Published March 1996 | Version v1
Report

High burnup effects in WWER fuel rods

  • 1. RRC Research Institute of Atomic Reactors, Dimitrovqrad (Russian Federation)

Description

Since 1987 at the Research Institute of Atomic Reactors, the examinations of the WWER spent fuel assemblies has been carried out. These investigations are aimed to gain information on WWER spent fuel conditions in order to validate the fuel assemblies use during the 3 and 4 year fuel cycle in the WWER-440 and WWER-1000 units. At present time, the aim is to reach an average fuel burnup of 55 MWd/kgU. According to this aim, a new investigation program on the WWER spent fuel elements is started. The main objectives of this program are to study the high burnup effects and their influence on the WWER fuel properties. This paper presented the main statistical values of the WWER-440 and WWER-1000 reactors' fuel assemblies and their fragment parameters. Average burnup of fuel in the investigated fuel assemblies was in the range of 13 to 49.7 MWd/kgU. In this case, the numer of fuel cycles was from 1 to 4 during operation of the fuel assemblies

Additional details

Publishing Information

Imprint Title
Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings
Imprint Pagination
265 p.
Journal Page Range
p. 81-92.
Report number
NUREG/CP--0149-Vol.1

Conference

Title
23. water reactor safety information meeting.
Dates
23-25 Oct 1995.
Place
Bethesda, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27068636
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BURNUP; DIAGRAMS; EXPERIMENTAL DATA; FUEL RODS; IMAGES; WWER-3 REACTOR; WWER-5 REACTOR
Descriptors DEC
DATA; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Secondary number(s)
CONF-9510156--Vol.1.