Art

J-GLOBAL ID：201702233832220750   Reference number：17A0484072

Neutronic Characteristic of HTTR Fuel Compact with Various Packing Models of Coated Fuel Particle

様々な被覆粒子燃料充填モデルにおけるHTTR炉心の核特性評価

Author (4)： HO Hai Quan (Japan Atomic Energy Agency, Ibaraki-ken) ,  HONDA Yuki (Japan Atomic Energy Agency, Ibaraki-ken) ,  GOTO Minoru (Japan Atomic Energy Agency, Ibaraki-ken) ,  TAKADA Shoji (Japan Atomic Energy Agency, Ibaraki-ken)
Material： 日本原子力研究開発機構JAEA-Technology(Web)
Issue： 2016-040  Page： WEB ONLY  Publication year： Mar. 2017 
JST Material Number： U0305A  Document type： Article
Article type： 原著論文  Country of issue： Japan (JPN)  Language： ENGLISH (EN)

Thesaurus term： notch ,  *coated particle fuel ,  *HTGR type reactor ,  *Monte Carlo Method ,  computer code ,  nuclear data library ,  magnification ,  multiplication factor ,  self shielding ,  neutron flux ,  computation model ,  numerical calculation ,  MCNP code ,  effective multiplication ratio ,  High Temperature Engineering Test Reactor
Semi thesaurus term： high temperature engineering test reactor ,  ENDF(Nuclear Data)

JST classification (2)： Gas-cooled reactors  (MD03020M) ,  Reactor nuclear characteristics  (MD02040B)

Reference (15)：

• Saito S., et al., Design of high temperature engineering test reactor (HTTR). JAERI 1332, 1994, 247p.
• Mori, T., Nakagawa, M., MVP/GMVP: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods. JAERI-Data/Code 94-007, 1994, 388p.
• Naoki, N., et al., Characteristic test of initial HTTR core. Nuclear Engineering and Design, 233, 2004, pp.283-290.
• Goorley T., et al., Initial MCNP6 Release Overview. Nuclear Technology, 180, 2012, pp.298-315.
• Brown, F.B., Martin, W.R., Stochastic geometry capability in MCNP5 for the analysis of particle fuel. Ann. Nucl. Energy, 31, 2004, pp.2039-2047.

Terms in the title (5)： 被覆粒子燃料 ,  モデル ,  HTTR ,  核 ,  特性評価