Reevaluation of HFIR [High-Flux Isotope Reactor] pressure vessel integrity
Creators
Description
The design of the High-Flux Isotope Reactor (HFIR) pressure vessel included consideration of radiation embrittlement, which enhances the chances of vessel failure as a result of propagation of crack-like defects (flaws). The intent was to surround the core and beryllium reflector with sufficient water and to use sufficiently tough beam-tube nozzle material so that a vessel lifetime of at least 20 effective full-power years (EFPY) could be achieved. The criterion by which vessel integrity was to be judged was that the operating temperature of the vessel should always be greater than the nil-ductility temperature (NDT) by 33 degree C. Specimens withdrawn in 1983 and 1986 indicated that in 1983, NDT + 33 degree C was as much as 25 degree C above the minimum permissible temperature for pressurization (20 degree C), and that by 1986, NDT + 33 degree C exceeded the vessel normal operating temperature (49 degree C) by 8 degree C. Indications were that the radiation damage rate was greater than expected. Thus, HFIR was shut down and a reevaluation of vessel integrity commenced. The reevaluation effort is described
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 61
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 230-231
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 10-14 Jun 1990.
- Place
- Nashville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22035066
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; DEFECTS; EMBRITTLEMENT; FRACTURE MECHANICS; HFIR REACTOR; IRRADIATION; LIFETIME; MONITORING; ORNL; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; SPECIFICATIONS; STRESSES; US NRC
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICS; NATIONAL ORGANIZATIONS; OPERATION; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900608--.