Effect of non-equilibrium fission gas and fuel creep on swelling and release in irradiated carbide fuels
- 1. California Univ., Los Angeles (USA). School of Engineering and Applied Science
- 2. Argonne National Lab., IL (USA). Materials Science and Technology Div.
Description
The code UCSWELL was developed to simulate fission gas behavior in carbide fuels. One of the limiting assumptions in UCSWELL - that matrix gas bubbles are in equilibrium with gas atom concentration - is removed and non-equilibrium matrix fission gas bubbles are allowed, but with relaxation to equilibrium by means of vacancy diffusion and thermal and radiation-induced creep of the fuel. For a given grain size, the difference in swelling between equilibrium and non-equilibrium with relaxation bubble fission gas treatment increases with decreasing irradiation temperature. At a given temperature, the non-equilibrium effect is more pronounced for large grain fuel. This is to be expected because the creep rate (and hence the rate at which bubbles grow to an equilibrium size) decreases as temperature decreases and/or as grain size increases. At temperatures, where the creep rate is grain size insensitive, grain size remains important to the equilibrium process in so far as the grain boundary is a source of vacancies to the non-equilibrium bubbles. While the difference in these quantities is at the most of the order of 20% for the steady operating conditions considered, it is anticipated that the non-equilibrium effects become more pronounced during reactor overpower and undercooling transients. (orig./HP)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 88
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 93-101
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17036843
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; CREEP; FISSION PRODUCT RELEASE; IRRADIATION; LMFBR TYPE REACTORS; MIXED OXIDE FUELS; PLUTONIUM CARBIDES; SWELLING; TRANSIENT OVERPOWER ACCIDENTS; URANIUM CARBIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CARBIDES; CARBON COMPOUNDS; DEFORMATION; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FUELS; PLUTONIUM COMPOUNDS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS