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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

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

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)

Author(s)
NRC
Publication Date

This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.

pwr bwr operation regulations radioactive waste management standard technical specifications

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

Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B

Preliminary Transportation, Aging and Disposal Canister System Performance Specification Requirements Rationale, Revision B

Author(s)
DOE Office of Civilian Radioactive Waste Management
Publication Date

The purpose of this document is to provide the requirements rationale for the current version of the Preliminary Transportation, Aging and Disposal Canister System Performance Specification; WMO-TADCS-000001.

transportation radioactive waste radioactive waste management aging and disposal (tad)

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

UNF-ST&DARDS presentation to WM2015

UNF-ST&DARDS presentation to WM2015

Author(s)
Kaushik Banerjee
Publication Date

A comprehensive, integrated data and analysis tool—the Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) —is being developed for the US DOE Office of Nuclear Energy (DOE-NE) Nuclear Fuels Storage and Transportation Planning Project (NFST). The overarching goal of UNF-ST&DARDS is to provide a comprehensive controlled source of technical data integrated with key analysis capabilities to characterize inputs to the overall US waste management system from reactor power production through ultimate disposition.

unf-st&dards snf

Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management

SED Publication Type

Emergence of Collective Action and Environmental Networking in Relation to Radioactive Waste Management

Author
Williams, R. G. ,
Payne, B. A.
Publication Date

This paper explores the relationship between the national environmental movement and nuclear technology in relation to a local emergent group. The historical development of nuclear technology in this country has followed a path leading to continued fear and mistrust of waste management by a portion of the population. At the forefront of opposition to nuclear technology are people and groups endorsing environmental values.

siting environmental networking local action group radioactive waste management

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

Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule

SED Publication Type

Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule

Author
EPA
Publication Date

We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.

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

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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report, Revision 2.3

Author
Czech Republic
Publication Date

. On 25 March 1999 the Government of the Czech Republic approved the Joint Convention which came into effect in the Czech Republic on 18 June 2001. In agreement with the obligations resulting from its accession to the Joint Convention the Czech Republic has already drawn the second National Report for the purposes of Review Meetings of the Contracting Parties, which describes the system of spent fuel and radioactive waste management in the scope required by selected articles of the Joint Convention.

siting national report joint convention spent fuel management czech republic radioactive waste management
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