共 7 条
- [1] CHATELARD P, REINKE N, ARNDT S, Et al., ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives, Nuclear Engineering and Design, 272, pp. 119-135, (2014)
- [2] CANTREL L, COUSIN F, BOSLAND L, Et al., ASTEC V2 severe accident integral code: fission product modelling and validation, Nuclear Engineering and Design, 272, pp. 195-206, (2014)
- [3] BOSLAND L., ASTEC v2.0 rev2 code iode module: iodine and ruthenium behavior in the containment: Rev. 1, DPAM-SEMIC-2011-345, (2011)
- [4] HU W C, ZHAO C Q, BI J S, Et al., ASTEC simulation of fission product source term ruthenium in coolant in severe accident, Annals of Nuclear Energy, 133, pp. 658-664, (2019)
- [5] SOFFER L, BURSON S B, FERRELL C M, Et al., Accident source terms for light-water nuclear power plants: NUREG-1465, (1995)
- [6] BAKER L, RITZMAN R L, FINK J K, Et al., Summary results of the treat source term experiments project (STEP), Proceedings of the International ENS/ANS Conference on Thermal Reactor Safety, pp. 2127-2136, (1988)
- [7] OSETEK D J, CRONENBERG A W, HOBBINS R R, Et al., Fission product behaviour during the first two PBF severe fuel damage tests, American Nuclear Society Meeting on Fission Product Behaviour and Source Term Research, (1985)