Neutronic analysis of the conversion of HEU to LEU fuel for a 5-MW MTR core
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6883269
In recent years, due to cessation of highly enriched uranium (HEU) fuel supply, practical steps have been taken to substitute HEU fuel in almost all research reactors by medium-enriched uranium or low-enriched uranium (LEU) fuels. In this study, a neutronic calculation of a 5-MW research reactor core fueled with HEU (93% /sup 235/U) is presented. In order to assess the performance of the core with the LEU (< 20%) fuel replacement, while keeping fuel element geometry nearly unchanged, several different /sup 235/U loadings were examined. The core consists of 22 standard fuel elements (SFEs) and 6 control fuel elements (CFEs). Each fuel elements has 18 curved plates of which two end plates are dummies. Initial /sup 235/U content is 195 g /sup 235/U/SFE and 9.7 g /sup 235/U/CFE or /PFE. In all calculations the permitted changes to the fuel elements are (a) 18 active plates per SFE, (b) fuel plates assumed to be flat, and (c) 8 or 9 active plates per CFE.
- OSTI ID:
- 6883269
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
Similar Records
Preliminary neutronics calculations for conversion of the Tehran research reactor core from HEU to LEU fuel
Feasibility studies of LEU fuel conversion for the BMRR and HFBR
Validation of ATR Fission Power Deposition Fraction in HEU and LEU Fuel Plates
Journal Article
·
Sun Aug 01 00:00:00 EDT 1993
· Nuclear Technology; (United States)
·
OSTI ID:6406968
Feasibility studies of LEU fuel conversion for the BMRR and HFBR
Journal Article
·
Sun Nov 30 23:00:00 EST 1997
· Transactions of the American Nuclear Society
·
OSTI ID:552390
Validation of ATR Fission Power Deposition Fraction in HEU and LEU Fuel Plates
Conference
·
Mon Sep 01 00:00:00 EDT 2008
·
OSTI ID:941749
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BURNUP
CROSS SECTIONS
ELEMENTS
ENRICHED URANIUM
GROUP THEORY
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
KINETICS
MATERIALS
MATHEMATICS
METALS
MODERATELY ENRICHED URANIUM
PERFORMANCE
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
URANIUM
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
BURNUP
CROSS SECTIONS
ELEMENTS
ENRICHED URANIUM
GROUP THEORY
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
KINETICS
MATERIALS
MATHEMATICS
METALS
MODERATELY ENRICHED URANIUM
PERFORMANCE
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
URANIUM