Monticello BWR spent fuel assembly decay heat predictions and measurements

Abstract

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How well does ORIGEN predict spent LWR (Light Water Reactor) fuel characteristics

“…The experimental heat-generation data for fuel assemblies have been compared with those predicted using 0RIGEN2 (4)(5)(6)(7)(8)(9)(10)(11). Comparisons of measured values with those predicted by ORIGEN agree to within ±10%; the experimental data scatter is also ~±10%.…”

“…Gainma exposure rates have been measured near full fuel bundles in a pool experiment (12) and surrounding a partially and fully loaded spent fuel storage cask (8,11). In both cases, a combination of an ORIGEN code for prediction of the photon source and a radiation transport code were required; this makes it impossible to completely separate experimental errors from inaccuracies introduced by the codes.…”

“…Neutron dose rate measurements were made on the same partially and completely filled storage cask as was used for gamma measurements (8,11).…”

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

“…At present, such data are primarily based on a combination of destructive chemical and radiochemical analysis methods (OECD NEA, 2016;Michel-Sendis et al, 2017), involving various steps starting with the dissolution of the sampled material, affecting the final uncertainty of the results (OECD NEA, 2011). Data obtained by NDA are rather scarce and limited to the measurement of the decay power by calorimetry (McKinnon et al, 1986;Maeda et al, 2004;SKB, 2006;Murphy and Gauld, 2010). Most of the data originate from measurements at the calorimeter installed at Clab, the Swedish Interim Storage Facility (SKB, 2006;Murphy and Gauld, 2010).…”