Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package

The objective of this calculation is to perform intact and degraded mode criticality evaluations of the U.S. Department of Energy’s (DOE) Advanced Test Reactor (ATR) Spent Nuclear Fuel (SNF) placed in the DOE standardized SNF canister. This analysis evaluates the codisposal of the DOE SNF canister containing the ATR SNF in a 5-Defense High-Level Waste (5-DHLW) Short Waste Package (WP) (Bechtel SAIC Company, LLC [BSC] 2004a), which is to be placed in a monitored geologic repository (MGR).

Criticality Evaluation of Plutonium Disposition Ceramic Waste Form: Degraded Mode

The purpose of this calculation is to perform degraded mode criticality evaluations of Plutonium disposed in a ceramic waste form and emplaced in a Monitored Geologic Repository (MGR). A 5 Defense High-Level Waste (DHLW) Canister Waste Package (WP) design, incorporating the can-in-canister concept for Plutonium immobilization is considered for this calculation. Each HLW glass pour canister contains 7 tubes. Each tube contains 4 cans, with 20 ceramic disks (immobilzed Plutonium) in each.

Commercial Reactor Criticality Depletion For Grand Gulf, Unit 1

The objectie of this calculation is to document the Grand Gulf, Unit 1, (GG1) fuel depletion calculations. The GG1 reactor is a boiling water reactor (BWR) owned and operated by Entergy Operations Inc. The Commercial Reactor Criticality (CRC) evaluations support the development and validation of the neutronic models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation is performed as part of the evaluation CRC program. This report is an engineering calculation supporting the burnup credit methodology of YMP 2000 (Ref.

Humboldt Bay License Termination Plan

The license termination plan for Humboldt Bay owned by the Pacific Gas and Electric Company.

3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degradedmode criticality performance.

Wyoming Decline of MRS

This letter is written by Former Wyoming Governor Mike Sullivan to inform the Fremont County Commissioners of his conclusion to decline the MRC facility.

Radiolytic Specie Generation from Internal Waste Package Criticality

The effects of radiation on the corrosion of various metals and alloys, particularly with respect to in-reactor processes, has been discussed by a number of authors (Shoesmith and King 1998, p.2). Shoesmith and King (1998) additionally discuss the effects of radiation of the proposed Monitored Geologic Repository (MGR) Waste Package (WP) materials. Radiation effects on the corrosion of metals and alloys include, among other things, radiolysis of local gaseous and aqueous environments lead to the fixation of nitrogen as NO, NO2, and especially HN03 (Reed and Van Konynenburg 1988, pp.

Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository, Volume II: Immobilized In Ceramic

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 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.

Nuclear Energy Research and Development Roadmap

To achieve energy security and greenhouse gas (GHG) emission reduction objectives, the United States must develop and deploy clean, affordable, domestic energy sources as quickly as possible. Nuclear power will continue to be a key component of a portfolio of technologies that meets our energy goals. This document provides a roadmap for the Department of Energy’s (DOE’s) Office of Nuclear Energy (NE) research, development, and demonstration activities that will ensure nuclear energy remains viable energy option for the United States.

Environmental Impact Statement, Management of Commercially Generated Radioactive Waste. Volume 1

In the course of producing electrical power in light water reactors (LWRs), the uranium fuel accumulates fission products until the fission process is no longer efficient.for power production. At that point the fuel is removed from the reactor and stored in water basins to allow radioactivity to partially decay before further disposition. This fuel is referred to as "spent fuel." Although spent fuel as it is discharged from a reactor is intensely radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could

Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty

Analytical methods, described in this report, are used to systematically determine experimental fuel sub-batch reactivities as a function of burnup. Fuel sub-batch reactivities are inferred using more than 600 in-core pressurized water reactor (PWR) flux maps taken during 44 cycles of operation at the Catawba and McGuire nuclear power plants. The analytical methods systematically search for fuel sub-batch reactivities that minimize differences between measured and computed reaction rates, using Studsvik Scandpower’s

Feasibility of Direct Disposal of Dual-Purpose Canisters-Options for Assuring Criticality Control

The concept of direct disposal of dual-purpose canisters (DPCs) has not been previously considered for the Yucca Mountain geologic repository because of concerns, among other reasons, about degradation of the reactivity-control material over the relatively long period of the repository analyses. Aluminum-based neutron absorber materials, typically used in DPCs, are not expected to have sufficient corrosion resistance necessary to retain their integrity over a 10,000+

Dry Transfer System for Spent Fuel: Project Report: A System Designed to Achieve the Dry Transfer of Bare Spent Fuel Between Two Casks

Use of an on-site dry transfer system (DTS) allows utilities with limited crane capacities or other plant restrictions to take advantage of large efficient storage systems. By using this system, utilities can also transfer fuel from loaded storage casks to transport casks without returning to their fuel storage pool.

Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems

Due to the delayed opening of a final geological repository for spent nuclear fuel, the lifespan of dry cask storage systems may be increased to 120 years or longer. To ensure safety over this extended period of interim storage, degradation mechanisms that have the potential to cause penetration of the canister confinement boundary must be evaluated and understood.

Calvert Cliffs Stainless Steel Dry Storage Canister Inspection

Stress corrosion cracking (SCC) of welded stainless steel dry storage canisters may potentially impact systems exposed to corrosive atmospheric elements, such as those occurring near salt water bodies. Conditions important for atmospheric-related SCC include concentration and chemical species of the contaminants, temperature, and humidity. Calvert Cliffs Nuclear Power Plant conducted this historically important first inspection of spent fuel canisters to collect data for an SCC evaluation as part of the EPRI-led Extended Storage Collaboration Program (ESCP).

NRC SFST ISG-2: Fuel Retrievability

This Interim Staff Guidance (ISG) provides guidance to the staff for determining if storage systems to be licensed under 10 CFR Part 72 allow ready retrieval of spent fuel. This guidance is not a regulation or a requirement.

NRC ISG-1: Classifying the Condition of Spent Nuclear Fuel for Interim Storage and Transportation Based on Function

This Interim Staff Guidance (ISG) provides guidance to the staff on classifying spent nuclear fuel as either (1) damaged, (2) undamaged, or (3) intact, before interim storage or transportation. This is not a regulation or requirement and can be modified or superseded by an applicant with supportable technical arguments. Revision 2

NRC SFST ISG-3: Post Accident Recovery and Compliance with 10 CFR 72.122(l)

Compliance with 10 CFR 72.122(l) has been interpreted to mean that a licensee, during any point in the storage cycle, must have a means of retrieving and repackaging individual fuel assemblies even after an accident. The staff has reevaluated this interpretation.

NRC SFST ISG-4: Cask Closure Weld Inspections

The closure weld for the outer cover plate for austenitic stainless steel designs may be inspected using either volumetric or multiple pass dye penetrant techniques subject to the following conditions: • Dye penetrant (PT) examination may only be used in lieu of volumetric examination only on austenitic stainless steels. PT examination should be done in accordance with ASME Section V, Article 6, “Liquid Penetrant Examination.” • For either ultrasonic examination (UT) or PT examination, the minimum

Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability

Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability GAO-15-141: Published: Oct 9, 2014. Publicly Released: Nov 12, 2014.

2015 NEI Used Fuel Management Conference Presentations

Link to NEI's website where the 2015 NEI Used Fuel Management Conference presentations can be downloaded. Day 1 Session 0, Opening Plenary Korsnick, Maria Exelon Generation Nuclear Energy in a Changing Marketplace Lombard, Mark U.S. Nuclear Regulatory Commission NRC Management Perspective: What’s Up? McCullum, Rod Nuclear Energy Institute Management Perspectives Session 1, Used Fuel Policy

Public Participation in Environmental Assessment and Decision Making

The National Research Council established the Panel on Public Participation in Environmental Assessment and Decision Making at the request of U.S. Environmental Protection Agency, the U.S. Department of Energy, and the U.S. Food and Drug Administration, with additional support from the U.S. Forest Service, to assess whether, and under what conditions, public participation achieves the outcomes desired.

Designing a Process for Selecting a Site for a Deep-Mined, Geologic Repository for High-Level Radioactive Waste and Spent Nuclear Fuel

If policymakers decide to launch a new repository-siting effort, an understanding of previ¬ous repository-siting efforts, both in the United States and abroad, might help to inform decisions defining and implementing the siting process. For this reason and to apprise the public of a critical issue associated with the long-term management of HLW and SNF, the U.S. Nuclear Waste Technical Review Board has written this report.

Stakeholder Involvement in Decision Making: A Short Guide to Issues, Approaches and Resources

Radioactive waste management is embedded in broader societal issues such as the environment, risk management, energy, health policy and sustainability. In all these fields, there is an increasing demand for public involvement, participation and engagement. Involvement may take different forms at different phases and can include sharing information, consulting, dialoguing or deliberating on decisions with relevant stakeholders. Stakeholder involvement should be seen as a

Multipurpose Canister System Design Synopsis Report

The multipurpose canister (MPC) concept can simplify the management of spent nuclear fuel by enclosing the fuel permanently in a canister that can be used for long-term dry storage at a utility site, transportation to an interim federal storage facility, and eventual disposal in a repository. This synopsis report summarizes the key design and analysis features of the U.S. Department of Energy (DOE) MPC program.