The French thermal-hydraulic program addressing the requirements of future pressurized water reactors

Journal Article · Thu Dec 31 23:00:00 EST 1987 · Nucl. Technol.; (United States)

OSTI ID:6957452

Courtaud, M; Deruaz, R; D'Aillon, L G

In the framework of feasibility studies of future pressurized water reactors, a thermal-hydraulic program has been established in order to qualify computer codes in three fields: critical heat flux and reflooding heat transfer in triangular rod bundle arrays with tight lattices and the coolability of movable fertile rods in their guide tubes. Tests carried out at the Commissariat a l'Energie Atomique in cooperation with Electricite de France and Framatome are now in progress, and preliminary results are shown for these three studies.

• Research Organization: Commissariat a l'Energie Atomique, Service d'Etudes Thermohydrauliques, Centre d'Etudes Nucleaires de Grenoble, 85 X 38041 Grenoble Cedex (FR)
• OSTI ID: 6957452
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 80:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

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