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Title: Main experimental results of the Phebus Severe Fuel Damage Program

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6958829
 [1]
  1. Centre d'Etudes Nucleaires de Cadarache, St. Paul-les-Durance (France)

The main objective of this program is to improve our knowledge about the early phase of a pressurized water reactor in-vessel core melt degradation in a temperature range up to 2800 K. The experimental program performed from December 1986 to June 1989 consists of six in-pile experiments with 21 fresh fuel rod bundles of 0.8 m active length. It is divided into two series of tests: (1) The first one (B9, B9R, B9+) is mainly devoted to the oxidation phenomenon and its consequences for fuel degradation. This series is characterized by high oxidation rates. (2) The second series [C3, C3+, Ag-In-CD (AIC)] is characterized by low oxidation rates of the cladding in order to study the interaction between the remaining Zircaloy and the other materials: interactions with Inconel and UO[sub 2] for C3 and C3+ tests and interactions with the Ag-In-Cd alloy and stainless steel of the control rod for the AIC test.

OSTI ID:
6958829
Report Number(s):
CONF-931160-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
Country of Publication:
United States
Language:
English