Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method-Reference-Cited by-同舟云学术

Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

Published:2016-06 Issue:2 Volume:183 Page:229-246
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Jo YuGwon¹,Cho Bumhee¹,Cho Nam Zin¹

Affiliation:

1. Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE15-100

Reference5 articles.

1. “Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation. A 2-D/3-D MOX Fuel Assembly Benchmark,” NEA/NSC/DOC(2003)16, Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2003).

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