Assessment of Thermal-Hydraulic Characteristics of the Primary Circuit-Reference-Cited by-同舟云学术

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Assessment of Thermal-Hydraulic Characteristics of the Primary Circuit

Published:1990-09 Issue:1 Volume:106 Page:55-63
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Francois G.¹,Azarian G.¹,Astegiano J. C.²,Lacroix C.³,Poet G.⁴

Affiliation:

1. Novatome, Framatome, Direction Novatome, 10 rue Juliette Recamier, 69398 Lyon Cedex 03, France

2. Commissariat à l’Energie Atomique, Centre d’Etudes Nucléaire de Cadarac Département de Recherche Physique, 13108, St. Paul-lez-Durance, France

3. Electricité de France, Laboratoire National Hydraulique, 1 Avenue du Général de Gaulle, 92141 Clamart, France

4. Electricité de France, R.E. Lyon, 35 rue Louis Guérin 69611 Villeurbanne Cedex, France

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE90-A23757

Reference1 articles.

1. Coolant Mixing Phenomena Influencing Measurements of Core Coolant Temperature Rises

Cited by 7 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. Thermal hydraulic issues and challenges for current and new generation FBRs;Nuclear Engineering and Design;2015-12

2. Computational fluid dynamic investigations of partial blockage detection by core-temperature monitoring system of a sodium cooled fast reactor;Nuclear Engineering and Design;2011-12

3. Some thermal hydraulic challenges in sodium cooled fast reactors;Nuclear Engineering and Design;2010-05

4. Overview of pool hydraulic design of Indian prototype fast breeder reactor;Sadhana;2010-04

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

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