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Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Author(s)
OCRWM
Publication Date
The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation.
high level waste radiation protection storage hanford site 2-mco/2-dhlw dose calculation multi-canister overpack defense

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

Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Author(s)
Duke Engineering & Services, Inc.
Publication Date
The Design Criteria Policy Document will provide guidance on the types of Design Events, Design Basis Accidents, and Design Criteria for Important To Radiological Safety Systems, Structures, and Components (SSCs) to be assumed during the design of the MRS facility. Definitions of key terms associated with Design Events are also included with this document. Appropriate combinations of Design Events and criteria is identified.
structure analysis spent fuel mol.19970729.0629 mrs radioactive waste radiation protection storage used fuel

Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF

Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.

transportation yucca mountain criticality safety radiation protection storage canister doe spent nuclear fuel

Storage of Spent Nuclear Fuel (Specific Safety Guide)

SED Publication Type

Storage of Spent Nuclear Fuel (Specific Safety Guide)

Author
IAEA
Publication Date

This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup.

spent fuel radiation protection storage public health public safety 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).

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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

Radionuclide Screening

Radionuclide Screening

Author(s)
Sandia National Laboratories
Publication Date

The waste forms under consideration for disposal in the repository at Yucca Mountain contain scores of radionuclides. It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from a nuclear waste repository at Yucca Mountain.

yucca mountain epa radiation protection storage radionuclides radiation dose postclosure

Preclosure Consequence Analyses

Preclosure Consequence Analyses

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The purpose of this calculation is to demonstrate that the preclosure performance objectives specified in 10 CFR 63.111(a) and 10 CFR 63.111(b) (Reference 2.2.1) have been met for the proposed design and operations in the geologic repository operations area (GROA) during normal operations and Category 1 event sequences, and following Category 2 event sequences. Category 1 event sequences are those natural and human-induced event sequences that are expected to occur one or more times before permanent closure of the repository.

yucca mountain radiation protection radiation dose preclosure environmental radiation protection public safety geologic repository operations area (groa)

Canister Handling Facility Criticality Safety Calculations

Canister Handling Facility Criticality Safety Calculations

Author(s)
OCRWM
Publication Date

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).

spent fuel criticality safety safety radiation protection canister used fuel

Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF

Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.

transportation, aging and disposal (tad) yucca mountain commercial spent nuclear fuel criticality safety radiation protection canister

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

Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document

SED Publication Type

Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document

Author
EPA
Publication Date

EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.

disposal high level waste spent fuel yucca mountain licensing epa dose radiation protection wipp siting regulations used fuel
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