Art

J-GLOBAL ID：201402223498429735   Reference number：14A0339211

Preliminary Accident Analysis for a Conceptual Design of a 10MW Multi-purpose Research Reactor

10MW級多目的研究炉の概念設計のための予備的な事故解析

Author (6)： PARK Cheol (Japan Atomic Energy Agency, Ibaraki-ken) ,  TANIMOTO Masataka (Japan Atomic Energy Agency, Ibaraki-ken) ,  IMAIZUMI Tomomi (Japan Atomic Energy Agency, Ibaraki-ken) ,  MIYAUCHI Masaru (Japan Atomic Energy Agency, Ibaraki-ken) ,  ITO Masayasu (Japan Atomic Energy Agency, Ibaraki-ken) ,  KAMINAGA Masanori (Japan Atomic Energy Agency, Ibaraki-ken)
Material： 日本原子力研究開発機構JAEA-Technology(Web)
Issue： 2012-039  Page： WEB ONLY  Publication year： Jan. 2013 
JST Material Number： U0305A  Document type： Article
Article type： 原著論文  Country of issue： Japan (JPN)  Language： ENGLISH (EN)

Thesaurus term： *multipurpose reactor ,  research reactor ,  *loss of coolant ,  *reactivity insertion accident ,  safety analysis ,  *accident analysis ,  computer code ,  preliminary research ,  analytical model ,  conceptual design

JST classification (2)： Safety of watercooled reactors  (MD06020H) ,  Other applications and utilization of reactor  (MD07040K)

Reference (27)：

• T. Imaizumi et.al, Conceptual Design of a Multipurpose Low-Power Research Reactor, JAEA-Technology 2011-031, 2011.
• Safety of research reactors - Safety requirements, IAEA SS No.NS-R-4, IAEA, 2005.
• Safety Evaluation Report related to the evaluation of LEU silicide-aluminum dispersion fuel for use in non-power reactors, NUREG-1313, US NRC, 1988.
• M.Kaminaga et.al, “Improvement of CHF Correlation for Research Reactors using Plate Type Fuel”, Journal of Science and Technology, Vol 35, Dec. 1998.
• RELAP5/MOD3 Code Manual Volume 1 : Code Structure, System Models, and Solution Methods”, Scientech, Inc. , NUREG/CR-5535 (1998).

Terms in the title (4)： 多目的 ,  研究 ,  概念設計 ,  事故解析