Fuel element and full core thermal–hydraulic analysis of the AHTR for the evaluation of the LOFC transient-Reference-Cited by-同舟云学术

Fuel element and full core thermal–hydraulic analysis of the AHTR for the evaluation of the LOFC transient

Published:2014-02 Issue: Volume:64 Page:499-510
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Avigni P.,Petrovic B.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference8 articles.

1. RELAP5-3D Code Development Team, 2012. RELAP5-3D Code Manual Volume I: Code Structure, System Models and Solution Methods. Idaho National Laboratory, June, 2012. INEEL-EXT-98-00834.

2. Pre-conceptual design of a fluoride-salt-cooled Small Modular Advanced High-Temperature Reactor (SmAHTR);Greene;Oak Ridge National Laboratory,2010

3. Griveau, A., Peterson, F., 2006. RELAP5-3D Loss of Forced Cooling (LOFC) Transient Response Modeling for the PB-AHTR. In: Berkeley, U.C. September 17, 2006. UCBTH-06-003.

4. Core and refueling design studies for the advanced high temperature reactor;Holcomb;Oak Ridge National Laboratory,2011

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