Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13-Reference-Cited by-同舟云学术

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Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13

Published:2024-01 Issue: Volume:195 Page:110157
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Hamase Erina,Ohgama Kazuya,Kawamura Takumi,Doda Norihiro^ORCID,Tanaka Masaaki^ORCID,Yamano Hidemasa^ORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. PARTISN: A Time-dependent, Parallel Neutral Particle Transport Code System;Alcouffe,2005

2. A Summary Description of the Fast Flux Test Facility. HEDL-400;Cabell,1980

3. Hydrodynamic Models and Correlations for Bare and Wire-wrapped Hexagonal Rod Bundles – Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters;Cheng;Nucl. Eng. and Des.,1986

4. Crane Co., 1982. Flow of Fluids-through Valves, Fittings, and Pipe. Technical paper No. 410M.

5. JSME Data Book, 1979. Hydralics Losses in Pipes and Ducts (in Japanese). Maruzen.

Cited by 1 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. Investigation of the fast flux test facility transient behavior during a loss of flow without scram test;Nuclear Engineering and Design;2024-11

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