Published 1995
| Version v1
Book
Effect of operating temperatures of fuel and clad on burnup capability of FBTR (Fast breeder test reactor) mixed carbide fuel
- 1. Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Dept. of Atomic Energy
Description
Indian Fast Breeder Test Reactor uses 70% Pu C-30% UC as fuel. Analytical estimates have been made to find the attainable burnup for this fuel. Data on fuel and clad material are very crucial in the analysis. Analysis has been performed for those subassemblies which are representative of entire core, using the data available and the information found in literature, for nominal and hot spot temperature conditions. It is found that the burnup potential of the fuel is only about 70% of what is achievable under nominal temperature conditions and the burnup attainable at fuel middle column is the limiting one compared to fuel top column. (author). 8 refs., 3 figs., 1 tab
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-349-4
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 1
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 93-98.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27029244
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FBR TYPE REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; FUEL PINS; FUEL-CLADDING INTERACTIONS; MECHANICAL PROPERTIES; MIXED CARBIDE FUELS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; REACTORS
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; REACTOR MATERIALS; SAFETY; SOLID FUELS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.