Citation: | Tu Teng, Gao Shixin, Zhou Yi, Chen Ping, Zhang Ruiqian, Yang Qingfeng, Liao Nan. Simulation Analysis of FeCrAl-UN Fuel Rod Performance[J]. Nuclear Power Engineering, 2021, 42(S2): 165-170. doi: 10.13832/j.jnpe.2021.S2.0165 |
[1] |
BRAASE L, MAY W E. Advanced fuels campaign FY 2014 accomplishments report[R]. Idaho Falls: U. S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operaton Office, 2014.
|
[2] |
涂腾,李文杰,李伟,等. UN燃料性能数值分析[J]. 核动力工程,2017, 38(6): 185-188.
|
[3] |
涂腾,李文杰,陈平,等. UN燃料稳态和瞬态性能初步分析[J]. 中国核电,2017, 10(1): 335-340.
|
[4] |
MATTHEWS R B. Irradiation performance of nitride fuels[R]. Washington: Los Alamos National Laboratory, 1993.
|
[5] |
WU X, KOZLOWSKI T, HALES J D. Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions[J]. Annals of Nuclear Energy, 2015, 85: 763-775. doi: 10.1016/j.anucene.2015.06.032
|
[6] |
BATES J F, STRAALSUND J L. An empirical representation of irradiation-induced swelling of solution treated type 304 stainless steel[J]. Nuclear Technology, 1972, 14(3): 292-298. doi: 10.13182/NT72-A31119
|
[7] |
SWEET R, GEORGE N, TERRANI K, et al. BISON Fuel Performance Analysis of FeCrAl cladding with updated properties[R]. Oak Ridge: Oak Ridge National Laboratory, 2016.
|
[8] |
HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: II. Mechanical properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 271-288. doi: 10.1016/0022-3115(90)90375-W
|
[9] |
HAYES S L, ThOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: I. Physical properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 262-270. doi: 10.1016/0022-3115(90)90374-V
|
[10] |
HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: III. Transport properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 289-299. doi: 10.1016/0022-3115(90)90376-X
|
[11] |
HAYES S L, THOMAS J K, PEDDICORD K L. Material property correlations for uranium mononitride: IV. Thermodynamic properties[J]. Journal of Nuclear Materials, 1990, 171(2-3): 300-318. doi: 10.1016/0022-3115(90)90377-Y
|
[12] |
EL-GENK M S, ROSS S B, MATTHEWS R B. Uranium nitride fuel swelling and thermal conductivity correlations[C]//Proceedings of the Transactions of the Fourth Symposium on Space Nuclear Power Systems. 1987: 313-317
|
[13] |
STORMS E K. An equation which describes fission gas release from UN reactor fuel[J]. Journal of Nuclear Materials, 1988, 158: 119-129. doi: 10.1016/0022-3115(88)90161-4
|