| 1. |
Irwan Liapto SIMANULLANG, Yuki Honda, Yuji Fukaya, Minoru Goto, Yoske Shimazaki, 藤本 望, Shoji Takada, Calculation of Decay Heat by ORIGEN Libraries for High Temperature engineering Test Reactor, 2016.09, これまで高温工学試験研究炉の崩壊熱は、軽水炉のデータを基にしたShure の式やORIGEN計算で評価してきたが、厳密には軽水炉の中性子スペクトルと異なることから最適な評価方法を検討する必要がある。このため、黒鉛減速材量を変えた炉心の中性子スペクトルを用い、ORIGEN2コードで崩壊熱及び生成核種を計算して軽水炉の崩壊熱曲線と比較した。. |
| 2. |
Nozomu Fujimoto, H. Wang, Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2009, 2010.07, The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2009.. |
| 3. |
Nozomu Fujimoto, Yukio Tachibana, Y. Sun, Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2008, 2009.07, The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2008.. |
| 4. |
Nozomu Fujimoto, Yukio Tachibana, Nariaki Sakaba, Ryutaro Hino, S. Yu, Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2007, 2008.06, The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2007.. |
| 5. |
Akio Saikusa, Shigeaki Nakagawa, Nozomu Fujimoto, Yukio Tachibana, Tatsuo Iyoku, Data on test results of vessel cooling system of High Temperature Engineering Test Reactor, 2003.02, High Temperature Engineering Test Reactor (HTTR) is the first graphite-moderated helium gas cooled reactor in Japan. The rise-to-power test of the HTTR started on September 28,1999 and thermal power of the HTTR reached its full power of 30 MW on December 7, 2001. Vessel Cooling System (VCS) of the HTTR is a first Reactor Cavity Cooling System applied for High Temperature Gas Cooled Reactors. The VCS cools the core indirectly through the reactor pressure vessel to keep core integrity during the loss of core flow accidents such as depressurization accident. Minimum heat removal of the VCS to satisfy its safety requirement is 0.3MW at 30 MW power operation. Through the performance test of the VCS in the rise-to-power test of the HTTR, it is confirmed that the VCS heat removal at 30 MW power operation is higher than 0.3MW. This paper shows outline of the VCS and test results on the VCS performance.. |
| 6. |
Takeshi TAKEDA, Shigeaki NAKAGAWA, Nozomu FUJIMOTO, Tatsuo IYOKU, Data on loss of off-site electric power simulation tests of the High Temperature Engineering Test Reactor, 2002.07. |
| 7. |
Nozomu FUJIMOTO, Ursula OHLIG, Hans BROCKMANN, Kiyonobu YAMASHITA, Analysis of the HTTR's benchmark problems and comparison between the HTTR and the FZJ code systems, 1998.11, The first Research Coordination Meeting for the Coordinated Research Program on the HTTR benchmark problems were held in August 1998. The results and calculation models of JAERI and Forshcungszentrum Jiilich GmbH (FZJ) by diffusion calculation were compared. Both results showed a good agreement at fully-loaded core but the results of JAERI showed about 1 %Ak higher value during fuel loading state. To investigate the cause of the difference, effects of energy group number, neutron streaming from control rod insertion holes and cell models of burnable poison (BP) were studied. As the results, we found that the difference caused by energy group number and neutron streaming were small. The effect of BP cell model was evaluated by sensitivity analysis of dimension of BP cell. Improvements for each calculation model were proposed.. |
| 8. |
Nozomu Fujimoto, Kiyonobu Yamashita, H. J. Rütten, Study on temperature coefficients of actinide burning HTGRs, 1997.11. |
