Analysis with the ORIGEN Module of PNAR Spent Fuel Measurements for Nuclear Safeguards Applications

Hu, Jianwei; Ilas, Germina; Gauld, Ian C

doi:10.2172/1760108

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2022

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“…Validation for neutron and gamma spectra in spent nuclear fuel, which is of particular interest to nuclear safeguards and nonproliferation applications, is not addressed in this report. However, such validation studies are available in the literature [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

SCALE 6.2.4 Validation: Reactor Physics

Ilas¹,

Burns²,

Hiscox³

et al. 2022

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This report is the third volume in a report series documenting the validation of SCALE 6.2.4, which is used herein with ENDF/B-VII.1 libraries, for nuclear criticality safety, reactor physics, and radiation shielding applications. This report focuses on validating SCALE capabilities that affect reactor physics applications. The experimental data used as basis for validation consists of measurement data for nuclide inventory, decay heat, and full-core experiments and include the following: NuclideNo. of samples Application a

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Section: Introductionmentioning

confidence: 99%