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Title: Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory

Abstract

Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have completed a five-year program to investigate burnup credit (BUC) for boiling-water reactor (BWR) spent nuclear fuel (SNF) stored in storage and transportation systems. The project examined both peak reactivity BUC, also sometimes called gadolinium credit, and extended BWR BUC. Here extended refers to credit for burnups beyond that associated with peak reactivity. The findings related to peak reactivity BUC are summarized in NUREG/CR-7194, and four additional NUREG/CR documents present the results of the studies of extended BWR BUC. The first of these documents, NUREG/CR-7224, presents results of investigations to determine the effects of axial moderator density profiles, control blade use, and axial burnup profiles. Studies on the impact of core operating conditions and assembly-specific depletion conditions are addressed in NUREG/CR-7240, validation of depleted SNF isotopic predictions is addressed in NUREG/CR-7251, and validation of keff calculations for extended BWR BUC are discussed in NUREG/CR-7252. A summary of the entire project, including major conclusions regarding each of the studies, is included in this paper.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [2]
  1. ORNL
  2. Organisation for Economic Cooperation and Development, Nuclear Energy Agency
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1566984
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: International Conference on Nuclear Criticality Safety (ICNC 2019) - Paris, , France - 9/15/2019 8:00:00 AM-9/20/2019 4:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Marshall, William B.J., Ade, Brian J., Gauld, Ian C., Ilas, Germina, Mertyurek, Ugur, Clarity, Justin B., Radulescu, Georgeta, Betzler, Benjamin R., Bowman, Stephen M., and Gonzalez, Martinez. Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory. United States: N. p., 2019. Web.
Marshall, William B.J., Ade, Brian J., Gauld, Ian C., Ilas, Germina, Mertyurek, Ugur, Clarity, Justin B., Radulescu, Georgeta, Betzler, Benjamin R., Bowman, Stephen M., & Gonzalez, Martinez. Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory. United States.
Marshall, William B.J., Ade, Brian J., Gauld, Ian C., Ilas, Germina, Mertyurek, Ugur, Clarity, Justin B., Radulescu, Georgeta, Betzler, Benjamin R., Bowman, Stephen M., and Gonzalez, Martinez. Sun . "Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory". United States. https://www.osti.gov/servlets/purl/1566984.
@article{osti_1566984,
title = {Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory},
author = {Marshall, William B.J. and Ade, Brian J. and Gauld, Ian C. and Ilas, Germina and Mertyurek, Ugur and Clarity, Justin B. and Radulescu, Georgeta and Betzler, Benjamin R. and Bowman, Stephen M. and Gonzalez, Martinez},
abstractNote = {Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have completed a five-year program to investigate burnup credit (BUC) for boiling-water reactor (BWR) spent nuclear fuel (SNF) stored in storage and transportation systems. The project examined both peak reactivity BUC, also sometimes called gadolinium credit, and extended BWR BUC. Here extended refers to credit for burnups beyond that associated with peak reactivity. The findings related to peak reactivity BUC are summarized in NUREG/CR-7194, and four additional NUREG/CR documents present the results of the studies of extended BWR BUC. The first of these documents, NUREG/CR-7224, presents results of investigations to determine the effects of axial moderator density profiles, control blade use, and axial burnup profiles. Studies on the impact of core operating conditions and assembly-specific depletion conditions are addressed in NUREG/CR-7240, validation of depleted SNF isotopic predictions is addressed in NUREG/CR-7251, and validation of keff calculations for extended BWR BUC are discussed in NUREG/CR-7252. A summary of the entire project, including major conclusions regarding each of the studies, is included in this paper.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

Conference:
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