Fission gas release and transport model for high-burnup PWR models

Conference · Thu Jan 01 04:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6883516

Kinoshita, M; Matsui, T; Fukuya, K

To minimize fuel cycle cost, Japanese utilities are planning to convert to extended burnup operation in the near future. However, there is concern that enhanced fission gas release will result in increased rod internal pressure. Some remedies for fuel pellets, such as large grain or doped pellets, are proposed and under examination to reduce fission gas release. To evaluate the effects of these improvements, we developed a diffusion based gas release and transport model that is applicable to the quantitative investigation of detailed phenomena at high burnup. These models are implemented in the IRON code and verified against its pressurized water reactor (PWR) fuel data base. This code is now applicable to the analyses for the extended burnup operation up to 55 MWd/kgU.

• OSTI ID: 6883516
• Report Number(s): CONF-8711195-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BURNUP
COMPUTER CODES
FABRICATION
FISSION PRODUCT RELEASE
FUEL ELEMENTS
I CODES
MASS TRANSFER
MATHEMATICAL MODELS
OPERATION
PERFORMANCE
POROSITY
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR OPERATION
REACTORS
TEMPERATURE DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS