Published September 1995 | Version v1
Miscellaneous

Development of re instrumentation technology for irradiated fuel rod

  • 1. Japan Atomic Energy Research Institute, Tokai (Japan)

Description

The extension of burnup of LWR fuel is one of the current important issues from an economical point of view. The information on fission product (FP) gas release and center line temperature of fuel pellets during power transient are important to study pellet clad interaction (PCI) mechanism of LWR fuel rods. To study irradiation behavior of high burnup LWR fuel, re instrumentation of FP gas pressure gage and thermocouple for centerline temperature measurement to the fuel rod irradiated in LWR has been developed in the Department of JMTR. The most important technique was how to drill the center line of cracked pellets to insert a thermocouple. This problem being resolved, a thermocouple and FP gas pressure gage were dually instrumented to the fuel rod irradiated in LWR. Re instrumented fuel rod was loaded in the BOCA (BOiling water CApsule) to perform the demonstration test in the JMTR power ramping test facility. This paper describes the results of demonstration test as well as the development of the re instrumentation technologies

Part of:
Proceedings of the 2nd KAERI-JAERI Joint Seminar on the PIE Technology

Additional details

Publishing Information

Publisher
KAERI-JAERI
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the 2nd KAERI-JAERI Joint Seminar on the PIE Technology
Imprint Pagination
384 p.
Journal Page Range
p. 125-136

Conference

Title
2. KAERI-JAERI Joint Seminar on the PIE Technology
Dates
20-22 Sep 1995
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44055955
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BURNUP; CRACKS; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL PELLETS; FUEL RODS; TEST FACILITIES; WATER COOLED REACTORS
Descriptors DEC
FUEL ELEMENTS; ISOTOPES; MATERIALS; PELLETS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
4 refs, 10 figs, 2 tabs