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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
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
Co-Mingled and Defense-Only Repositories
Co-Mingled and Defense-Only Repositories
At the request of the staff to the Blue Ribbon Commission on America’s Nuclear Future (“BRC”), we have reviewed the following questions:
1. Is there legal authority for DOE or any other entity to undertake to site a repository for “co-mingled” nuclear materials (i.e., civilian and defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW)) at any site other than Yucca Mountain?
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.
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.
ANS Position Statement: Creation of an Independent Entity to Manage U.S. Used Nuclear Fuel
ANS Position Statement: Creation of an Independent Entity to Manage U.S. Used Nuclear Fuel
It is increasingly apparent that the United States will require a large expansion of nuclear power
generation capacity to meet its future baseload electricity needs while reducing greenhouse gas
emissions. As a result, Congress and the Administration must act to update U.S. nuclear fuel
cycle policy to address these realities. This will likely require a multifaceted approach involving
some combination of on-site/centralized dry cask interim storage, nuclear fuel recycling, and
emplacement of high-level wastes in long-term geological storage.
In-Package Chemistry Abstraction
In-Package Chemistry Abstraction
This report was developed in accordance with the requirements in Technical Work Plan for Postclosure Waste Form Modeling (BSC 2005 [DIRS 173246]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as a function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA).
Sequoyah Unit 2 CRC Depletion Calculations
Sequoyah Unit 2 CRC Depletion Calculations
The purpose of this calculation is to document the Sequoyah Unit 2 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.
Nuclear Waste Bill to Implement the Blue Ribbon Commission's Recommendations Section-by-Section Summary of Discussion Draft - April 2013
Nuclear Waste Bill to Implement the Blue Ribbon Commission's Recommendations Section-by-Section Summary of Discussion Draft - April 2013
In General: The Nuclear Waste Administration Act of 2013 includes most of the language of S.3469, the Nuclear Waste Administration Act of 2012. The most significant change in the 2013 bill is the provision linking construction and siting of a consolidated storage facility to progress on a repository. The 2012 Act prohibited storage of any spent nuclear fuel beyond 10,000 metric tons until the Administration concluded a repository consent agreement.
Criticality Evaluation of Intact and Degraded PWR WPs Containing MOX SNF
Criticality Evaluation of Intact and Degraded PWR WPs Containing MOX SNF
The purpose of this calculation is to perform criticality evaluations for mixed oxide spent nuclear fuel (MOX SNF) in 12 and 21 Pressurized Water Reactor (PWR) waste packages (WPs) for both intact and degraded configurations.
The MOX assembly design considered in previous studies on Pu disposition in commercial reactors is based on the Westinghouse (W) 17x17 Vantage 5 assembly (Ref. 7.2). Depletion analyses of four Pu enrichment and burnup (expressed as gigawatt days/metric ton heavy metal; GWd/MTHM) combinations were performed in Reference 7.4. These are:
Spent Nuclear Fuel Management: How centralized interim storage can expand options and reduce costs
Spent Nuclear Fuel Management: How centralized interim storage can expand options and reduce costs
The purpose of this study is to assist decision makers in evaluating the centralized interim
storage option. We explore the economics of centralized interim storage under a wide variety of
circumstances. We look at how a commitment to move forward with centralized interim storage
today could evolve over time. And, we evaluate the costs of reversing a commitment toward
centralized storage if it turns out that such a decision is later considered a mistake. We have not
THE REPORT TO THE PRESIDENT AND THE CONGRESS BY THE SECRETARY OF ENERGY ON THE NEED FOR A SECOND REPOSITORY
THE REPORT TO THE PRESIDENT AND THE CONGRESS BY THE SECRETARY OF ENERGY ON THE NEED FOR A SECOND REPOSITORY
The Nuclear Waste Policy Act of 1982, as amended (NWPA), establishes a process for the siting, construction and operation of one or more national repositories for permanent disposal of the Nation’s spent nuclear fuel (SNF) and high-level radioactive waste (HLW). In 1987, after the Department of Energy (the Department or DOE) had conducted studies of nine potential repository sites located throughout the United States, Congress amended the NWPA and selected the Yucca Mountain site in Nye County, Nevada as the only site for further study for the first national repository.
Dry Transfer Facility Criticality Safety Calculations
Dry Transfer Facility Criticality Safety Calculations
This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the Project Design Criteria (PDC) Document (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in Project Requirements Document (Canori and Leitner 2003 [DIRS 166275], p.
Background Paper on Commingling of Defense and Commercial Waste
Background Paper on Commingling of Defense and Commercial Waste
Since a 1985 decision by President Reagan that a separate permanent repository for disposal of
defense high level waste was not required1, DOE has planned for disposal of all high-level waste
and spent fuel from national defense activities and DOE’s own research activities in a repository
for commercial waste developed under the Nuclear Waste Policy Act (NWPA). The Commission
has heard recommendations from some commenters2 that this decision be revisited, or even
Cladding Degradation Summary for LA
Cladding Degradation Summary for LA
The purpose of this analysis report is to develop the summary cladding degradation abstraction that will be used in the Total System Performance Assessment for the License Application (TSPA-LA). Most civilian commercial nuclear fuel is encased in Zircaloy cladding. The analysis addressed in this report is intended to describe the postulated condition of commercial Zircaloy-clad fuel as a function of postclosure time after it is placed in the repository.
Reactor Record Uncertainty Determination
Reactor Record Uncertainty Determination
The objective of this calculation is to evaluate commercial spent nuclear fuel (CSNF) bumup uncertainty based on pressurized water reactor (PWR) and boiling water reactor (BWR) records kept by each utility. The bumup uncertainties will be used to adjust either the waste package loading curves or the bumup values of assemblies shipped to the repository.
This engineering calculation supports the burnup credit methodology in Reference 1 and is performed in accordance with the AREVAIFANP procedures in References 2 and 3.
3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF
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 degraded mode criticality performance.
The Potential of Using Commercial Duel Purpose Canisters for Direct Disposal
The Potential of Using Commercial Duel 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 the current designs of waste packages and as they relate to
disposability in the repository. Where DPC features appear to compromise future disposability,
those changes that would improve prospective disposability are identified.
CRC Depletion Calculations for Three Mile Island Unit 1
CRC Depletion Calculations for Three Mile Island Unit 1
The purpose of this calculation is to document the Three Mile Island Unit 1 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.
Partnering for Long-Term Management of Radioactive Waste, Evolution and Current Practice in Thirteen Countries
Partnering for Long-Term Management of Radioactive Waste, Evolution and Current Practice in Thirteen Countries
The search for sites for radioactive waste management (RWM) facilities attracts attention from implementers, government bodies, local communities, and the public at large. Facility siting processes, in general, tend to be marred by conflicts, disagreements, and delays.
Blue Ribbon Commission on America’s Nuclear Future Report to the Secretary of Energy
Blue Ribbon Commission on America’s Nuclear Future Report to the Secretary of Energy
This report highlights the findings and conclusions of the Blue Ribbon Commission on America’s Nuclear Future (BRC) and presents recommendations for consideration by the Administration and Congress, as well as interested state, tribal and local governments, other stakeholders, and the public.
CURRENT U.S. DEPARTMENT OF ENERGY NUCLEAR ENERGY RD&D PROGRAMS AND PLANS
CURRENT U.S. DEPARTMENT OF ENERGY NUCLEAR ENERGY RD&D PROGRAMS AND PLANS
This document summarizes DOE’s commercial nuclear energy RD&D program based on a R&D roadmap and on DOE/NE’s budget request for fiscal year 2011. The roadmap is written at a high level and is mostly qualitative in terms of activities, milestones and decisions to be made and does not contain budget information. The fiscal year 2011 budget request contains more specific and detailed information on activities, milestones, decisions, and budgets but only for fiscal year 2011 and the two preceding fiscal years.
Letter to Co‐Chairs and Members of the Joint Select Committee
Letter to Co‐Chairs and Members of the Joint Select Committee
Dear Co‐Chairs and Members of the Joint Select Committee: The Blue Ribbon Commission on America’s Nuclear Future was established by the Secretary of Energy at the direction of the President 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 believe should be reflected in your Committee’s baseline budget projections as you craft a bipartisan plan for reducing the national budget deficit.