ASTEC validation on TMI-2 and LOFT LP-FP-2-Reference-Cited by-同舟云学术

ASTEC validation on TMI-2 and LOFT LP-FP-2

Published:2014-06 Issue: Volume:272 Page:163-172
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bandini Giacomino,De Rosa Felice

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference8 articles.

1. A scenario of the Three Mile Island Unit 2 accident;Broughton;Nuclear Technology,1989

2. ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives;Chatelard;Nuclear Engineering and Design,2014

3. Summary of Important Results and SCDAP/RELAP5 Analysis for OECD LOFT Experiment LP-FP-2. NUREG/CR-6160, NEA-CSNI-R(94)3, EGG-2721;Coryel,1994

4. Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding – Benchmark Exercise on an Alternative TMI-2 Accident Scenario. NEA/CSNI/R(2009)3;Fichot,2009

5. Thermal-Hydraulic Post-Test Analysis of OECD LOFT LP-FP-2 Experiment. International Agreement Report, NUREG/IA-0049/ICSP-LP-FP-2;Pena,1992

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1. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

2. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: Analysis of RCS thermal-hydraulics and in-vessel phenomena;Nuclear Engineering and Design;2022-02

5. Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review;Annals of Nuclear Energy;2019-09