N Reactor pressure tube 1350 postirradiation examination
Description
The N Reactor pressure tubes were fabricated from Zircaloy-2 primarily due to the excellent corrosion resistance, low neutron absorption, and high strength properties of this alloy. Irradiation damage mechanisms increase the strength and decrease the ductility of the Zircaloy-2. Irradiation data available at the time the tubes were installed indicated that fast neutron irradiation damage mechanisms would not decrease the ductility to unacceptable levels over the estimated plant life of 25 to 30 years. However, because the tubes are a primary coolant system component and only limited data are available on irradiation effects at high fluences, a Postirradiation Examination (PIE) program was developed to assure that service factors do not compromise pressure tube integrity essential to reactor safety. The PIE program requires that a pressure tube be periodically removed from the reactor for destructive testing. The N Reactor Technical Specifications specify that the frequency of pressure tube removal and examination be based upon the previous PIE test results. Four pressure tubes were examined before tube 1350, and the test results were summarized in individual reports. PIE results on tube 1350 were summarized along with the test results on the previous four tubes in a previous report. The purpose of this report is to present in detail the results on PIE of pressure tube 1350, and, in particular, document the technique by which the fracture toughness of the pressure tube was determined
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- UNI--736
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10445983
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- DESTRUCTIVE TESTING; FRACTURE PROPERTIES; N-REACTOR; PHYSICAL RADIATION EFFECTS; PRESSURE TUBES; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; IRON ADDITIONS; LWGR TYPE REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; PLUTONIUM PRODUCTION REACTORS; POWER REACTORS; PRODUCTION REACTORS; RADIATION EFFECTS; REACTORS; TESTING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS