Core Disruptive Accident Analysis using ASTERIA-FBR-Reference-Cited by-同舟云学术

Core Disruptive Accident Analysis using ASTERIA-FBR

Published:2014 Issue: Volume: Page:
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Container-title:SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
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Author:

Ishizu Tomoko,Endo Hiroshi,Yamamoto Toshihisa,Tatewaki Isao

Abstract

JNES is developing a core disruptive accident analysis code, ASTERIA-FBR, which tightly couples the thermal-hydraulics and the neutronics to simulate the core behavior during core disruptive accidents of fast breeder reactors (FBRs). ASTERIA-FBR consists of the three-dimensional thermal-hydraulics calculation module: CONCORD, the fuel pin behavior calculation module: FEMAXI-FBR, and the space-time neutronics module: Dynamic-GMVP or PARTISN/RKIN. This paper describes a comparison between characteristics of GMVP and PARTISN and summarizes the challenging issues on applying Dynamic-GMVP to the calculation against unprotected loss-of-flow (ULOF) event which is a typical initiator of core disruptive accident of FBR. The statistical error included in the calculation results may affect the super-prompt criticality during ULOF event and thus the amount of released energy.

Publisher

EDP Sciences

Link

http://sna-and-mc-2013-proceedings.edpsciences.org/10.1051/snamc/201401402/pdf

Reference15 articles.

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3. Ishizu T., Endo H., Tatewaki I., Yamamoto T., and Shirakawa N., “Development of Integrated Core Disruptive Accident Analysis Code for FBR – ASTERIA-FBR,” Proceedings of ICAPP’12, Chicago, USA, June 24-28 (2012)

4. Ishizu T., Endo H., Yamamoto Y., Shirakawa N., “Development of Core Disruptive Accident Analysis Code–ASTERIA-FBR (5) Validation of thermal-hydraulics calculation module (2),” Annual meeting of AESJ, 2012 [in Japanese]

5. Sensitivity analysis of fuel pin failure performance under slow-ramp type transient overpower condition by using a fuel performance analysis code FEMAXI-FBR