Design of a mixed-oxide fuel assembly to be assessed as a lead test assembly in a BWR reactor
Creators
- 1. UAEM, Also National Institute of Nuclear Research, ININ (Mexico)
- 2. ININ, Also National Polytechnic Institute, IPN. U.P. (Mexico)
Description
The open and the close cycle are the two alternatives to pursue during power generation. The reprocessing is a mature process that now shows a more competitive economic aspect, making it more attractive than ever. Mexico has not decided what to do with the existing and future depleted fuel assemblies that will be generated from the power operation, thus the direct disposal and the reprocessing are still being considered. To have enough arguments in one or the other alternatives it is necessary to make an assessment of both. This investigation focus in the MOX fuel design assuming that the reprocessing is the option to follow and looking for the lowest impact in power generation. The first step in a reprocessing program is to analyze the performance of four lead test assemblies (LTA's), thus in this investigation we design the corresponding MOX to be used as LTA's and assess their performance through one operational cycle. (author)
Availability note (English)
Available from INIS in electronic formFiles
33010817.pdf
Files
(227.8 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:37dbbd1221af724d3c7f83fc86676573
|
227.8 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- [6 p.]
- Report number
- INIS-FR--754
Conference
- Title
- 9. international conference on nuclear engineering
- Dates
- 8-12 Apr 2001
- Place
- Nice Acropolis (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 33010817
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ECONOMICS; FUEL ASSEMBLIES; FUEL CYCLE; MIXED OXIDE FUELS; PERFORMANCE TESTING; REPROCESSING
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.