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Transportation System Requirements Document Revision 5
Transportation System Requirements Document Revision 5
The Nuclear Waste Policy Act of 1982 (NWPA), as amended, authorized the DOE to develop and manage a Federal system for the disposal of Spent Nuclear Fuel (SNF) and High-Level Radioactive Waste (HLW). The Office of Civilian Radioactive Waste (OCRWM) was created to manage acceptance, transportation and disposal of SNF and HLW in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence.
slides - Fuel Assembly Vibration/Shock Test - Simulating Normal Truck Transport
slides - Fuel Assembly Vibration/Shock Test - Simulating Normal Truck Transport
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Integrating Standardization into the Nuclear Waste Management System
Integrating Standardization into the Nuclear Waste Management System
Presentation to the Nuclear Waste Technical Review Board (NWTRB) in regards to integrating standardization into the nuclear waste management system.
Key Issues Associated with Interim Storage of Used Nuclear Fuel
Key Issues Associated with Interim Storage of Used Nuclear Fuel
The issue of interim storage of used (spent)1 fuel is dependent on a number of key factors, some
of which are not known at this time but are the subject of this study. The first is whether or not
the Yucca Mountain Project continues or is cancelled such that it may be able to receive spent
fuel from existing and decommissioned nuclear power stations. The second is whether the United
States will pursue a policy of reprocessing and recycling nuclear fuel. The reprocessing and
Dry Storage of Used Fuel Transition to Transport FCRD-UFD-2012-000253
Dry Storage of Used Fuel Transition to Transport FCRD-UFD-2012-000253
This report provides details of dry storage cask systems and contents in U.S. for commercial light water
reactor fuel. Section 2 contains details on the canisters used to store approximately 86% of assemblies in
dry storage in the U.S. Transport cask details for bare fuels, dual purpose casks and canister transport
casks are included in Section 3. Section 4 details the inventory of those shutdown sites without any
operating reactors. Information includes the cask type deployed, transport license and status as well as
Internationalization of the Nuclear Fuel Cycle
Internationalization of the Nuclear Fuel Cycle
Following the proposals for nuclear fuel assurance of International Atomic Energy
Agency (IAEA) Director General Mohamed El Baradei, former Russian President Vladimir V.
Putin, and U.S. President George W. Bush, joint committees of the Russian Academy of
Sciences (RAS) and the U.S. National Academies (NAS) were formed to address these and other
fuel assurance concepts and their links to nonproliferation goals. The joint committees also
addressed many technology issues relating to the fuel assurance concepts. This report provides
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
The objective of this analysis is to characterize a codisposal canister containing MIT or ORR fuel in the Five-Pack Defense High-Level Waste (5-DHLW) Waste Package (WP) to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame. The purpose of this analysis is to investigate the disposal criticality and shielding issues for the DHLW WP and establish DHLW WP and codisposal canister compatibility with the MGDS, and to provide criticality and shielding evaluations for the preliminary DHLW WP design.
Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container
Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container
The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins.
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
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.
Degraded Waste Package Criticality: Summary Report of Evaluations Through 1996
Degraded Waste Package Criticality: Summary Report of Evaluations Through 1996
The purpose of this document is to summarize the degraded waste package disposal criticality evaluations which were performed in fiscal years I995 and I996. These evaluations were described in detail in 4 previous documents (Refs. I through 4). The initial version of this summary has been described in the I996 Disposal Criticality Analysis Methodology Technical Report (Ref. 5). A topical report planned for 1998 will present the methodology in its final form for approval by the US Nuclear Regulatory Commission.
slides - Generic Communications and Guidance on Spent Fuel Storage & Transportation
slides - Generic Communications and Guidance on Spent Fuel Storage & Transportation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
The purpose of this calculation is to evaluate the transient behavior and consequences of a worst- case criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.
slides - Cook Nuclear Plant, Dry Cask Loading & Storage
slides - Cook Nuclear Plant, Dry Cask Loading & Storage
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
UCF Waste Package Criticality Analysis
UCF Waste Package Criticality Analysis
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the UCF waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan5·1 for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
Probability of a PWR Uncanistered Fuel Waste Package Postclosure Criticality
Probability of a PWR Uncanistered Fuel Waste Package Postclosure Criticality
The purpose of this calculation is to estimate the probability of criticality in a pressurized water reactor (PWR) uncanistered fuel waste package during the postclosure phase of the repository as a function of various waste package material, loading, and environmental parameters. Parameterization on the upper subcritical limit that is used to define the threshold for criticality will also be performed. The possibility of waste package misload due to human or equipment error during preclosure is also considered in estimating the postclosure criticality probability.
ANS Position Statement: The Safety of Transporting Radioactive Materials
ANS Position Statement: The Safety of Transporting Radioactive Materials
More than 45 million shipments of radioactive materials have taken place in the United States
over the last three decades, with a current rate of about three million per year. The majority of
these radioactive shipments consist of radiopharmaceuticals, luminous dials and indicators,
smoke detectors, contaminated clothing and equipment, and research and industrial sources.
Fewer than 3,500, or 0.01%, have been involved in any sort of accident, incident, or anything
slides - Generic Issue Management--An Idea Taking Flight
slides - Generic Issue Management--An Idea Taking Flight
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Isotopic Models for Commercial SNF Burnup Credit
Isotopic Models for Commercial SNF Burnup Credit
Disposal Criticality Analysis Methodology Topical Report1 describes a methodology for performing postclosure criticality analyses within the repository at Yucca Mountain, Nevada. An important component of the postclosure criticality analysis is the calculation of conservative isotopic concentrations for spent nuclear fuel. This report documents the isotopic calculation methodology. The isotopic calculation methodology is shown to be conservative based upon current data for pressurized water reactor and boiling water reactor spent nuclear fuel.
EQ6 Calculations for Chemical Degradation of Fast Flux Test Facility (FFTF) Waste Packages
EQ6 Calculations for Chemical Degradation of Fast Flux Test Facility (FFTF) Waste Packages
Fuel from the Fast Flux Test Facility ' (FFTF) has been considered for disposal at the proposed
slides - Cumulative Impact of Industry and NRC Actions
slides - Cumulative Impact of Industry and NRC Actions
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository
Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository
As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of the mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix.
Extended Storage and Transportation - Evaluation of Drying Adequacy
Extended Storage and Transportation - Evaluation of Drying Adequacy
The U.S. Nuclear Regulatory Commission (NRC) is evaluating the safety and security of spent nuclear fuel (SNF) stored in dry casks for extended time periods before transportation to a location where the SNF is further processed or permanently disposed.
Isotopic Generation and Verification of the PWR Application Model
Isotopic Generation and Verification of the PWR Application Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from pressurized water reactors (PWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (YMP 2000).
Commercial Spent Nuclear Fuel Waste Package Misload Analysis
Commercial Spent Nuclear Fuel Waste Package Misload Analysis
The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected
commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package