Tài liệu tham khảo |
Loại |
Chi tiết |
[1] Masaki Amaya and Mutsumi Hirai (1997), “Recovery behavior of thermal conductivity in irradiated U02 pellets ”, Journal of nuclear materials, 247, pp. 76–81 |
Sách, tạp chí |
Tiêu đề: |
Recovery behavior of thermalconductivity in irradiated U02pellets |
Tác giả: |
Masaki Amaya and Mutsumi Hirai |
Năm: |
1997 |
|
[2] Masaki Amaya et al. (1996), “Thermal conductivity measurements on 10 wt% Gd 2 0 3 doped U0 2 + x”, Journal of nuclear materials, 231 (1-2), pp. 29–33 |
Sách, tạp chí |
Tiêu đề: |
Thermal conductivity measurements on10 wt% Gd203 doped U02+ x |
Tác giả: |
Masaki Amaya et al |
Năm: |
1996 |
|
[3] Marielle Asou and Jacques Porta (1997), “Prospects for poisoning reactor cores of the future”, Nuclear engineering and design, 168 (1-3), pp. 261–270 |
Sách, tạp chí |
Tiêu đề: |
Prospects for poisoning reactorcores of the future |
Tác giả: |
Marielle Asou and Jacques Porta |
Năm: |
1997 |
|
[4] D Balestrieri (1998), “A study of the UO 2 – Gd 2 O 3 composite fuel”, Fuel pellet technology for improved performance at high burnup, p. 63 |
Sách, tạp chí |
Tiêu đề: |
Fuel pellet technology for improved performance at high burnup |
Tác giả: |
D Balestrieri |
Năm: |
1998 |
|
[5] D BARON and JC COUTY (1997), “A proposal for a unified fuel thermal conductivity model available for UO 2 ,(U-Pu)O 2 and UO 2 –Gd 2 O 3 PWR fuel”, Water reactor fuel element modelling at high burnup and its exper- imental support, p. 229 |
Sách, tạp chí |
Tiêu đề: |
Water reactor fuel element modelling at high burnup and its experimental support |
Tác giả: |
D BARON, JC COUTY |
Năm: |
1997 |
|
[6] C Behar et al. (2014), “Technology roadmap update for generation IV nuclear energy systems”, Organisation for Economic Co-operation and Development/Nuclear Energy Agency |
Sách, tạp chí |
Tiêu đề: |
Technology roadmap update for generation IVnuclear energy systems |
Tác giả: |
C Behar et al |
Năm: |
2014 |
|
[7] Joseph Raymond Burns (2015), “Reactivity control of a PWR 19x19 ura- nium silicide fuel assembly”, Georgia Tech Electronic Thesis and Disser- tation Archive |
Sách, tạp chí |
Tiêu đề: |
Reactivity control of a PWR 19x19 uranium silicide fuel assembly |
Tác giả: |
Joseph Raymond Burns |
Nhà XB: |
Georgia Tech Electronic Thesis and Dissertation Archive |
Năm: |
2015 |
|
[8] Mark B Chadwick et al. (2011), “ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data”, Nuclear data sheets, 112 (12), pp. 2887–2996 |
Sách, tạp chí |
Tiêu đề: |
ENDF/B-VII. 1 nuclear data for scienceand technology: cross sections, covariances, fission product yields anddecay data |
Tác giả: |
Mark B Chadwick et al |
Năm: |
2011 |
|
[9] Paul K Chan, Stephane Paquette, and Hugues W Bonin (2015), “Varia- tion of Burnable Neutron Absorbers in a Heavy Water Moderated Fuel Lattice: A Potential to Improve CANDU Reactor Operating Margins”, Nuclear Technology, 191 (1), pp. 1–14 |
Sách, tạp chí |
Tiêu đề: |
Variation of Burnable Neutron Absorbers in a Heavy Water Moderated Fuel Lattice: A Potential to Improve CANDU Reactor Operating Margins |
Tác giả: |
Paul K Chan, Stephane Paquette, Hugues W Bonin |
Nhà XB: |
Nuclear Technology |
Năm: |
2015 |
|
[10] Jiwon Choe, Ho Cheol Shin, and Deokjung Lee (2016), “New burnable absorber for long-cycle low boron operation of PWRs”, Annals of Nuclear Energy, 88, pp. 272–279 |
Sách, tạp chí |
Tiêu đề: |
New burnable absorber for long-cycle low boron operation of PWRs |
Tác giả: |
Jiwon Choe, Ho Cheol Shin, Deokjung Lee |
Nhà XB: |
Annals of Nuclear Energy |
Năm: |
2016 |
|
[11] Aiman Dandi, MinJae Lee, and Myung Hyun Kim (2020), “Feasibility of combinational burnable poison pins for 24-month cycle PWR reload core”, Nuclear Engineering and Technology, 52 (2), pp. 238–247 |
Sách, tạp chí |
Tiêu đề: |
Feasibility of combinational burnable poison pins for 24-month cycle PWR reload core |
Tác giả: |
Aiman Dandi, MinJae Lee, Myung Hyun Kim |
Nhà XB: |
Nuclear Engineering and Technology |
Năm: |
2020 |
|
[12] James J Duderstadt and Louis J Hamilton (1976), Nuclear reactor anal- ysis, John Wiley and Sons, Inc. ISBN 0-471-22363-8 |
Sách, tạp chí |
Tiêu đề: |
Nuclear reactor analysis |
Tác giả: |
James J Duderstadt, Louis J Hamilton |
Nhà XB: |
John Wiley and Sons, Inc. |
Năm: |
1976 |
|
[13] Van Khanh E Hoang and Hoai Nam Tran (2011), “Benchmark Calcula- tions For A VVER-1000 Assembly Using SRAC”, Proceedings of the 9 th National Conference on Nuclear Science and Technology, 3, pp. 129–134 |
Sách, tạp chí |
Tiêu đề: |
Benchmark Calcula- tions For A VVER-1000 Assembly Using SRAC |
Tác giả: |
Van Khanh E Hoang, Hoai Nam Tran |
Nhà XB: |
Proceedings of the 9 th National Conference on Nuclear Science and Technology |
Năm: |
2011 |
|
[14] H El Yaakoubi et al. (2019), “Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors”, Journal of King Saud University-Science, 31 (4), pp. 1271–1275 |
Sách, tạp chí |
Tiêu đề: |
Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors |
Tác giả: |
H El Yaakoubi, et al |
Nhà XB: |
Journal of King Saud University-Science |
Năm: |
2019 |
|
[15] C Forsberg, M. Kazimi, and E. J. Moniz (2010), “The Future of the Nuclear Fuel Cycle”, Massachusetts Institute of Technology |
Sách, tạp chí |
Tiêu đề: |
The Future of the Nuclear Fuel Cycle |
Tác giả: |
C Forsberg, M. Kazimi, E. J. Moniz |
Nhà XB: |
Massachusetts Institute of Technology |
Năm: |
2010 |
|
[16] JL Franácois et al. (2003), “A practical optimization procedure for radial BWR fuel lattice design using tabu search with a multiobjective function”, Annals of Nuclear Energy, 30 (12), pp. 1213–1229 |
Sách, tạp chí |
Tiêu đề: |
A practical optimization procedure for radial BWR fuel lattice design using tabu search with a multiobjective function |
Tác giả: |
JL Franácois, et al |
Nhà XB: |
Annals of Nuclear Energy |
Năm: |
2003 |
|
[17] A Abdelghafar Galahom (2016), “Investigation of different burnable ab- sorbers effects on the neutronic characteristics of PWR assembly”, Annals of Nuclear Energy, 94, pp. 22–31 |
Sách, tạp chí |
Tiêu đề: |
Investigation of different burnable absorbers effects on the neutronic characteristics of PWR assembly |
Tác giả: |
A Abdelghafar Galahom |
Nhà XB: |
Annals of Nuclear Energy |
Năm: |
2016 |
|
[18] A Abdelghafar Galahom (2018), “Simulate the effect of integral burnable absorber on the neutronic characteristics of a PWR assembly”, Nuclear Energy and Technology, 4, p. 287 |
Sách, tạp chí |
Tiêu đề: |
Simulate the effect of integral burnable absorber on the neutronic characteristics of a PWR assembly |
Tác giả: |
A Abdelghafar Galahom |
Nhà XB: |
Nuclear Energy and Technology |
Năm: |
2018 |
|
[19] A Abdelghafar Galahom (2020), “Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER- 1200”, Annals of Nuclear Energy, 148, p. 107758 |
Sách, tạp chí |
Tiêu đề: |
Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER- 1200 |
Tác giả: |
A Abdelghafar Galahom |
Nhà XB: |
Annals of Nuclear Energy |
Năm: |
2020 |
|
[20] Brian Vincent Haibach and Madeline A Feltus (1997), “A study on the op- timization of integral fuel burnable absorbers using the genetic algorithm based CIGARO fuel management system”, Annals of Nuclear Energy, 24 (6), pp. 439–448 |
Sách, tạp chí |
Tiêu đề: |
A study on the optimization of integral fuel burnable absorbers using the genetic algorithm based CIGARO fuel management system |
Tác giả: |
Brian Vincent Haibach, Madeline A Feltus |
Nhà XB: |
Annals of Nuclear Energy |
Năm: |
1997 |
|