An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel

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Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determination of source terms for subsequent system analyses involving heat transfer, radiation shielding, isotopic migration, etc. Unlike fresh fuel assumptions typically employed in the criticality safety analysis of spent fuel configurations, burnup credit applications also rely on depletion and decay calculations to predict the isotopic composition of spent fuel. These isotopics are used in subsequent criticality calculations to assess the reduced worth of spent fuel. To validate the codes and data used in depletion approaches, experimental measurements are compared with numerical predictions for relevant spent fuel samples. ... continued below

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124 pages

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DeHart, M.D. January 1, 1993.

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Description

Isotopic characterization of spent fuel via depletion and decay calculations is necessary for determination of source terms for subsequent system analyses involving heat transfer, radiation shielding, isotopic migration, etc. Unlike fresh fuel assumptions typically employed in the criticality safety analysis of spent fuel configurations, burnup credit applications also rely on depletion and decay calculations to predict the isotopic composition of spent fuel. These isotopics are used in subsequent criticality calculations to assess the reduced worth of spent fuel. To validate the codes and data used in depletion approaches, experimental measurements are compared with numerical predictions for relevant spent fuel samples. Such comparisons have been performed in earlier work at the Oak Ridge National Laboratory (ORNL). This report describes additional independent measurements and corresponding calculations, which supplement the results of the earlier work. The current work includes measured isotopic data from 19 spent fuel samples obtained from the Italian Trino Vercelles pressurized-water reactor (PWR) and the U.S. Turkey Point Unit 3 PWR. In addition, an approach to determine biases and uncertainties between calculated and measured isotopic concentrations is discussed, together with a method to statistically combine these terms to obtain a conservative estimate of spent fuel isotopic concentrations. Results are presented based on the combination of measured-to-calculated ratios for earlier work and the current analyses. The results described herein represent an extension to a new reactor design not included in the earlier work, and spent fuel samples with enrichment as high as 3.9 wt % {sup 235}U. Results for the current work are found to be, for the most part, consistent with the findings of the earlier work. This consistency was observed for results obtained from each of two different cross-section libraries and suggests that the estimated biases determined for each of the isotopes in the earlier work are reasonably good estimates, as the additional measurement/calculated ratios resulting from the current work tend to confirm these estimates.

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124 pages

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  • Other Information: PBD: 1 Jan 1993

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  • Report No.: ORNL/TM-13317
  • Grant Number: AC05-00OR22725
  • DOI: 10.2172/814107 | External Link
  • Office of Scientific & Technical Information Report Number: 814107
  • Archival Resource Key: ark:/67531/metadc736019

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  • January 1, 1993

Added to The UNT Digital Library

  • Oct. 18, 2015, 6:40 p.m.

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  • March 30, 2016, 8:23 p.m.

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DeHart, M.D. An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel, report, January 1, 1993; United States. (digital.library.unt.edu/ark:/67531/metadc736019/: accessed November 14, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.