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Title: Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety

Abstract

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (US)
OSTI Identifier:
10406
Report Number(s):
ORNL/TM-1999/99
TRN: US0103541
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Aug 1999
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CRITICALITY; MULTIPLICATION FACTORS; PARAMETRIC ANALYSIS; SAFETY ANALYSIS; SPENT FUEL CASKS; SPENT FUELS; RADIOACTIVE WASTE DISPOSAL; BURNUP

Citation Formats

DeHart, M D. Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety. United States: N. p., 1999. Web. doi:10.2172/10406.
DeHart, M D. Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety. United States. https://doi.org/10.2172/10406
DeHart, M D. 1999. "Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety". United States. https://doi.org/10.2172/10406. https://www.osti.gov/servlets/purl/10406.
@article{osti_10406,
title = {Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety},
author = {DeHart, M D},
abstractNote = {Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.},
doi = {10.2172/10406},
url = {https://www.osti.gov/biblio/10406}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Aug 01 00:00:00 EDT 1999},
month = {Sun Aug 01 00:00:00 EDT 1999}
}