Transition Core Planning and Safety Analyses in Support of LEU Fuel Conversion of the University of Missouri Research Reactor (MURR)

Abstract

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University of Missouri Research Reactor LEU Fuel Element Flow Test Conceptual Design—Hydraulic Reactor Design Parameters

“…(4.3) and (4.4) is calculated using the total flow area and wetted perimeter of an element. This simplified approach is also used in the previous safety analyses of MURR [5,8] for estimating the core flow rate of the analyses.…”

“…In MURR LEU safety analysis [5,8], a maximum of 0.008 inch channel gap reduction (0.004 inch for end channels) is used at the maximum burnup (180 MWd), and a linear relation between burnup and the channel gap reduction is assumed. The approach of 0.008 inch maximum channel gap reduction and linear relation with burnup is followed in this work.…”

“…The fuel element burnup amount used for the calculations presented here is assumed following the analysis for the MURR LEU equilibrium core [5,8]. Since the fuel elements of MURR are loaded in pairs, each pair of elements will have the same burnup level.…”

“…Recently, the planning and safety analysis for the sequence of transition cores in support of the conversion from HEU to equilibrium LEU operations have been finished [5].…”

“…a Refer to Figure2.1 (a) for element location in the core. b Burnup is from MURR LEU equilibrium core[5,8].…”