Measurement of Core Thermal-Hydraulic Characteristics-Reference-Cited by-同舟云学术

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Measurement of Core Thermal-Hydraulic Characteristics

Published:1990-09 Issue:1 Volume:106 Page:47-54
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Leteinturier D.¹,Bernardin B.¹,Blanc M.²,Paulin M.³

Affiliation:

1. Commissariat à l’Energie Atomique, Centre d’Etudes Nucléaires de Cadarache, 13108 St. Paul-lez-Durance, Cedex, France

2. Novatome-NIRA, Framatome, Direction Novatome, 10 rue Juliette Récamier, 69398 Lyon, Cedex 03, France

3. Electricité de France/SEPTEN, 12-14 Avenue Dutrievoz, 69628 Villeurbanne, Cedex, France

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE90-A23756

Cited by 5 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. Interpretation of the Control Rod Withdrawal Test in the Sodium-Cooled Fast Reactor Phénix;Nuclear Science and Engineering;2013-10

2. Measurement of Decay Heat and Comparison with Predictions;Nuclear Science and Engineering;1990-09

3. Neutron Monitoring and the Inherent Source of Superphénix;Nuclear Science and Engineering;1990-09

4. Coolant Mixing Phenomena Influencing Measurements of Core Coolant Temperature Rises;Nuclear Science and Engineering;1990-09

5. An Overview of Superphénix Commissioning Tests;Nuclear Science and Engineering;1990-09

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