Published February 1991 | Version v1
Report

Calculation study of the CANDU type fuel performance at extended burnup

  • 1. Institute for Nuclear Power Reactors, Pitesti (Romania)

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

Part of:
Fuel performance at high burnup for water reactors

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

Optional Information