Published 1977
| Version v1
Book
Computer modeling of the Danish BWR and PWR ramp tests
Description
The CYGRO-3 code was used to analyze the Danish ramp tests of several BWR and PWR fuel pins, and to compare the results to the experimental data. The fuel rods were irradiated to burnups of 12,900 MWD/te UO/sub 2/ for the PWR rods and 21,200 MWD/te UO/sub 2/ for the BWR rods. After the pre-ramp irradiation, the fuel pins were removed from the reactor and nondestructively examined. Subsequently, they were re-inserted and ramped to a slightly higher power level at high ramp rates. Two out of three PWR and one out of two BWR rods failed. Computer calculations for prediction of rod failures are discussed. 7 refs
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- Chicago, IL
- Imprint Title
- Water reactor fuel performance, ans topical meeting, 1977
- Journal Page Range
- p. 189-196.
Conference
- Title
- ANS topical meeting on water reactor fuel performance.
- Dates
- 9 - 11 May 1981.
- Place
- St Charles, IL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12642208
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; C CODES; COMPUTER CALCULATIONS; DENMARK; FUEL ELEMENT FAILURE; FUEL PINS; MATHEMATICAL MODELS; PWR TYPE REACTORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; EUROPE; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SCANDINAVIA; WATER COOLED REACTORS; WATER MODERATED REACTORS