High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method-Reference-Cited by-同舟云学术

High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method

Published:2023-06-26 Issue:3 Volume:198 Page:545-564
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Rahman Anisur¹^ORCID,Lee Hyun Chul²,Lee Deokjung¹³^ORCID

Affiliation:

1. Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of Korea

2. School of Mechanical Engineering, Pusan National University, Busan 46241, Republic of Korea

3. Advanced Nuclear Technology and Services, 406-21 Jonga-ro, Jung-gu, Ulsan 44429, Republic of Korea

Funder

National Research Foundation of Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2023.2194219

Reference17 articles.

1. Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation

2. Incorporation of anisotropic scattering into the method of characteristics

3. J. E. HOOGENBOOM W. R. MARTIN and B. PETROVIC “Monte Carlo Performance Benchmark for Detailed Power Density Calculation in a Full Size Reactor Core Benchmark Specifications Revision 1” (2010).

4. Fusion of Method of Characteristics and Nodal Method for 3-D Whole-Core Transport Calculation;CHO N. Z.;Trans. Am. Nucl. Soc.,2002

5. J.-Y. CHO et al., “Transient Capability for a MOC-Based Whole Core Transport Code DeCART,” Trans. Am. Nucl. Soc., 92, 721 (2005).

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