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Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

Author(s)
SR Suffield ,
JM Cuta ,
JA Fort ,
BA Collins ,
HE Adkins ,
ER Siciliano
Publication Date
As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). The inspection procedure included surface temperature measurements on one end of the DSC within the storage module.
isfsi thermal modeling used nuclear fuel thermal performance sensitivity study nuhoms computational fluid dynamics cobra-sfs

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions

Author(s)
Radulescu, G. ,
Gauld, I. C. ,
Ilas, G. ,
Wagner, J. C.
Publication Date

Taking credit for the reduced reactivity of spent nuclear fuel in criticality analyses is referred to
as burnup credit. Criticality safety evaluations employing burnup credit require validation of the
depletion and criticality calculation methods and computer codes with available measurement
data. To address the issues of burnup credit criticality validation, the U.S. Nuclear Regulatory
Commission initiated a project with Oak Ridge National Laboratory to (1) develop and establish

fission products nureg/cr-7108 ornl/tm-2011/509 criticality aalysis burnup credit spent fuel composition validation sensitivity analysis

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Author(s)
Radulescu, G. ,
Mueller, D. E. ,
Wagner, J. C.
Publication Date

This paper provides insights into the neutronic similarities between a representative high-capacity rail-transport cask containing typical pressurized water reactor (PWR) spent nuclear fuel assemblies and critical reactor state-points, referred to as commercial reactor critical (CRC) state-points. Forty CRC state-points from five PWRs were analyzed, and the characteristics of CRC state-points that may be applicable for validation of burnup-credit criticality safety calculations for spent fuel transport/storage/disposal systems were identified.

burnup credit spent fuel criticality analysis keff validation spent fuel composition sensitivity analysis used fuel

Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel

Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel

Author(s)
Electric Power Research Institute
Publication Date

As nuclear power plants began to run out of storage capacity in spent nuclear fuel (SNF) storage pools, many nuclear operating companies added higher density pool storage racks to increase pool capacity. Most nuclear power plant storage pools have been re-racked one or more times. As many spent fuel storage pools were re-racked to the maximum extent possible, nuclear operating companies began to employ interim dry storage technologies to store SNF in certified casks and canister-based systems outside of the storage pool in independent spent fuel storage installations (ISFSIs).

isfsi spent fuel dry cask storage centralized spent fuel storage interim storage blue ribbon commission used fuel independent spent fuel storage independent spent fuel storage installation (isfsi)

Technical Bases for Extended Dry Storage of Spent Nuclear Fuel

Technical Bases for Extended Dry Storage of Spent Nuclear Fuel

Author(s)
Electric Power Research Institute
Publication Date

Independent spent fuel storage installations (ISFSIs) are currently licensed for 20 years. However, delays in developing permanent spent fuel disposal capability require continued ISFSI storage beyond the 20-year term. This report provides a technical basis for demonstrating the feasibility of extended spent fuel storage in ISFSIs.

isfsi spent fuel casks fuel assemblies licensing storage material degradation waste package degradation used fuel spent fuel storage aging

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Author(s)
Wagner, J. C. ,
Mueller, D. E. ,
Radulescu, G.
Publication Date

The purpose of this study is to provide insights into the neutronic similarities that may exist between a
generic cask containing typical spent nuclear fuel assemblies and commercial reactor critical (CRC) state-
points. Forty CRC state-points from five pressurized-water reactors were selected for the study and the
type of CRC state-points that may be applicable for validation of burnup credit criticality safety
calculations for spent fuel transport/storage/disposal systems are identified. The study employed cross-

burnup credit criticality analysis nureg/cr-6951 ornl/tm-2006/87 keff validation spent fuel composition crc sensitivity analysis

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages

Author(s)
DeHart, M. D.
Publication Date

Spent fuel transportation and storage cask designs based on a burnup credit approach must
consider issues that are not relevant in casks designed under a fresh-fuel loading assumption. For
example, the spent fuel composition must be adequately characterized and the criticality analysis
model can be complicated by the need to consider axial burnup variations. Parametric analyses are
needed to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel

burnup credit pwr spent fuel ornl/tm-12973 sensitivity analysis used fuel

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions

Author(s)
Scaglione, J. M. ,
Mueller, D. E. ,
Wagner, J. C. ,
Marshall, W. J.
Publication Date

Taking credit for the reduced reactivity of spent nuclear fuel (SNF) in criticality analyses is referred to as burnup credit (BUC). Criticality safety evaluations require validation of the computational methods with critical experiments that are as similar as possible to the safety analysis models, and for which the keff values are known. This poses a challenge for validation of BUC criticality analyses, as critical experiments with actinide and fission product (FP)

burnup credit spent fuel fission products nureg/cr-7109 ornl/tm-2011/514 criticality analysis keff validation sensitivity analysis used fuel

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL

Author(s)
HE Adkins ,
JA Fort ,
SR Suffield ,
JM Cuta
Publication Date

The work reported here is an investigation of the sensitivity of component temperatures in a specific storage system, including fuel cladding temperatures, in response to modeling assumptions that differ from design-basis, including age-related changes that could degrade the thermal behavior of the system. Preliminary evaluations of representative horizontal and vertical storage systems at design basis conditions provides general insight into the expected behavior of storage systems over extended periods of time.

isfsi cfd material degradation used nuclear fuel material modeling thermal performance sensitivity study nuhoms computational fluid dynamics ufd pnnl hsm15

DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION

DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION

Author(s)
TLG Services, Inc. ,
Exelon Generation Company, LLC ,
William Cloutier ,
John Carlson ,
Francis Seymore
Publication Date

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isfsi wet storage decommissioning cost estimate exelon clinton ml13063a531 e16-1640-006

Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT

Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT

Author(s)
Duke Energy ,
Terry Hobbs ,
William Cloutier ,
John Carlson ,
Francis Seymore ,
TLG Services, Inc.
Publication Date

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isfsi wet storage crystal river decommissioning cost estimates dpr-72 50-302 ml13340a008 ml13343a178

ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS

ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS

Author(s)
Federal Energy Regulatory Commission
Publication Date

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isfsi maine yankee connecticut yankee wet storage yankee rowe shutdown sites cost estimate yankees er13-1395-000 er13-1399-000 143 ferc 61289 er13-1397-000

Civilian Nuclear Spent Fuel Temporary Storage Options

SED Publication Type

Civilian Nuclear Spent Fuel Temporary Storage Options

Author
Mark Holt
Publication Date

The Department of Energy (DOE) is studying a site at Yucca Mountain, Nevada, for a permanent underground repository for highly radioactive spent fuel from nuclear reactors, but delays have pushed back the facility’s opening date to 2010 at the earliest. In the meantime, spent fuel is accumulating at U.S. nuclear plant sites at the rate of about 2,000 metric tons per year. Major options for managing those growing quantities of nuclear spent fuel include continued storage at reactors, construction of a DOE interim storage site near Yucca Mountain, and licensing of private storage facilities.

isfsi spent fuel interim storage underground repository used fuel
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