[Shaw] Final Report - Task Order No. 11 - Development of Consolidated Storage Facility Design Concepts

This report has been prepared by the industry team of Shaw Environmental & Infrastructure, Inc. (Shaw) and Longenecker & Associates (L&A) in response to the Department of Energy (DOE) Statement of Work, “Development of Consolidated Storage Facility Design Concepts,” indefinite delivery/indefinite quantity Task Order No. 11, as specified by the DOE’s Office of Nuclear Energy.

A Project Concept for Nuclear Fuels Storage and Transportation

The Department of Energy (DOE) issued its Strategy for the Management and Disposition of Used Nuclear Fuel and High-Level Radioactive Waste in January 2013. DOE undertook studies and analyses to determine systems and design concepts as a preliminary step to further defining systems, equipment, and facilities to implement the Strategy. This report uses the work performed by industry and national laboratories and configures system components to meet the requirements of the Strategy. The project

Oak Ridge National Laboratory Response to DOE call for photos

Please use the following credit line for all photos “Courtesy of Oak Ridge National Laboratory, U.S. Dept. of Energy.” These photos are also available in the photo gallery.

Used Fuel Management System Architecture Evaluation, Fiscal Year 2012

In the 1990s the U.S. Department of Energy (DOE) completed a number of system analyses investigating consolidated interim storage as a part of the waste management solution. These analyses are “dated” and do not reflect the present situation regarding at-reactor used nuclear fuel (UNF) management, alternatives for away from reactor management of used nuclear fuel, and alternatives for the ultimate disposal of UNF.

Dry Cask Inventory Assessment, Rev. 1

The report, Commercial Spent Nuclear Fuel and High-Level Radioactive Waste Inventory Report(FCRD-NFST-2013-000263, Rev.3), provides information on the inventory of commercial spent fuel, referred to in this report as used nuclear fuel (UNF), as well as Government-owned UNF and High Level Waste (HLW) in the U.S. Department of Energy (DOE) complex. Inventory forecasts for commercial UNF were made for a few selected scenarios of future commercial nuclear power generation involving the existing reactor fleet including one scenario involving reactors under construction.

CISF Topical Safety Analysis Report Volumes 1 and 2

The Centralized Interim Storage Facility (CISF) is designed as a temporary, above-ground away-from-reactor spent fuel storage installation for up to 40,000 metric tons of uranium (MTU). The design is non-site-specific but incorporates conservative environmental and design factors (e.g., 360 mph tornado and 0.75 g seismic loading) intended to be capable of bounding subsequent site-specific factors. Spent fuel is received in dual-purpose canister systems and/or casks already approved for transportation and storage by the Nuclear Regulatory Commission (NRC).

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL

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.

Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Intact SNF Canister

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.

Report On External Criticality of Plutonium Waste Forms In A Geologic Repository

This report presents the analyses and results for the potential occurrence of external criticality events which could result from plutonium waste forms emplaced in a geologic repository similar to the one being developed at Yucca Mountain. The analyses evaluate both the MOX spent fuel and the immobilized plutonium waste forms in a repository if the waste package has degraded and if the fissile material has migrated to the invert and out into the far-field.

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.

ANS Position Statement: Licensing of Yucca Mountain as a Geological Repository for Radioactive Wastes

The American Nuclear Society (ANS) supports (1) the development and use of geological repositories for disposal of high-level radioactive wastes and (2) expeditious processing of the Yucca Mountain license application in an open, technically sound manner. Geological disposal means placing the wastes hundreds of feet underground and far from the biosphere. The U.S. Nuclear Regulatory Commission (NRC) is following a legislatively well-defined regulatory process to evaluate the safety of the proposed Yucca Mountain Site to meet both the scientific

Public Beliefs, Concerns and Preferences Regarding the Management of Used Nuclear Fuel and High Level Radioactive Waste

US policy for management of used nuclear fuel (UNF) and high level radioactive wastes (HLRW) is at a crossroads, and the success of new policy directions will depend in part on broad public acceptance and support. In this paper I provide an overview of the evidence concerning the beliefs and concerns of members of the American public regarding UNF and HLNW. I also characterize the evidence on American’s policy preferences for management of these materials.

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.

Probabilistic Criticality Consequence Evaluation

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department with the objective of providing a comprehensive, conservative estimate of the consequences of the criticality which could possibly occur as the result of commercial spent nuclear fuel emplaced in the underground repository at Yucca Mountain. The consequences of criticality are measured principally in terms of the resulting changes in radionuclide inventory as a function of the power level and duration of the criticality.

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

Sensitivity Study of Reactivity Consequences to Waste Package Egress Area

The criticality consequence analysis for pressurized water reactor (PWR) waste packages (WP) (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 1997) focused on results obtained by maximizing postulated rates of reactivity insertion to assure no synergistic reactions could occur among waste packages from hypothetical criticality events. Other variables potentially influencing the criticality consequences were held constant during the above referenced analysis. One of those variables

ANS Response and Comments on Nuclear Waste Administration Act of 2013 Draft

The American Nuclear Society (ANS) appreciates the opportunity to comment on the draft Nuclear Waste Administration Act (NWAA). The ANS is a not-for-profit, international, scientific, and educational organization with nearly 12,000 members worldwide. The core purpose of ANS is to promote awareness and understanding of the application of nuclear science and technology. As an organization, it has published a number of position statements regarding the issue of spent fuel and radioactive waste.

TRIGA Fuel Phase I and II Criticality Calculation

The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA (Training, Research, Isotopes, General Atomic) reactor spent nuclear fuel (SNF) with Savannah River Site (SRS) high-level waste (HLW). The TRIGA SNF is loaded into a Department of Energy (DOE) standardized SNF canister which is centrally positioned inside five-canister defense SRS HLW waste package (WP). The objective of the calculation is to investigate the criticality issues for the WP containing the five SRS HLW and DOE SNF canisters in various stages of degradation.

Disposal Criticality Analysis Methodology Topical Report Revision 2

This topical report describes the approach to the risk-informed, performance-based methodology to be used for performing postclosure criticality analyses for waste forms in the Monitored Geologic Repository at Yucca Mountain, Nevada. The risk-informed, performance-based methodology will be used during the licensing process to demonstrate how the potential for postclosure criticality will be limited and to demonstrate that public health and safety are protected against postclosure criticality.

Highly Enriched Uranium: Striking a Balance, rev. 1

In February 1996, the Department of Energy (DOE) commissioned a comprehensive effort to document and declassify the United States inventory and other information needed to present a complete picture of the production, acquisition, and utilization of highly enriched uranium (HEU). Highly Enriched Uranium:Striking A Balance presents the results of that study.

44-BWR WASTE PACKAGE LOADING CURVE EVALUATION

The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU.

Waste Package Probabilistic Criticality Analysis: Summary Report of Evaluations in 1997

The purpose of this document is to summarize the degraded waste package disposal criticality evaluations which were reported in FY 1997 (Refs. 2-6), and to explain how those evaluations have served to further develop various aspects of the overall methodology for such evaluations.

External Criticality Calculation for DOE SNF Codisposal Waste Packages

The purpose of this document is to evaluate the potential for criticality for the fissile material that could accumulate in the near-field (invert) and in the far-field (host rock) beneath the U.S. Department of Energy (DOE) spent nuclear fuel (SNF) codisposal waste packages (WPs) as they degrade in the proposed monitored geologic repository at Yucca Mountain. The scope of this calculation is limited to the following DOE SNF types: Shippingport Pressurized Water Reactor (PWR), Enrico Fermi, Fast Flux Test Facility (FFTF), Fort St.

DOE Site-Specific Transportation Campaign Fact Sheet Development Guide

US DOE collaborated with state and tribal stakeholders in the National Transportation Stakeholders Forum (NTSF) Communications ad hoc working group to develop a guide for site personnel to follow when preparing campaign-specific fact sheets.

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

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. An internal WP criticality is modeled in a manner analogous to transient phenomena in a nuclear reactor core.