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Volume 198

Number 5

Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles

Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Hiroki Koike, Kazuya Yamaji, Koji Asano

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 981-992

Research Article / dx.doi.org/10.1080/00295639.2023.2230414

An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations

Qi Li, Song Jiang, Wenjun Sun, Xiaojing Xu

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 993-1020

Research Article / dx.doi.org/10.1080/00295639.2023.2230416

Neutron Importance Estimation via New Recursive Monte Carlo Method for Deep Penetration Neutron Transport

Delgersaikhan Tuya, Yasunobu Nagaya

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1021-1035

Research Article / dx.doi.org/10.1080/00295639.2023.2233850

TRISO Burnup-Dependent Failure Analysis of a HTGR Design-Basis Accident Using BISON

Carlotta G. Ghezzi, Brian D. Wirth, Nicholas R. Brown

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1036-1050

Research Article / dx.doi.org/10.1080/00295639.2023.2230031

Separation of Thorium from Light Rare Earth Elements from Monazite Chloride Leach Liquor

Ana Carolina Santos de Souza, Luiz Rogério Pinho de Andrade Lima

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1051-1061

Research Article / dx.doi.org/10.1080/00295639.2023.2229600

Experimental Study of Thick Target Yield from the 13C(α,n0)16O Reaction

P. S. Prusachenko, T. L. Bobrovskiy, M. V. Bokhovko, A. F. Gurbich

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1062-1074

Research Article / dx.doi.org/10.1080/00295639.2023.2236477

On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem

Yu Yang, Helin Gong, Qiaolin He, Qihong Yang, Yangtao Deng, Shiquan Zhang

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1075-1096

Research Article / dx.doi.org/10.1080/00295639.2023.2236840

Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches

Junda Zhang, Tao Li, Zhirui Shen, Xiangyue Li, Jinbiao Xiong, Xiang Chai, Xiaojing Liu, Tengfei Zhang

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1097-1121

Research Article / dx.doi.org/10.1080/00295639.2023.2227838

Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly

Rowayda Fayez M Abou Alo, Amr Abdelhady, Mohamed K. Shaat

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1122-1130

Research Article / dx.doi.org/10.1080/00295639.2023.2227837

Simulating Properties of Canadian Research Reactor Fuels Important to Disposal

Aaron Barry, Markus H. A. Piro

Nuclear Science and Engineering / Volume 198 / Number 5 / May 2024 / Pages 1131-1154

Research Article / dx.doi.org/10.1080/00295639.2023.2229193

 

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