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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

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
criticality low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Author(s)
John A. McClure ,
James R. Worsham, III
Publication Date
The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP.
storage isotopic concentrations 21 pwr waste package waste package degradation criticality consequence bba000000-01717-0200-00057

Supplement to the Disposal Criticality Analysis Methodology

Supplement to the Disposal Criticality Analysis Methodology

Author(s)
CRWMS
Publication Date
The Disposal Criticality Analysis Methodology Topical Report, YMP/TR-0004Q (DOE 1998b) described a risk-informed methodology for postclosure criticality analyses in the potential repository at Yucca Mountain, Nevada. Various models contained in the methodology were described and a process for validating these models was presented. The topical report also committed to following this process in validating the models used for License Application.
disposal neutronics analysis yucca mountain criticality analysis repository license application storage postclosure risk models b00000000-01717-5705-00137

Screening Analysis of Criticality Features, Events, and Processes for License Application

Screening Analysis of Criticality Features, Events, and Processes for License Application

Author(s)
Sandia National Laboratories
Publication Date
The purpose of this analysis report is to evaluate the features, events, and processes (FEPs) associated with criticality and document the screening decision for either inclusion or exclusion of criticality in the Total System Performance Assessment for License Application (TSPA-LA). The FEPs associated with criticality address scenarios that include initiators of sequences of events or processes that could lead to configurations that have potential for criticality in the repository.
criticality yucca mountain criticality analysis license application nrc storage regulations postclosure

UNF-STANDARDS presentation to EPRI extended storage collaboration project

UNF-STANDARDS presentation to EPRI extended storage collaboration project

Author(s)
John Scaglione
Publication Date

Understanding the changing nuclear and mechanical characteristics of used nuclear fuel (UNF) over time and how these changing characteristics affect storage, transportation, and disposal options can require many tools and types of data. To streamline analysis capabilities for the waste management system, a comprehensive, integrated data and analysis tool has been assembled—UNF-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS).

disposal transportation data storage database used nuclear fuel

NRC Waste Confidence Positions

NRC Waste Confidence Positions

Author(s)
NRC
Publication Date

In response to the remand of the U.S. Court of Appeals for the District of Columbia Circuit (Minnesota v. NRC, 602 F.2d 412 (1979)), and as a continuation of previous proceedings conducted in this area by NRC (44 Fed. Reg. 61,372), the Commission initiated a generic rulemaking proceeding on October 25, 1979.

disposal spent fuel storage blue ribbon commission rulemaking waste confidence used fuel

Transportation and Storage Subcommittee Report to the Full Commission DRAFT

Transportation and Storage Subcommittee Report to the Full Commission DRAFT

Author(s)
Blue Ribbon Commission
Publication Date

The main question before the Transportation and Storage Subcommittee was whether the United States
should change its approach to storing and transporting spent nuclear fuel (SNF) and high-level
radioactive waste (HLW) while one or more permanent disposal facilities are established.
To answer this question and to develop specific recommendations and options for consideration by the
full Commission, the Subcommittee held multiple meetings and deliberative sessions, visited several

disposal transportation high level waste spent fuel storage blue ribbon commission used fuel

Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges

Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges

Author(s)
U.S. National Academy of Sciences ,
National Research Council ,
Russian Academy of Sciences
Publication Date

The so-called nuclear renaissance has increased worldwide interest in nuclear power.
This potential growth also has increased, in some quarters, concern that nonproliferation
considerations are not being given sufficient attention. In particular, since the introduction of
many new power reactors will lead to requiring an increase in uranium enrichment services to
provide the reactor fuel, the proliferation risk of adding enrichment facilities in countries that do

nuclear fuel cycle fuel fabrication nuclear engineering storage blue ribbon commission

Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

Author(s)
Mays, G. T. ,
Belles, R. J. ,
Cetiner, S. M. ,
Howard, R. L. ,
Liu, C. ,
Mueller, D. E. ,
Omitaomu, O. A. ,
Peterson, S. K. ,
Scaglione, J. M.
Publication Date

The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs).

transportation ornl/tm-2012/237 spatial data modeling geographical information systems gis storage nuclear power

Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit

Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit

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

This report proposes and documents a computational benchmark for the estimation of the
additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor
actinides in a burnup-credit storage/transport environment, relative to SNF compositions
containing only the major actinides. The benchmark problem/configuration is a generic burnupcredit
cask designed to hold 68 boiling water reactor (BWR) spent nuclear fuel assemblies. The
purpose of this computational benchmark is to provide a reference configuration for the

burnup credit bwr fission products criticality safety computational benchmark minor actinides nureg/cr-7157 ornl/tm-2012/96 estimated reactivity margin storage

Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel

Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel

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

This report has been prepared to support technical discussion of and planning for future
research supporting implementation of burnup credit for boiling-water reactor (BWR) spent fuel
storage in spent fuel pools and storage and transport cask applications. The review and
discussion in this report are based on knowledge and experience gained from work performed
in the United States and other countries, including experience with burnup credit for
pressurized-water reactor (PWR) spent fuel. Relevant physics and analysis phenomena are

burnup credit bwr criticality safety nureg/cr-7158 ornl/tm-2012/261 storage
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