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)
Losey, David C;
Brown, Forrest B;
Martin, William R;
Lee, John C
[1]
- Department of Nuclear Engineering, University of Michigan (United States)
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}
}
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}
}