Burn-up characteristics and criticality effect of impurities in the graphite structure of a commercial-scale prismatic HTGR

Nuclear Engineering and Design - Tập 326 - Trang 108-113 - 2018
Y. Fukaya1, M. Goto1, T. Nishihara1
1HTGR Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency (JAEA), 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 319-1395, Japan

Tài liệu tham khảo

Centaur Communications Ltd, 1956, Calder Hall Power Station, The Engineer, 5, 466 Croff, 1983, ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear material, Nucl. Technol., 62, 335, 10.13182/NT83-1 Fukaya, 2013 Fukaya, 2015 IAEA, 1993 IAEA, 2002 IAEA, 2003 Katanishi, 2007, Safety evaluation on the depressurization accident in the gas turbine high temperature reactor (GTHTR300), Nucl. Eng. Des., 237, 1372, 10.1016/j.nucengdes.2006.09.037 Kawakami, 1986, Air oxidation behavior of carbon and graphite materials for HTGR, Tanso, 124, 26, 10.7209/tanso.1986.26 Koning, 2006 Koning, 2011, Status of the JEFF nuclear data library, J. Korean Phys. Soc., 59, 1057, 10.3938/jkps.59.1057 Koning, A. J., Rochman, D., 2011b. TENDL-2011:TALYS-based Evaluated Nuclear Data Library. (URL:http://www.talys.eu/). MacFarlane, 2010, methods for processing ENDF/B-VII with NJOY, Nucl. Data Sheets, 111, 2739, 10.1016/j.nds.2010.11.001 Murata, 1997, New sampling method on continuous energy monte carlo calculation for pebble bed reactors, J. Nucl. Sci. Technol., 24, 734, 10.1080/18811248.1997.9733737 Nagaya, 2006, A Monte Carlo neutron/photon transport code MVP 2, Trans. Am. Nucl. Soc., 95, 662 Nakajima, Y., 1991. JNDC WG on Activation Cross Section Data: JENDL Activation Cross Section File. In: Proc. the 1990 Symposium on Nuclear Data, JAERI-M 91-032, Japan Atomic Energy Research Institute, 43–57. Nakata, 2002 Nakata, 2003, Nuclear, Thermal and Hydraulic Design for Gas Turbine High Temperature Reactor (GTHTR300), J. At. Energy Soc. Jpn., 2, 478 Nojiri, 1998 Saito, 1994 Shibata, 2011, JENDL-4.0: A new library for nuclear science and engineering, J. Nucl. Sci. Technol., 48, 1, 10.1080/18811248.2011.9711675 Sumita, 2003, Reprocessing technologies of the high temperature gas-cooled reactor (HTGR) fuel, J. At. Energy Soc. Jpn., 2, 546 Tanaka, T., 1999. Critical experiment of HTTR. Nuclear Data News, 63, (in Japanese). Yan, 2003, GTHTR300 design and development, Nucl. Eng. Des., 222, 247, 10.1016/S0029-5493(03)00030-X