Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods-Reference-Cited by-同舟云学术

Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods

Published:2015-11 Issue: Volume:85 Page:830-836
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Liu Shichang,Wang Guanbo,Liang Jingang,Wu Gaochen,Wang Kan

Funder

CAEP

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Applied Reactor Physics;Hebert,2009

2. Hebert, A., Sekki, D., Chambon, R., et al., 2014. A user’s guide for DONJON 5. IGE–344.

3. Hosoya, T., Kato, T., Murayama, Y., 2007. Investigation of JRR-3 control rod worth changed with burn-up of follower fuel elements In: International Research Reactors: Safe Management and Effective Utilization, Australia.

4. IAEA, 2010. Available via web at: .

5. Iwasaki, J., Ichikawa, H., Tsuruta, H., 1984. Neutronics calculation of upgraded JRR-3 research reactor. Few-group constants, Japan Atomic Energy Research Inst., JAERI-M–84-159.

Cited by 6 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Fine-mesh homogenization and anisotropic SP3 calculation for PWR cores with plate-type fuel and strong absorbers;Annals of Nuclear Energy;2024-04

2. Fine-Mesh Homogenization and Anisotropic Sp3 Calculation for Pwr Cores with Plate-Type Fuel and Strong Absorbers;2023

3. Nuclear Data Sensitivity and Uncertainty Study for the Pressurized Water Reactor (PWR) Benchmark Using RMC and SCALE;Energies;2022-12-15

4. Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses;Journal of Nuclear Science and Technology;2022-08-21

5. Fuel management code system against experimental measurements of the CMRR reactor;Annals of Nuclear Energy;2019-08