The French Thermal-Hydraulic Program Addressing the Requirements of Future Pressurized Water Reactors-Reference-Cited by-同舟云学术

The French Thermal-Hydraulic Program Addressing the Requirements of Future Pressurized Water Reactors

Published:1988-01 Issue:1 Volume:80 Page:73-82
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Courtaud Michel¹,Deruaz Roger¹,D’Aillon Luc Gros¹

Affiliation:

1. Commissariat à l’Energie Atomique, Service d’Etudes Thermohydrauliques, Centre d’Etudes Nucléaires de Grenoble, 85 X 38041 Grenoble Cedex, France

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT88-A35550

Reference10 articles.

1. R. PLAS, “FLICA III.M code de calcul thermohydraulique de reacteurs ou de boucles d’essais,” CEA-N-2418, Commisariat à l’Energie Atomique (Dec. 1984).

2. G. F. STEVENS et al. “A Quantitative Comparison Between Burn Out Data for Water at 1000 psia and Freon 12 at 155 psia. Uniformly Heated Round Tubes Vertical Up-flow,” AEEW-R-327, United Kingdom Atomic Energy Authority (1964).

3. G. F. STEVENS et al. “A Comparison Between Burn Out Data for 19 Rod Cluster Test Sections Cooled by Freon 12 at 155 psia and by Water at 1000 psia in Vertical Up-flow,” AEEW-R-468, United Kingdom Atomic Energy Authority (1966).

4. R. W. BOWRING, “WSC2: A Subchannel Dry Out Correlation for Water Cooled Clusters Over the Pressure Range 3.4-15.9 MPa,” AEEW-R-983, United Kingdom Atomic Energy Authority (1979).

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