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Core physics analysis in support of the FNR HEU-LEU demonstration experiment

Abstract

A core neutronics analysis has been undertaken to assess the impact of low-enrichment fuel on the performance and utilization of the FNR As part of this analytic effort a computer code system has been assembled which will be of general use in analyzing research reactors with MTR-type fuel. The code system has been extensively tested and verified in calculations for the present high enrichment core. The analysis presented here compares the high-and-low enrichment fuels in batch and equilibrium core configurations which model the actual FNR operating conditions. The two fuels are compared for cycle length, fuel burnup, and flux and power distributions, as well as for the reactivity effects which are important in assessing the impact of LEU fuel on reactor shutdown margin. (author)
Authors:
Losey, David C; Brown, Forrest B; Martin, William R; Lee, John C [1] 
  1. Department of Nuclear Engineering, University of Michigan (United States)
Publication Date:
Aug 01, 1983
Product Type:
Conference
Report Number:
ANL/RERTR/TM-3; CONF-801144; INIS-XA-C-021
Resource Relation:
Conference: International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR), Argonne, IL (United States), 12-14 Nov 1980; Other Information: 20 refs, 13 figs, 10 tabs; PBD: Aug 1983; Related Information: In: Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology, 671 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; COMPUTER CALCULATIONS; FNR REACTOR; FUEL CYCLE; HIGHLY ENRICHED URANIUM; NEUTRON FLUX; POWER DISTRIBUTION; REACTOR CORES; REACTOR LATTICE PARAMETERS; REACTOR SAFETY; SLIGHTLY ENRICHED URANIUM
Sponsoring Organizations:
U.S. Department of Energy, Assistant Secretary for Nuclear Energy, Office of Spent Fuel Management and Reprocessing Systems (United States)
OSTI ID:
20571732
Research Organizations:
Argonne National Laboratory, Argonne, IL (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA04C1568023739
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 450-498
Announcement Date:

Citation Formats

Losey, David C, Brown, Forrest B, Martin, William R, and Lee, John C. Core physics analysis in support of the FNR HEU-LEU demonstration experiment. IAEA: N. p., 1983. Web.
Losey, David C, Brown, Forrest B, Martin, William R, & Lee, John C. Core physics analysis in support of the FNR HEU-LEU demonstration experiment. IAEA.
Losey, David C, Brown, Forrest B, Martin, William R, and Lee, John C. 1983. "Core physics analysis in support of the FNR HEU-LEU demonstration experiment." IAEA.
@misc{etde_20571732,
title = {Core physics analysis in support of the FNR HEU-LEU demonstration experiment}
author = {Losey, David C, Brown, Forrest B, Martin, William R, and Lee, John C}
abstractNote = {A core neutronics analysis has been undertaken to assess the impact of low-enrichment fuel on the performance and utilization of the FNR As part of this analytic effort a computer code system has been assembled which will be of general use in analyzing research reactors with MTR-type fuel. The code system has been extensively tested and verified in calculations for the present high enrichment core. The analysis presented here compares the high-and-low enrichment fuels in batch and equilibrium core configurations which model the actual FNR operating conditions. The two fuels are compared for cycle length, fuel burnup, and flux and power distributions, as well as for the reactivity effects which are important in assessing the impact of LEU fuel on reactor shutdown margin. (author)}
place = {IAEA}
year = {1983}
month = {Aug}
}