[1] YANG Shiyan, HE Manli, JIANG Danfeng, et al. Optimization design of radiation shielding materials for 235U fission source in reactor[J]. Chinese Journal of Computational Physics, 2017, 34(1):73-81. [2] SHEN Yaosong, LI Kaibo, SHI Xueming, et al. Study on disposing high-level transuranic waste in a fusion fission reactor[J]. Chinese Journal of Computational Physics, 2017, 34(2):142-148. [3] HAN Wenjing. Numerical study and preliminary application of activation method based on CRAM[D]. North China Electric Power University, 2015. [4] PAMPIN R, DAVIS A, IZQUIERDO J, et al. Developments and needs in nuclear analysis of fusion technology[J]. Fusion Engineering & Design, 2013, 88(6-8):454-460. [5] ISOTALO A E, AARNIO P A. Comparison of depletion algorithms for large systems of nuclides[J]. Annals of Nuclear Energy, 2011, 38(2):261-268. [6] FENSIN M L, UMBEL M. Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculations[J]. Progress in Nuclear Energy, 2015, 85:719-728. [7] FORREST R A. FISPACT-2007:User manual[M]. EURATOM/UKAEA Fusion Association, 2007. [8] CROFF A G. A user's manual for ORIGEN2 computer code[R]. Oak Ridge National Laboratory, 1980. [9] CABELLOS O, SANZ J, RODRÍGUEZ A, et al. Sensitivity and uncertainty analysis to burnup estimates on ADS using the ACAB Code[C]//International Conference on Nuclear Data for Science & Technology, American Institute of Physics, 2005:1576-1579. [10] PUSA M, LEPPANEN J. Computing the matrix exponential in burnup calculations[J]. Nuclear Science and Engineering, 2010, 164(2):140-150. [11] FORREST R A. The European activation file:EAF-2007 decay data library[R]. UKAEA FUS 537, 2007. [12] FORREST R A. The European activation file:EAF-2007 neutron-induced cross section library[R]. UKAEA FUS 535, 2007. [13] BATEMAN H. The solution of differential equations occurring in the theory of radioactive transformations[C]//Proceedings of the Cambridge Philosophical Society, 1910, 15(5):423-427. [14] PUSA M. Rational approximations to the matrix exponential in burnup calculations[J]. Nuclear Science & Engineering the Journal of the American Nuclear Society, 2011, 169(2):155-167. [15] CARPENTER A J, RUTTAN A, VARGA R S. Extended numerical computations on the "1/9" conjecture in rational approximation theory[J]. Lectures Notes in Mathematics,1984, 1105(4):383-411. [16] ROSE D J, TARJAN R E. Algorithmic aspects of vertex elimination on directed graphs[J]. Siam Journal on Applied Mathematics, 1978, 34(1):176-197. [17] TARJAN R E. Graph theory and Gaussian elimination[J]. Sparse Matrix Computations, 1976:3-22. [18] SUBLET J C, EASTWOOD J W, MORGAN J G. The FISPACT-Ⅱ user manual[J]. CCFE-R, 2012, 11(11). [19] WRIXON A D. New ICRP recommendations[J]. Journal of Radiological Protection, 2008, 28(2):161-168. [20] YAMAMOTO M. Clearance levels for radionuclides and waste disosal:Approaches to develop concept and regulatory systems for clearance levels in overseas countries[J]. J-STAGE, 1999, 34(4):348-352. [21] FORREST R A,TABASSO A, DANANI C, et al. Handbook of activation data calculated using EASY-2007[J]. UKAEA FUS, 2009, 552:339. [22] SHIMOMURA Y, SAJI G. ITER safety and operational scenario[J]. Fusion Engineering & Design, 1998, s 39-40(3):17-32. [23] ZHANG Binhang, HAO Lijuan, et al. Research and verification of activation calculations based on Chebyshev rational approximation method[J]. Nuclear Science and Engineering, 2017, 37(1):65-72. |