A comprehensive fission gas release model considering multiple bubble sizes on the grain boundary under steady-state conditions

Journal Article · Sun Sep 01 00:00:00 EDT 1991 · Nuclear Technology; (United States)

OSTI ID:5780164

Hwang, W; Suk, H C ^[1]; Jae, W M ^[2]

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1. Korea Atomic Energy Research Inst., P.O. Box 7, Daeduk-Danji, Daejeon (KR)
2. Hanyang Univ., Haengdang-Dong 17, Sungdong-Gu, Seoul (KR)

This paper reports on a comprehensive fission gas release model developed by considering the behavior of multiple bubble sizes on the fuel grain boundary in terms of relevant physical parameters. This model takes into account bubble migration and coalescence; critical bubble size, which depends on the thermal gradient on the grain boundary; and the lenticular shape of the bubbles. Booth's classical diffusion theory is directly adopted in the modeling of intragranular fission gas behavior. To consider the bubble drift due to the thermal gradient, those bubbles that exceed the critical bubble size are assumed to be left on the grain boundary and to migrate along the thermal gradient until they encounter free voidages. Use of this model in the KAFEPA code, which predicts the absolute magnitude and the trend of the gas release depending on power history, gives better agreement with the experimental data than the predictions of the model in the ELESIM code, which considers only a single bubble size at the grain boundary.

• OSTI ID: 5780164
• Journal Information: Nuclear Technology; (United States), Vol. 95:3; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BUBBLES
SIZE
FISSION PRODUCT RELEASE
COMPUTERIZED SIMULATION
REACTOR ACCIDENTS
REACTOR MONITORING SYSTEMS
PERFORMANCE TESTING
CRITICALITY
E CODES
EXPERIMENTAL DATA
GRAIN BOUNDARIES
K CODES
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
TEMPERATURE GRADIENTS
ACCIDENTS
ANALOG SYSTEMS
COMPUTER CODES
CRYSTAL STRUCTURE
DATA
FUNCTIONAL MODELS
INFORMATION
MICROSTRUCTURE
NUMERICAL DATA
SIMULATION
SIMULATORS
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
220400 - Nuclear Reactor Technology- Control Systems