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Iskander, S.K.; Nanstad, R.K.
Heavy-section steel irradiation program. Progress report, October 1994--March 19951995
Heavy-section steel irradiation program. Progress report, October 1994--March 19951995
AbstractAbstract
[en] The purpose of the Ninth Irradiation Series is to evaluate the correlation between fracture toughness and CVN impact energy during irradiation, annealing, and reirradiation (IAR). Results of annealing CVN specimens from the low-USE welds from the Midland beltline and nozzle course welds, as well as HSST plate 02 and HSSI weld 73W are given. Also presented is the effect of annealing on the initiation fracture toughness of annealed material from Midland beltline weld and HSST plate 02. The results from capsule 10-5 specimens of weld 73W confirm those previously obtained on the so-called undersize specimens that were irradiated in the Fifth Irradiation Series, namely that the recovery due to annealing at 343 degrees C (650 degrees F) for 1 week is insignificant. The fabrication of major components for the IAR facility for two positions on the east side of the FNR at the University of Michigan has begun. Fabrication of two reusable capsules (one for temperature verification and the other for dosimetry verification), as well as two capsules for IAR, studies is also under way. The design of a reusable capsule capable of reirradiating previously irradiated and annealed CVN and 1T C(T) specimens is also progressing. The data acquisition and control (DAC) instrumentation for the first two IAR facilities is essentially complete and awaiting completion of the IAR facilities and temperature test capsule for checkout and control algorithm development
Primary Subject
Secondary Subject
Source
Corwin, W.R. (Oak Ridge National Lab., TN (United States)); Oak Ridge National Lab., TN (United States); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; 61 p; Oct 1995; p. 26-32; Also available from OSTI as DE96002233; NTIS
Record Type
Report
Literature Type
Numerical Data; Progress Report
Report Number
Country of publication
DATA, DESTRUCTIVE TESTING, DOCUMENT TYPES, ENRICHED URANIUM REACTORS, HEAT TREATMENTS, IMPACT TESTS, INFORMATION, JOINTS, MATERIALS TESTING, MECHANICAL PROPERTIES, MECHANICAL TESTS, POWER REACTORS, PROCESS HEAT REACTORS, PWR TYPE REACTORS, REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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