Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Keywords
Analysis of Critical Benchmark Experiments for Configurations External to WP
Analysis of Critical Benchmark Experiments for Configurations External to WP
The Disposal Criticality Analysis Methodology Topical Report (Reference 1) states that the accuracy of the criticality analysis methodology (MCNP Monte Carlo code and cross-section data) designated to assess the potential for criticality of various configurations in the Yucca Mountain proposed repository is established by evaluating appropriately selected benchmark critical experiments.
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).
Budget and Financial Management Improvements to the Nuclear Waste Fund (NWF)
Budget and Financial Management Improvements to the Nuclear Waste Fund (NWF)
The paper discusses issues and options for improving the budgeting and financial management
of the Nuclear Waste Fund (NWF). The issues and options would facilitate implementation of
any changes in program scope and content, or any changes in organization and management
structure. .
The three issues for possible administrative action include:
1. Instituting financial management enhancements to foster multi-year budgeting and
appropriations; combined accrual and cash budgeting; and separate capital budgeting;
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
The purpose of this study is to provide insights into the neutronic similarities that may exist between a
generic cask containing typical spent nuclear fuel assemblies and commercial reactor critical (CRC) state-
points. Forty CRC state-points from five pressurized-water reactors were selected for the study and the
type of CRC state-points that may be applicable for validation of burnup credit criticality safety
calculations for spent fuel transport/storage/disposal systems are identified. The study employed cross-
Long-Term Criticality Control Issues for the MPC (SCPB: N/A)
Long-Term Criticality Control Issues for the MPC (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) in response to a request received via a QAP-3-12 Design Input Data Request (Reference 5.1) from Waste Acceptance, Storage, & Transportation (WAST) Design (formerly MRSMPC Design). This design analysis is an answer to the Design Input Data Request to provide: Specific requirements for long-term criticality control.
Characteristics of Potential Repository Wastes
Characteristics of Potential Repository Wastes
The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for all spent fuels and high-level wastes (HLW) that will eventually be disposed of in a geologic repository. The purpose of this document, and the information contained in the associated computerized data bases and supporting technical reports, is to provide the technical characteristics of the radioactive waste materials that will (or may) be accepted by DOE for interim storage in an MRS or emplacement in a repository as developed under the Nuclear Waste Policy Act Amendment of 1987.
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
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transporation of Used Fuel Rev. 1
Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transporation of Used Fuel Rev. 1
Because there is currently no designated disposal site for used nuclear fuel in the United States, the nation faces the prospect of extended long‐term storage (i.e., >60 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S.
Transportation and Storage Subcommittee Report to the Full Commission DRAFT
Transportation and Storage Subcommittee Report to the Full Commission DRAFT
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
Summary Report of Commercial Reactor Criticality Data for Quad Cities Unit 2
Summary Report of Commercial Reactor Criticality Data for Quad Cities Unit 2
Review of Information for Spent Nuclear Fuel Burnup Confirmation
Review of Information for Spent Nuclear Fuel Burnup Confirmation
The Interim Staff Guidance on burnup credit (ISG-8, revision 2) for pressurized-water-reactor spent
nuclear fuel in storage and transport casks, issued in 2002 by the U.S. Nuclear Regulatory Commission’s
Spent Fuel Project Office, recommends an out-of-core burnup measurement to confirm the reactor record
and compliance with the assembly burnup value used for cask loading acceptance. This recommendation
is intended to prevent unauthorized loading (i.e., misloading) of assemblies due to inaccuracies in reactor
Probabilistic External Criticality Evaluation (SCPB: N/A)
Probabilistic External Criticality Evaluation (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.
Blue Ribbon Commission on America’s Nuclear Future Draft Report to the Secretary of Energy
Blue Ribbon Commission on America’s Nuclear Future Draft Report to the Secretary of Energy
America’s nuclear waste management program is at an impasse. The Obama Administration’s decision
to halt work on a repository at Yucca Mountain in Nevada is but the latest indicator of a policy that has
been troubled for decades and has now all but completely broken down. The approach laid out under
the 1987 Amendments to the Nuclear Waste Policy Act (NWPA)—which tied the entire U.S. high-level
waste management program to the fate of the Yucca Mountain site—has not worked to produce a
Screening Analysis of Criticality Features, Events, and Processes for License Application
Screening Analysis of Criticality Features, Events, and Processes for License Application
This analysis documents the screening analysis for postclosure criticality features, events, and
processes (FEPs). It addresses the probability of criticality events resulting from degradation
processes as well as disruptive events (i.e., seismic, igneous, and rockfall). Probability
evaluations are performed utilizing the configuration generator model described in Configuration
Generator Model for In-Package Criticality1, a component of the methodology from Disposal
The Potential of Using Commercial Dual Purpose Canisters for Direct Disposal
The Potential of Using Commercial Dual Purpose Canisters for Direct Disposal
This report evaluates the potential for directly disposing of licensed commercial Dual Purpose
Canisters (DPCs) inside waste package overpacks without reopening. The evaluation considers
the principal features of the DPC designs that have been licensed by the Nuclear Regulatory
Commission (NRC) as these relate to thedesigns of waste packages and as they relate to
disposability in a repository in unsaturated volcanic tuff. Where DPC features appear to compromise future disposability in an unsaturated tuff (e.g., Yucca Mountain) repository
Total System Model Version 6.0 Transportation Design and Bases
Total System Model Version 6.0 Transportation Design and Bases
The Civilian Radioactive Waste Management System (CRWMS) Total System Model (TSM) is
a planning tool that estimates the logistic and cost impacts of various operational assumptions in
accepting radioactive wastes. Waste forms currently tracked are commercial spent nuclear fuel
(CSNF), Department of Energy (DOE) Spent Nuclear Fuel (DOE SNF), and High-Level
(radioactive) Waste (HLW). The TSM and associated programs analyze and simulate the actions
for waste acceptance from discharge until emplacement.
Letter to President Obama - Blue Ribbon Commission
Letter to President Obama - Blue Ribbon Commission
Dear Mr. President:
At your direction, the Secretary of Energy established the Blue Ribbon Commission on
America’s Nuclear Future to review policies for managing the back end of the nuclear
fuel cycle and recommend a new strategy. We are pleased to be serving as Co‐
Chairmen of the Commission, and we are writing to you to highlight an important action
we strongly believe should be reflected in your Fiscal Year 2013 baseline budget
projections.
In our draft report to the Secretary, issued in July of this year, the Commission
Letter from the BRC to the Members of the South Carolina Congressional Delegation
Letter from the BRC to the Members of the South Carolina Congressional Delegation
Dear Members of the South Carolina Congressional Delegation:
Thank you all for your letter of October 27th. We appreciate hearing your views on the
Yucca Mountain project, the safety benefits of deep geologic disposal, and the
importance of the retaining the H Canyon facility at the Department of Energy’s
Savannah River Site.
In our draft report, the Commission finds that deep geologic disposal is an essential
component of a comprehensive nuclear waste management system. Your comments
CRC Reactivity Calculations for Crystal River Unit 3
CRC Reactivity Calculations for Crystal River Unit 3
The purpose of this calculation is to document the Crystal River Unit 3 pressurized waste reactor (PWR) reactivity calculations performed as part of the commercial reactor critical (CRC) evaluation program. CRC evaluation reactivity calculations are performed at a number of statepoints, representing reactor start-up critical conditions at either beginning of life (BOL), beginning of cycle (BOC), or mid-cycle when the reactor resumed operation after a shutdown.
Isotopic Analysis of High-Burnup PWR Spent Fuel Samples from the Takahama-3 Reactor
Isotopic Analysis of High-Burnup PWR Spent Fuel Samples from the Takahama-3 Reactor
This report presents the results of computer code benchmark simulations against spent fuel radiochemical assay
measurements from the Kansai Electric Ltd. Takahama-3 reactor published by the Japan Atomic Energy
Research Institute. Takahama-3 is a pressurized-water reactor that operates with a 17 × 17 fuel-assembly design.
Spent fuel samples were obtained from assemblies operated for 2 and 3 cycles and achieved a maximum burnup
of 47 GWd/MTU. Radiochemical analyses were performed on two rods having an initial enrichment of
Bias Determination for DOE Nuclear Fuels
Bias Determination for DOE Nuclear Fuels
The purpose of this calculation is to establish the relative change in the effective neutron multiplication factor (k-eff) due to the use of MCNP unique identifiers used in the paper, Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF, that are different from the MCNP unique identifiers used in the paper, Analysis of Critical Benchmark Experiments and Critical Limit Calculation for DOE SNF.
Calculation of Isotopic Bias and Uncertainty for BWR SNF
Calculation of Isotopic Bias and Uncertainty for BWR SNF
The objective of Calculation of Isotopic Bias and Uncertainty for BWR SNF is to quantify the computational bias and uncertainty in the multiplication factor (keff) to be used for Boiling Water Reactor (BWR) spent nuclear fuel (SNF) burn-up credit. The scope of this bias and uncertainty determination covers 38 different radiochemical assay (RCA) spent fuel samples from 14 different fuel assemblies that were irradiated in four different BWRs. The irradiated fuel samples evaluated span an enrichment range of 2.53 weight percent U-235 through 3.95 weight percent U-235.
Abstraction of Drift Seepage
Abstraction of Drift Seepage
This model report documents the abstraction of drift seepage, conducted to provide seepage relevant parameters and their probability distributions for use in Total System Performance Assessment for License Application (TSPA-LA). Drift seepage refers to the flow of liquid water into waste emplacement drifts.
Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste 3
Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste 3
The Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel1 and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities.