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Fyfitch, S.; Gross, L.B.; Lowe, A.L. Jr.; Moore, K.E.; Yoon, K.K.
Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume)1993
Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume)1993
AbstractAbstract
[en] A Master Integrated Reactor Vessel Surveillance Program (MIRVP) was designed to provide the data required to ensure the continued licensability of 17 reactor vessels including 8 Babcock and Wilcox (B and W)--designed 177-fuel assembly (FA) plants and 9 Westinghouse--designed plants with B and W--fabricated reactor vessels. This program is an extension of the integrated surveillance program developed for the B and W 177-FA plants. The program combines 17 separate surveillance program developed for the B and W 177-FA plants. The program combines 17 separate surveillance programs with supplementary weld metal capsules and high fluence weld metal capsules designed to meet the needs for license renewals. In addition, capsules are included to address the requirements of reactor vessel annealing and to study the fluence spectrum effects of the two plant designs. Design details are provided for the new high fluence surveillance capsules
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Steele, L.E. (ed.); 414 p; ISBN 0-8031-1478-8;
; 1993; p. 118-131; American Society for Testing and Materials; Philadelphia, PA (United States); American Society for Testing and Materials, 1916 Race Street, Philadelphia, PA 19103 (United States)

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