The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit

Brian J. Ade; William B. J. Marshall; Germina Ilas; Benjamin R. Betzler; Stephen M. Bowman

doi:10.2172/1366400

The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit

Brian J. Ade
, William B. J. Marshall
, Germina Ilas
, Benjamin R. Betzler
, Stephen M. Bowman

Research output: Other contribution › Technical Report

Abstract

Applicants for certificates of compliance for spent nuclear fuel (SNF) transportation and dry storage systems perform analyses to demonstrate that these systems are adequately subcritical per the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Parts 71 and 72. For pressurized water reactor (PWR) SNF, these analyses may credit the reduction in assembly reactivity caused by depletion of fissile nuclides and buildup of neutron-absorbing nuclides during power operation. This credit for reactivity reduction during depletion is commonly referred to as burnup credit (BUC). US Nuclear Regulatory Commission (NRC) staff review BUC analyses according to the guidance in the Division of Spent Fuel Storage and Transportation Interim Staff Guidance (ISG) 8, Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1366400
State	Published - 2017

Keywords

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

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10.2172/1366400

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title = "The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit",

abstract = "Applicants for certificates of compliance for spent nuclear fuel (SNF) transportation and dry storage systems perform analyses to demonstrate that these systems are adequately subcritical per the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Parts 71 and 72. For pressurized water reactor (PWR) SNF, these analyses may credit the reduction in assembly reactivity caused by depletion of fissile nuclides and buildup of neutron-absorbing nuclides during power operation. This credit for reactivity reduction during depletion is commonly referred to as burnup credit (BUC). US Nuclear Regulatory Commission (NRC) staff review BUC analyses according to the guidance in the Division of Spent Fuel Storage and Transportation Interim Staff Guidance (ISG) 8, Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks.",

keywords = "11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS",

author = "Ade, \{Brian J.\} and Marshall, \{William B. J.\} and Germina Ilas and Betzler, \{Benjamin R.\} and Bowman, \{Stephen M.\}",

year = "2017",

doi = "10.2172/1366400",

language = "English",

type = "Other",

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T1 - The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit

AU - Ade, Brian J.

AU - Marshall, William B. J.

AU - Ilas, Germina

AU - Betzler, Benjamin R.

AU - Bowman, Stephen M.

PY - 2017

Y1 - 2017

N2 - Applicants for certificates of compliance for spent nuclear fuel (SNF) transportation and dry storage systems perform analyses to demonstrate that these systems are adequately subcritical per the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Parts 71 and 72. For pressurized water reactor (PWR) SNF, these analyses may credit the reduction in assembly reactivity caused by depletion of fissile nuclides and buildup of neutron-absorbing nuclides during power operation. This credit for reactivity reduction during depletion is commonly referred to as burnup credit (BUC). US Nuclear Regulatory Commission (NRC) staff review BUC analyses according to the guidance in the Division of Spent Fuel Storage and Transportation Interim Staff Guidance (ISG) 8, Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks.

AB - Applicants for certificates of compliance for spent nuclear fuel (SNF) transportation and dry storage systems perform analyses to demonstrate that these systems are adequately subcritical per the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Parts 71 and 72. For pressurized water reactor (PWR) SNF, these analyses may credit the reduction in assembly reactivity caused by depletion of fissile nuclides and buildup of neutron-absorbing nuclides during power operation. This credit for reactivity reduction during depletion is commonly referred to as burnup credit (BUC). US Nuclear Regulatory Commission (NRC) staff review BUC analyses according to the guidance in the Division of Spent Fuel Storage and Transportation Interim Staff Guidance (ISG) 8, Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks.

KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

U2 - 10.2172/1366400

DO - 10.2172/1366400

M3 - Technical Report

CY - United States

ER -

The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit

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Keywords

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