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GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel

Abstract

A mechanistic model of fission gas release and swelling for the U-(Pu)-Zr metallic fuel in the fast reactor, GRSIS (Gas Release and Swelling in ISotropic fuel matrix) was developed. Fission gas bubbles are assumed to nucleate isotropically from the gas atoms in the metallic fuel matrix since they can nucleate at both the grain boundaries and the phase boundaries which are randomly distributed inside the grain. Bubbles can grow to larger size by gas diffusion and coalition with other bubbles so that they are classified as three classes depending upon their sizes. When bubble swelling reaches the threshold value, bubbles become interconnected each other to make the open channel to the external free space, that is, the open bubbles and then fission gases inside the interconnected open bubbles are released instantaneously. During the irradiation, fission gases are released through the open bubbles. GRSIS model can take into account the fuel gap closure by fuel bubble swelling. When the fuel gap is closed by fuel swelling, the contact pressure between fuel and cladding in relation to the bubble swelling and temperature is calculated. GRSIS model was validated by comparison with the irradiation test results of U-(Pu)-Zr fuels in ANL as well  More>>
Publication Date:
Mar 01, 1999
Product Type:
Technical Report
Report Number:
KAERI/TR-1289/99
Reference Number:
EDB-00:100821
Resource Relation:
Other Information: PBD: Mar 1999
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BUBBLES; COMPUTER CODES; FAST REACTORS; FISSION PRODUCT RELEASE; NUCLEAR FUELS; PLUTONIUM; SWELLING; URANIUM; ZIRCONIUM
OSTI ID:
20010563
Research Organizations:
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
TRN: KR9900206056137
Availability:
Available from INIS in electronic form
Submitting Site:
KRN
Size:
45 pages
Announcement Date:

Citation Formats

Lee, Chan Bock, Lee, Byung Ho, Nam, Cheol, and Sohn, Dong Seong. GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel. Korea, Republic of: N. p., 1999. Web.
Lee, Chan Bock, Lee, Byung Ho, Nam, Cheol, & Sohn, Dong Seong. GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel. Korea, Republic of.
Lee, Chan Bock, Lee, Byung Ho, Nam, Cheol, and Sohn, Dong Seong. 1999. "GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel." Korea, Republic of.
@misc{etde_20010563,
title = {GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel}
author = {Lee, Chan Bock, Lee, Byung Ho, Nam, Cheol, and Sohn, Dong Seong}
abstractNote = {A mechanistic model of fission gas release and swelling for the U-(Pu)-Zr metallic fuel in the fast reactor, GRSIS (Gas Release and Swelling in ISotropic fuel matrix) was developed. Fission gas bubbles are assumed to nucleate isotropically from the gas atoms in the metallic fuel matrix since they can nucleate at both the grain boundaries and the phase boundaries which are randomly distributed inside the grain. Bubbles can grow to larger size by gas diffusion and coalition with other bubbles so that they are classified as three classes depending upon their sizes. When bubble swelling reaches the threshold value, bubbles become interconnected each other to make the open channel to the external free space, that is, the open bubbles and then fission gases inside the interconnected open bubbles are released instantaneously. During the irradiation, fission gases are released through the open bubbles. GRSIS model can take into account the fuel gap closure by fuel bubble swelling. When the fuel gap is closed by fuel swelling, the contact pressure between fuel and cladding in relation to the bubble swelling and temperature is calculated. GRSIS model was validated by comparison with the irradiation test results of U-(Pu)-Zr fuels in ANL as well as the parametric studies of the key variable in the model. (author). 13 refs., 1 tab., 22 figs.}
place = {Korea, Republic of}
year = {1999}
month = {Mar}
}