References
- Terada , A. , Iwatsuki , J. Ishikura , S. 2007 . “Development of hydrogen production technology by thermochemical water splitting IS process” . J. Nucl. Sci. Technol. , 44 ( 3 ) : 477 – 482 .
- Idaho National Laboratory, Oak Ridge National Laboratory, Argonne National Laboratory . 2005 . Next Generation Nuclear Plant Research and Development Program Plan , INEEL/EXT-05–02581 Idaho National Engineering and Environmental Laboratory (INEEL) .
- Ehster , S. , Dominguez , M. T. Mansani , L. 2005 . “Important viewpoints proposed for a safety approach of HTGR reactor in Europe” . In Proc. ICENES 2005 Brussels , , Belgium Aug. 21–26, 2005
- Kunitomi , K. , Yan , X. , Nishihara , T. Sakaba , N. 2007 . “JAEA's VHTR for hydrogen and electricity cogeneration: GTHTR300C” . Nucl. Eng. Technol. , 39 ( 1 ) : 9 – 20 .
- Sakaba , N. , Tachibana , Y. Shimakawa , S. 2008 . Examination on Small-Sized Cogeneration HTGR for Developing Countries , JAEA-Technology 2008–019 Japan Atomic Energy Agency (JAEA) .
- Saito , S. , Tanaka , T. Sudo , Y. 1994 . Design of High Temperature Engineering Test Reactor (HTTR) , JAERI 1332 Japan Atomic Energy Research Institute (JAERI) .
- Goto , M. , Nojiri , N. and Shimakawa , S. 2006 . “Neutronics calculations of HTTR with several nuclear data libraries” . J. Nucl. Sci. Technol. , 43 ( 10 ) : 1237 – 1244 .
- Shibata , K. , Iwamoto , O. Nakagawa , T. 2010 . “JENDL-4.0: A new library for innovative nuclear energy systems” . In Proc. Int. Conf. on Nuclear Data for Science and Technology (ND2010) Jeju Island , , Korea Apr. 26–30, 2010
- Firestone , R. B. , Krticka , M. McNabbet , D. P. 2007 . “New methods for the determination of total radiative thermal neutron capture cross sections” . In Proc. 2007 Int. Workshop on Compound-Nucleus Reactions and Related Topics Yosemite , , USA Oct. 22–26, 2007
- Shibata , K. 1983 . Evaluation of Neutron Nuclear Data for 12C , JAERI-M 83–221 Japan Atomic Energy Research Institute (JAERI) .
- Los Alamos National Laboratory . T-2 Nuclear Information Service http://t2.lanl.gov/data/data/ENDFB-VII-neutron/C/nat
- Kinsey , R. 1979 . ENDF/B Summary documentation , BNL-NCS-17541 Brookhaven National Laboratory (BNL) .
- Koning , A. , Forrest , R. Kellett , M. 2006 . The JEFF-3.1 Nuclear Data Library , JEFF Report 21 OECD/NEA .
- Nagaya , Y. , Okumura , K. Mori , T. 2005 . MVP/GMVPII: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods , JAERI 1348 Japan Atomic Energy Research Institute (JAERI) .
- Murata , I. , Mori , T. Nagaya , M. 1996 . Continuous Energy Monte Carlo Calculations for Randomly Distributed Spherical Fuels Based on Statistical Geometry Model , JAERI-Research 96–015 Japan Atomic Energy Research Institute (JAERI) . [in Japanese]
- Nojiri , N. , Shimakawa , S. Fujimoto , N. 2004 . “Characteristics test of initial HTTR core” . Nucl. Eng. Des. , 233 : 283