|
[1]
|
Trkov A et al. Evaluated Nuclear Data for Th-U Fuel Cycle Summary Report of the Second Research Coordination Meeting, INDC(NDS)-0477. 2003[2] Yun D, Kim T K et al. Th/U-233 Multi-recycle in Pressurized Water Reactors, ANL-FCRD-309. 2010[3] Haas B. Brazilian Journal of Physics, 2004, 34: 814[4] Ge Z G et al. J. Korean Physical Society, 2011, 59(2): 1052-1056[5] Carlson A D, Pronyaev V G, Smith D L et al. Nucl. Data Sheets, 2009, 110: 3215[6] Leal L C, Derrien H, Harvey J A et al. R-Matrix Resonance Analysis and Statistical Properties of the Resonance Parameters of U-233 in the Neutron Energy Range from Thermal to 600 eV, ORNL/TM-2000/372, March 2001. 9222 1451 166[7] Chadwick M B, Obložinsk P, Herman M et al. Nucl. Data Sheets, 2006, 107: 2931[8] Shibata K, Iwamoto O, Nakagawa T et al. J. Nucl. Sci. Technol., 2011, 48(1): 1-30[9] YU Bao-Sheng, CHEN Guo-Chang. Communication of Nuclear Data Progress, 2003, 29: 13[10] OECD/NEA Data Bank. The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD/NEA Data Bank, 2009[11] Poenitz W P, Whalen J F, Guenther P et al. Nucl. Sci. Eng., 1978, 68: 358[12] Poenitz W P, Whalen J F, Smith A B. Nucl. Sci. Eng., 1981, 78: 333[13] Poenitz W P, Whalen J F. Neutron Total Cross Section Measurements in the Energy Region from 47 keV to 20 MeV, ANL-NDM-80. 1983[14] Behrens J W, Carlson G W, Bauser R W. Neutron induced fission cross sections of 233U, 234U, 236U and 238U with respect to 235U. Meet Fast Neutron Cross Section of U and Pu, Argonne, 1976. 47[15] Carlson G W, Behrens J W. Nucl. Sci. Eng., 1978, 66: 205[16] Poenitz W P. Argonne National Laboratory Reports, 1978, 36[17] Fursov B I, Kuprijanov V M, Smirenkin G N. Atomnaya Energiya, 1978, 44(3): 236[18] Kanda K, Imaruoka H, Yoshida K et al. Radiation Effects, 1986, 93: 233[19] Shpak D L, Smirenkin G N. Yadernaya Fizika, 1975, 21(4): 704[20] Shpak D L, Korolyov G G. All Union Conf.on Neutron Phys., 1980, 3: 35[21] Shpak D L. Physics of Atomic Nuclei, 1998, 61: 1333[22] Lisowski P W, Gavron A, Parker W E et al. Conf. on Nucl. Data for Sci. and Technol., 1991. 732[23] Shcherbakov O A, Donets A Yu, Evdokimov A V et al. Int. Sem. on Interactions of Neutrons with Nuclei, 2001, 9: 257[24] Tovesson F, Birgersson E, Fleneus M et al. Nuclear Physics A, 2004, 733(1): 3[25] Calviani M, Praena J, Abbondanno U et al. Phy. Rev. C, 2009, 80: 044604[26] Adamov V M, Aleksandrov B M, Alkhazov I D et al. Yadernye Konstanty, 1977, 24: 8[27] Alkhazov I D, Ganza E A, Drapchinskij L V et al. Meet. on Neutron Radiation Metrology, 1983, 2: 201[28] Zasadny K R, Agrawal H M, Mahdavi M et al. Transactions of the American Nuclear Society, 1984, 47: 425[29] Manabe F, Kanda K, Iwasaki T et al. Fac. of Engineering, Tohoku Univ. Tech. Report, 1988, 52(Issue 2): 97[30] Meadows J W. Annals of Nuclear Energy, 1988, 15: 421[31] Smith A B, Guenther P T. Conf. on Nuclear Data for Science and Technology, Antwerp, 1982. 39[32] Haouat G, Lachkar J, Lagrange C H et al. Nucl. Sci. Eng., 1982, 81: 491[33] Hopkins J C, Diven B C. Nucl. Sci. Eng., 1962, 12: 169[34] Taschek R F. EXFOR12364, 1955[35] ZHANG Jing-Shang. User Manual of FUNF code for Fissile Material Data Calculation, CNIC-01782. 2005[36] Raynal J. Notes on ECIS94, Centre d'Etudes Nucleaires (Saclay), CEA-N-2772. 1994 |
Abstract
HTML
Reference
Related
PDF
DownLoad: