Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters
Abstract
Sensitivity analysis was carried out in order to investigate the effect of a fuel pellet's design parameters on the performance of a dry-processed Canada deuterium uranium (CANDU) fuel and to suggest the optimum design modifications. Under a normal operating condition, a dry-processed fuel has a higher internal pressure and plastic strain due to a higher fuel centerline temperature when compared with a standard natural uranium CANDU fuel. Under a condition that the fuel bundle dimensions do not change, sensitivity calculations were performed on a fuel's design parameters such as the axial gap, dish depth, gap clearance and plenum volume. The results showed that the internal pressure and plastic strain of the cladding were most effectively reduced if a fuel's element plenum volume was increased. More specifically, the internal pressure and plastic strain of the dry-processed fuel satisfied the design limits of a standard CANDU fuel when the plenum volume was increased by one half a pellet, 0.5 mm{sup 3}/K. (authors)
- Authors:
-
- Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)
- Publication Date:
- Research Org.:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI Identifier:
- 20979651
- Resource Type:
- Conference
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 4 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; CANDU TYPE REACTORS; CLADDING; DESIGN; FUEL PELLETS; NATURAL URANIUM; NUCLEAR FUELS; PERFORMANCE; SENSITIVITY ANALYSIS; STRAINS
Citation Formats
Choi, Hangbok, and Ryu, Ho Jin. Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters. United States: N. p., 2007.
Web.
Choi, Hangbok, & Ryu, Ho Jin. Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters. United States.
Choi, Hangbok, and Ryu, Ho Jin. 2007.
"Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters". United States.
@article{osti_20979651,
title = {Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters},
author = {Choi, Hangbok and Ryu, Ho Jin},
abstractNote = {Sensitivity analysis was carried out in order to investigate the effect of a fuel pellet's design parameters on the performance of a dry-processed Canada deuterium uranium (CANDU) fuel and to suggest the optimum design modifications. Under a normal operating condition, a dry-processed fuel has a higher internal pressure and plastic strain due to a higher fuel centerline temperature when compared with a standard natural uranium CANDU fuel. Under a condition that the fuel bundle dimensions do not change, sensitivity calculations were performed on a fuel's design parameters such as the axial gap, dish depth, gap clearance and plenum volume. The results showed that the internal pressure and plastic strain of the cladding were most effectively reduced if a fuel's element plenum volume was increased. More specifically, the internal pressure and plastic strain of the dry-processed fuel satisfied the design limits of a standard CANDU fuel when the plenum volume was increased by one half a pellet, 0.5 mm{sup 3}/K. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/20979651},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jul 01 00:00:00 EDT 2007},
month = {Sun Jul 01 00:00:00 EDT 2007}
}