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Nuclear Science and Engineering Volume 193, 2019 - Issue 12
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Technical Papers

Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions

P. DengUniversity of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109
,
B. K. JeonUniversity of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109
,
H. ParkUniversity of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109
&
W. S. YangUniversity of Michigan, Department of Nuclear Engineering & Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan48109Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0003-0734-6023
ORCID Icon
Pages 1310-1338 | Received 27 Mar 2019, Accepted 17 May 2019, Published online: 01 Jul 2019

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Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama & Toru Obara. (2022) Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling. Nuclear Science and Engineering 196:1, pages 109-120.
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Teng Zhang, Xubo Ma, Kui Hu & GuanQun Jia. (2023) The multigroup library processing method for coupled neutron and photon heating calculation of fast reactor. Nuclear Engineering and Technology.
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Hui Guo, Yi-Wei Wu, Qu-Fei Song, Yu-Yang Shen & Han-Yang Gu. (2023) Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor. Nuclear Science and Techniques 34:11.
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Ning Xu, Tiejun Zu, Liangzhi Cao & Hongchun Wu. (2022) Development of the capability for multi-group shielding library generation in the nuclear data processing code NECP-Atlas. Annals of Nuclear Energy 173, pages 109125.
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H. Park, B.K. Jeon, W.S. Yang, M.A. Smith, C.H. Lee & R.M. Lell. (2020) Verification and validation tests of gamma library of MC2-3 for coupled neutron and gamma heating calculation. Annals of Nuclear Energy 146, pages 107609.
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