Development of thermocouple re-instrumentation technique for irradiated fuel rod. Techniques for making center hole into UO2 pellets and thermocouple re-instrumentation to fuel rod
Description
The information on FP gas pressure and centerline temperature of fuel pellets during power transient is important to study the pellet clad interaction (PCI) mechanism of high burnup LWR fuel rods. At the Department of JMTR, a re-instrumentation technique of FP gas pressure gage for an irradiated fuel rod was developed in 1990. Furthermore, a thermocouple re-instrumentation technique was successfully developed in 1994. Two steps were taken to carry out the development program of the thermocouple re-instrumentation technique. In the first step, a drilling technique was developed for making a center hole of the irradiated fuel pellets. Various drilling tests were carried out using dummy of fuel rods consisted of Ba2FeO3 pellets and Zry-2 cladding. On this work it is important to keep the pellets just the state cracked at a power reactor. In these tests, the technique to fix the pellets by frozen CO2 was used during the drilling work. Also, diamond drills were used to make the center hole. These tests were completed successfully. A center hole, 54mm depth and 2.5mm diameter, was realized by these methods. The second step of this program is the in-pile demonstration test on an irradiated fuel rod instrumented dually a thermocouple and FP gas pressure gage. The demonstration test was carried out at the JMTR in 1995. (author)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 96 p.
- Report number
- JAERI-Tech--95-037
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27008523
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DRILLING; FISSION PRODUCT RELEASE; FUEL RODS; FUEL-COOLANT INTERACTIONS; JMTR REACTOR; PERFORMANCE TESTING; REACTOR INSTRUMENTATION; SPENT FUELS; THERMOCOUPLES; WATER MODERATED REACTORS; WELDING
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FABRICATION; FUEL ELEMENTS; FUELS; IRRADIATION REACTORS; JOINING; MATERIALS; MATERIALS TESTING REACTORS; MEASURING INSTRUMENTS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; WATER COOLED REACTORS