Irradiation Experiment Conceptual Design Parameters for NBSR Fuel Conversion

R., Brown N. ; Brown,N.R. ; Baek,J.S ; Hanson, A.L. ; Cuadra,A. ; Cheng,L.Y. ; Diamond, D.J.

Brookhaven National Laboratory

关键词: Nist;    Leu;    42 Nist;    Irradiation;    Heu;   

DOI  :  10.2172/1082050
RP-ID  :  BNL--99897-2013-IR
RP-ID  :  DE-AC02-98CH10886
RP-ID  :  1082050

美国|英语

来源: UNT Digital Library

【 摘 要 】

It has been proposed to convert the National Institute of Standards and Technology (NIST) research reactor, known as the NBSR, from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. The motivation to convert the NBSR to LEU fuel is to reduce the risk of proliferation of special nuclear material. This report is a compilation of relevant information from recent studies related to the proposed conversion using a metal alloy of LEU with 10 w/o molybdenum. The objective is to inform the design of the mini-plate and full-size plate irradiation experiments that are being planned. This report provides relevant dimensions of the fuel elements, and the following parameters at steady state: average and maximum fission rate density and fission density, fuel temperature distribution for the plate with maximum local temperature, and two-dimensional heat flux profiles of fuel plates with high power densities. . The latter profiles are given for plates in both the inner and outer core zones and for cores with both fresh and depleted shim arms (reactivity control devices). In addition, a summary of the methodology to obtain these results is presented.