Conference papers on the IWM Execution Strategy Analysis process and tool.

The question of whether or not consolidated interim storage of commercial spent nuclear fuel (SNF) should be part of the federal waste management system as an intermediate step before permanent disposal has been debated for more than four decades. This paper summarizes an evaluation of the cost implications of incorporating a consolidated interim storage facility (ISF) into the waste management system (WMS). In this study, the order-of-magnitude estimates of total system costs were calculated and tabulated.

10 CFR 63.2 defines the geologic repository operations area (GROA) at Yucca Mountain, Nevada, as “a high-level radioactive waste facility that is part of a geologic repository, including both surface and subsurface areas, where waste handling activities are conducted.” A general description of the GROA and its location, the general nature of the activities to be performed at the GROA, and the basis for the exercise of the U.S. Nuclear Regulatory Commission (NRC) licensing authority over a geologic repository are presented in Sections 1.1, 1.2, and 1.3, respectively.

Presentation given at the NEI Used Fuel Management Conference in Savannah, Georgia on May 3, 2017. It discusses advantages and disadvantages of consolidated interim storage as well as highlights recent work related to the economics of consolidated storage.

Presentation and Paper for WM 2017. A key factor in evaluating the safety of rail shipments involving the transport of commercial spent nuclear fuel (SNF) is the development of transportation accident rates that are reflective of the unique characteristics associated with these train operations. Typical rail freight operations may involve consists of a hundred cars or more, which may pass through multiple rail yards for trains to be decoupled and reassembled. In contrast, trains carrying SNF are anticipated to be operated in consists of considerably fewer cars.

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models.

The purpose of this analysis is to provide input on the criticality potential of various degraded configurations to an analysis on the probability of a criticality event in a Pressurized Water Reactor (PWR) Advanced Uncanistered Fuel (AUCF) Waste Package (WP).

The purpose of this engineering calculation is to estimate the frequency of misloading spent nuclear fuel (SNF) assemblies that would result in exceeding the criticality design basis of a waste package (WP). This type of misload - a reactivity misload - results from the incorrect placement of one or more fuel assemblies into a waste package such that the criticality controls do not match the required controls for the fuel assemblies. An actual criticality event can not occur in a WP unless a moderator (e.g. water) is present.

The amount of spent fuel stored on-site at commercial nuclear reactors will continue to accumulate—increasing by about 2,000 metric tons per year and likely more than doubling to about 140,000 metric tons—before it can be moved off-site, because storage or disposal facilities may take decades to develop. In examining centralized storage or permanent disposal options, GAO found that new facilities may take from 15 to 40 years before they are ready to begin accepting spent fuel. Once an off-site facility is available, it will take several more decades to ship spent fuel to that facility.

The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.

The purpose of this Analysis/Model Report (AMR) is to describe probabilistically the main features of the geometry of the fracture system in the vicinity of the repository. They will be used to determine the quantity of fissile material that could accumulate in the fractured rock underneath a waste package as it degrades. This AMR is to feed the geochemical calculations for external criticality reports. This AMR is done in accordance with the technical work plan (BSC (Bechtel SAIC Company) 2001 b). The scope of this AMR is restricted to the relevant parameters of the fracture system.

This Plan outlines the Department of Energy’s (DOE) 2009 strategy and planning for developing and implementing the transportation system required to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to the proposed repository at Yucca Mountain, Nevada. As such, it is a historical document that reflected the DOE's thinking and/or approach in 2009.

Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.

The Law of 30 December 1991 [1] confers to Andra the mission of assessing the feasibility of a repository of high-level and long-lived (HLLL) waste in a deep geological formation.

The objective of this calculation is to provide the uncertainty term for fission product and minor actinides which contributes to the determination of the critical limit for burnup credit calculations. The scope of this calculation covers PWR and BWR spent nuclear fuel. This activity supports the Criticality Department's validation of burnup credit. The intended use of these results is in future Criticality Department calculations and analyses.

The U.S. Nuclear Waste Technical Review Board (Board) is tasked by the amendments to the Nuclear Waste Policy Act of 1982 to independently evaluate U. S. Department of Energy (DOE) technical activities for managing and disposing of used nuclear fuel and high-level radioactive waste. This report was prepared to inform DOE and Congress about the current state of the technical basis for extended dry storage1 of used fuel and its transportation following storage.

This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB’s application for a final repository. The purposes of the safety assessment SR-Can are the following:
1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant.

This paper is DOE's response to Wyoming Governor Mike Sullivan's decision to decline moving forward with hosting an MRS.

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

COC 71-9358 for TN-LC Transportation Pacakge

From the Introduction: The Standard Contract requires the Department to issue an annual Acceptance Priority Ranking (APR) report and an Annual Capacity Report (ACR). The APR establishes the order in which the Department allocates the projected acceptance capacity for commercial spent nuclear fuel. The ACR applies projected nominal acceptance rates for the system to the APR, resulting in individual allocations for the owners and generators expressed in metric tons of uranium (MTU).

A newsletter from the OCRWM

OCRWM receives half its fiscal year 1996 budget request

Congressional budget action halts multi-purpose canister development

Secretary of energy testifies before congress on senate bill S1271

OCRWM participates in League of Women Voters panel discussion

OCRWM HBCU Scholarship Recipients Selected

Transportation External Coordination Working Group convenes in San Antonio

This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set
forth in Title 10, Code of Federal Regulations. Part 71, "Packaging and Transportation of Radioactive Material."