Calculation study of the CANDU type fuel performance at extended burnup
Description
In the case of CANDU type fuel there is a necessity to improve the fuel bundle design in order to increase its ability to meet high burnup. Further bundle sub-division and slightly enriched uranium is one possibility. Furthermore, grading the element sizes also minimizes the linear power output of the individual fuel elements, while maximizing the power output of the bundle. Also, there are design changes of the pellet that can improve performance at higher burnups. The purpose of this study was to make a comparison between new fuel concept performance and standard CANDU type fuel performance. The results of the thermo-mechanical behaviour included in this study demonstrate the influence of geometrical and microstructural parameters on the fuel performance. The calculations were performed by means of a probabilistic analysis system developed in INPR. The results of the analysis point out the performances of the new concept and constitute a guideline for future research. (author). 7 refs, 5 figs
Additional details
Publishing Information
- Imprint Title
- Fuel performance at high burnup for water reactors
- Imprint Pagination
- 216 p.
- Journal Page Range
- p. 191-195.
- Report number
- IWGFPT--36
Conference
- Title
- Technical committee meeting on fuel performance at high burnup for water reactors.
- Dates
- 5-8 Jun 1990.
- Place
- Studsvik (Sweden).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22091431
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; FUEL PELLETS; MODIFICATIONS; PROBABILISTIC ESTIMATION
- Descriptors DEC
- HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS