Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC-Reference-Cited by-同舟云学术

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Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC

Published:2021-01-04 Issue:5 Volume:195 Page:464-477
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Kim HyeonTae¹,Kim Yonghee¹

Affiliation:

1. Korea Advanced Institute of Science and Technology, Department of Nuclear and Quantum Engineering, Daejeon 34141, Korea

Funder

National Research Foundation of Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2020.1839342

Reference39 articles.

1. Multidimensional multiphysics simulation of nuclear fuel behavior

2. The Serpent Monte Carlo code: Status, development and applications in 2013

Cited by 4 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. Evaluation of effective kinetic parameters and adjoint flux distribution using iterated fission probability in the iMC Monte Carlo code;Annals of Nuclear Energy;2025-01

2. Evaluation of Effective Kinetic Parameters and Adjoint Flux Distribution Using Iterated Fission Probability in the Imc Monte Carlo Code;2024

3. Real variance estimation in iDTMC-based depletion analysis;Nuclear Engineering and Technology;2023-11

4. Pin-by-Pin Coupled Transient Monte Carlo Analysis Using the iMC Code;Frontiers in Energy Research;2022-03-18

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