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Title: Calculation of Design Parameters for an Equilibrium LEU Core in the NBSR

Abstract

A plan is being developed for the conversion of the NIST research reactor (NBSR) from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Previously, the design of the LEU fuel had been determined in order to provide the users of the NBSR with the same cycle length as exists for the current HEU fueled reactor. The fuel composition at different points within an equilibrium fuel cycle had also been determined. In the present study, neutronics parameters have been calculated for these times in the fuel cycle for both the existing HEU and the proposed LEU equilibrium cores. The results showed differences between the HEU and LEU cores that would not lead to any significant changes in the safety analysis for the converted core. In general the changes were reasonable except that the figure-of-merit for neutrons that can be used by experimentalists shows there will be a 10% reduction in performance. The calculations included kinetics parameters, reactivity coefficients, reactivity worths of control elements and abnormal configurations, and power distributions.

Authors:
;
Publication Date:
Research Org.:
BROOKHAVEN NATIONAL LABORATORY (BNL)
Sponsoring Org.:
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY
OSTI Identifier:
1030634
Report Number(s):
BNL-96386-2011-IR
R&D Project: 10608; TRN: US1200060
DOE Contract Number:  
DE-AC02-98CH10886
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONTROL ELEMENTS; DESIGN; FUEL CYCLE; HIGHLY ENRICHED URANIUM; KINETICS; NEUTRONS; PERFORMANCE; POWER DISTRIBUTION; REACTIVITY COEFFICIENTS; REACTIVITY WORTHS; RESEARCH REACTORS; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; NIST Reactor research; high-enriched uranium; low-enriched uranium

Citation Formats

Hanson, A.L., and Diamond, D. Calculation of Design Parameters for an Equilibrium LEU Core in the NBSR. United States: N. p., 2011. Web. doi:10.2172/1030634.
Hanson, A.L., & Diamond, D. Calculation of Design Parameters for an Equilibrium LEU Core in the NBSR. United States. doi:10.2172/1030634.
Hanson, A.L., and Diamond, D. Fri . "Calculation of Design Parameters for an Equilibrium LEU Core in the NBSR". United States. doi:10.2172/1030634. https://www.osti.gov/servlets/purl/1030634.
@article{osti_1030634,
title = {Calculation of Design Parameters for an Equilibrium LEU Core in the NBSR},
author = {Hanson, A.L. and Diamond, D.},
abstractNote = {A plan is being developed for the conversion of the NIST research reactor (NBSR) from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Previously, the design of the LEU fuel had been determined in order to provide the users of the NBSR with the same cycle length as exists for the current HEU fueled reactor. The fuel composition at different points within an equilibrium fuel cycle had also been determined. In the present study, neutronics parameters have been calculated for these times in the fuel cycle for both the existing HEU and the proposed LEU equilibrium cores. The results showed differences between the HEU and LEU cores that would not lead to any significant changes in the safety analysis for the converted core. In general the changes were reasonable except that the figure-of-merit for neutrons that can be used by experimentalists shows there will be a 10% reduction in performance. The calculations included kinetics parameters, reactivity coefficients, reactivity worths of control elements and abnormal configurations, and power distributions.},
doi = {10.2172/1030634},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2011},
month = {9}
}

Technical Report:

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