DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA-Reference-Cited by-同舟云学术

DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA

Published:2018-12 Issue: Volume:339 Page:202-214
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Glantz T.,Taurines T.,Belon S.,De Luze O.,Guillard G.,Jacq F.

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

Reference33 articles.

1. OECD/NEA: Sandia fuel project phase I: benchmark of ignition testing;Adorni;Nucl. Eng. Des.,2016

2. Adroguer, B., Commande, A., Rongier, C., M., M., 1992. International standard problem n28 PHEBUS SFD B9+ experiment on the degradation of PWR type core. Comparison report. OCDE/NEA-CSNI/R(92)17 I and II.

3. Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation;Bandini;Prog. Nucl. Energy,2010

4. Development and validation of the multi-physics DRACCAR code;Bascou;Ann. Nucl. Energy,2015

5. Bazin, P., 1995. ROSCO programme: experimental effects of oscillations and of fuel simulator structure on reflooding. In: Proc. of the 3rd International Conference on Nuclear Engineering, Kyoto, April.

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