Direct deterministic method for neutronics analysis and computation of asymptotic burnup distribution in a recirculating pebble-bed reactor

Annals of Nuclear Energy - Tập 29 - Trang 1345-1364 - 2002
W.K. Terry1, H.D. Gougar1, A.M. Ougouag1
1Idaho National Engineering and Environmental Laboratory, Nuclear Engineering Research and Design Division, P.O. Box 1625, Idaho Falls, ID 83415-3885, USA

Tài liệu tham khảo

Bedenig, 1968, Parameter studies concerning the flow behavior of a pebble with reference to the fuel element movement in the core of the THTR 300 MWe prototype reactor, NucI. Eng. Design., 7, 367, 10.1016/0029-5493(68)90068-X Izenson, M.G., 1986. Effects of Fuel Particle and Reactor Core Design on Modular HTGR Source Terms. Doctoral dissertation, Massachusetts Institute of Technology. Jung, 1981, Simultanlösung des Abbrand- und Durchlaufproblems der Kugeln bei Kugelhaufenreaktoren (simultaneous solution of the burn-up and fuel-movement problems in pebble-bed reactors), Atomkernenergie-Kerntechnik Bd., 38, 141 Liem, 1994, BATAN-MPASS, Ann. Nucl. Energy, 21, 281, 10.1016/0306-4549(94)90012-4 Liem, 1996, Design procedures for small pebble-bed high-temperature reactors, Ann. Nucl. Energy, 23, 207, 10.1016/0306-4549(95)00018-1 Massimo, 1976 Obara, 1991, New numerical method for equilibrium cycles of high conversion pebble bed reactors, J. Nucl. Sci. Technol., 28, 947, 10.3327/jnst.28.947 Sekimoto, 1987, New method to analyze equilibrium cycle of pebble-bed reactors, J. NucI. Sci. Technol., 24, 765, 10.3327/jnst.24.765 Terry, 2000, Deterministic method for fuel-cycle analysis in pebble-bed reactors, Trans. Am. Nucl. Soc., 83, 278 Teuchert, E., Hansen, U., Haas, K.A., 1980. V.S.O.P.—Computer Code System for Reactor Physics and Fuel Cycle Simulation. KFA-IRE Report Jül-1649. Vondy, D.R., Worley, B.A., 1979. Pebble Bed Reactor Core Physics and Fuel Cycle Analysis. ORNL 5484, Oak Ridge National Laboratory. Werner, 1997, Build-up of plutonium isotopes in HTR fuel elements—a comparison between computed prediction and chemical analysis, Nucl. Eng. Design, 170, 147, 10.1016/S0029-5493(97)00025-3