria

Leggere lo sport

Francesca Petrocchi D'Auria

Einer von Millionen

Francesco Paolo D'Auria

My Blood Is Royal

Joyce D'Auria

Contributi di letteratura comparata

Francesca Petrocchi D'Auria

Il pragmatismo flessibile

Chiara D'Auria

Le parole della musica

Francesca Petrocchi D'Auria

Offerings to the Discerning Eye

Sue D'Auria

Contra los jueces

Aníbal A. D'Auria

Servant of Mut

Sue D'Auria

Inganno, frode, deliberazione

Andrea D'Auria

Il matrimonio nel diritto della Chiesa

Angelo D'Auria

Esperienze e scritture di viaggio lungo il primo trentennio del Novecento

Francesca Petrocchi D'Auria

Ordine di Malta nel Mezzogiorno d'Italia

Alfredo D'Auria

Brouillard sur l'Etna

Pascale Védère d'Auria

Elena degli Angeli

Adriano 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

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

F D'Auria

Sa majesté le chat

Pascale Védère d'Auria

Une belle vie de lapin

Pascale Védère d'Auria

Por la orilla del río

Pascale Védère d'Auria

Ist Europa ein optimaler Währungsraum?

Laura Auria

Scrittori italiani e fascismo

Francesca Petrocchi D'Auria

Profili di "italianisants"

Francesca Petrocchi D'Auria

Mummies & magic

Sue D'Auria

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

Jong-Rong Wang

EPR, l'impasse nucléaire

Frédéric Marillier

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

GSI-191 technical assessment

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

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 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 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

Thermal analysis of pressurized water reactors

L. S. Tong

Applications of reliability degradation analysis

W. E. Vesley

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

Steam generator tube failures

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

Estimating pressurized water reactor decommissioning costs

M. C. Bierschbach

Effect of aging on the PWR chemical and volume control system

E. J. Grove

Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2

E. W. Coryell

Natural circulation phenomena in nuclear reactor systems

Franklin Cheung

2D/3D program work summary report

Pressurized-water reactor internals aging degradation study

K. H. Luk

Integrated systems analysis of the PIUS reactor

Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera nuclear station

R. Arroyo

Auxiliary feedwater system risk-based inspection guide for the Beaver Valley, units 1 and 2, nuclear power plants

Numerics and implementation of the UK horizontal stratification entrainment off-take model into RELAP5MOD3

W. M Bryce

Voltage-based interim plugging criteria for steam generator tubes

U.S. Nuclear Regulatory Commission. IPC Task Group

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

Post-test-analysis and nodalization studies of OECD LOFT experiment LP-LB-1 with RELAP5/MOD2 CY36-02

D Lubbesmeyer

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

F Pelayo

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

A. J Smethurst

Risk evaluation for a B&W pressurized water reactor, effects of fire protection system actuation on safety-related equipment

Thermal-hydraulic processes during reduced inventory operation with loss of residual heat removal