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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

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT

Author
National Atomic Energy Commission
Publication Date

This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.

spent fuel safety waste management joint convention argentina waste facilities used fuel

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT

SED Publication Type

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT

Author
National Atomic Energy Commission
Publication Date

The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.

spent fuel radioactive waste waste management joint convention waste facilities used fuel

Burnup Credit — Contribution to the Analysis of the Yankee Rowe Radiochemical Assays

Burnup Credit — Contribution to the Analysis of the Yankee Rowe Radiochemical Assays

Author(s)
Wells, Alan H.
Publication Date

This report presents a methodology for validation of the isotopic
contents of spent light water reactor fuel for actinide-only burnup
credit with additional high-quality radiochemistry assay (RCA) data
obtained from the Yankee Rowe pressurized water reactor. The
additional Yankee Rowe RCA data were not included in previous
isotopic validation studies for burnup credit due to the difficulty of
accurately modeling the complex Yankee Rowe fuel assembly design
using the SAS2H one-dimensional sequence of the earlier SCALE

burnup credit spent fuel criticality analysis actinide-only spent fuel composition epri tr 1022910 used fuel

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - III: Bounding Treatment of Spatial Burnup Distributions

Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - III: Bounding Treatment of Spatial Burnup Distributions

Author(s)
Kang, C. H. ,
Lancaster, D. B.
Publication Date

A flat, uniform axial burnup assumption, preferred for its computational simplicity, does not always conservatively estimate the pressurized water reactor spent-fuel-cask multiplication factors. Rather, the reactivity effect of the significantly underburned fuel ends, usually referred to as the "end effect," can be properly treated by explicit modeling of the axial burnup distribution based on limiting axial burnup profiles.

burnup credit pwr spent fuel actinide-only spatial burnup distributions 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

HTC Experimental Program: Validation and Calculational Analysis

HTC Experimental Program: Validation and Calculational Analysis

Author(s)
Fernex, F. ,
Ivanova, T. ,
Bernard, F. ,
Letang, E.
Publication Date

In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat à l'Energie Atomique, France) with the support of the Institut de Radioprotection et de Sûreté Nucléaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions.

burnup credit criticality analysis benchmark actinide-only keff validation

Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data

Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data

Author(s)
Mueller, D. E. ,
Elam, K. R. ,
Fox, P. B.
Publication Date

In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC)
experiments was conducted by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) at the
experimental criticality facility in Valduc, France. The plutonium-to- uranium ratio and the isotopic
compositions of both the uranium and plutonium used in the simulated fuel rods were designed to be
similar to what would be found in a typical pressurized-water reactor fuel assembly that initially had an

burnup credit criticality analysis benchmark actinide-only keff validation nureg/cr-6979 ornl/tm-2007/083

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Austrian National Report

Author
Austria
Publication Date

This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).

siting national report joint convention spent fuel management austria radioactive waste management

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

Author
Argentina
Publication Date

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Answers to Questions Posted by the Contracting Parties on the Argentina Second National Report

siting national report joint convention spent fuel management argentina radioactive waste management
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