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.

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

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

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.

The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.

The purpose of this document is to present the methodology to be used for development of the Subcritical Limit (SL) for post closure conditions for the Yucca Mountain repository. The SL is a value based on a set of benchmark criticality multiplier, keff> results that are outputs of the MCNP calculation method. This SL accounts for calculational biases and associated uncertainties resulting from the use of MCNP as the method of assessing kerr·

The 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), U.S. Department of Energy (DOE) spent nuclear
fuel (DOE SNF), and defense high-level (radioactive) waste (HLW). The TSM uses a TSM
Preprocessor (TSMPP) to generate the cask loads and target dates for shipments from waste
sites. The TSM then tracks these wastes from pickup at the waste sites until repository

The purpose of the material degradation and release (MDR) model is to predict the fate of the waste package materials, specifically the retention or mobilization of the radionuclides and the neutron-absorbing material as a function of time after the breach of a waste package during the 10,000 years after repository closure. The output of this model is used directly to assess the potential for a criticality event inside the waste package due to the retention of the radionuclides combined with a loss of the neutron-absorbing material.

This validation report supports the issuance of the Total System Model (TSM) Version 6.0 (Bechtel SAIC, LLC (BSC) 2007a) that is described in the TSM User Manual (UM) (BSC 2007b) and the TSM Pre-Processor (TSMPP) UM (BSC 2007c), and other supporting documentation in References BSC 2007d, BSC 2007e, 2007f, and 2007g. This report assumes the reader has detailed, working knowledge of the TSM functions and Civilian Radioactive Waste Management System (CRWMS) operations.

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.

Japan’s spent fuel management and fuel cycle programs are now at a critical stage. Its first commercial-scale reprocessing plant, at Rokkasho Village, will soon start full-scale operation.

The "Summary Report of Commercial Reactor Criticality Data for LaSalle Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the LaSalle Unit 1 (LS 1) reactor.

The Total System Model Preprocessor (TSMPP) is a part of the Total System Model (TSM),
which is a PC-based simulator that is a decision aid to achieve overall Office of Civilian
Radioactive Waste Management (OCRWM) disposal objectives. The TSM is identified as Level
3, i.e., not Important To Safety (ITS) and not Important To Waste Isolation (ITWI), software in
the Bechtel SAIC Company, LLC (BSC) Controlled Software Report.
The TSMPP combines information about existing conditions, such as waste inventory estimates

The Civilian Radioactive Waste Management System (CRWMS) Total System Model (TSM), a
Level 3 software, 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), Naval SNF, and high-level (radioactive) waste (HLW). The TSM simulates the actions for
Waste Acceptance (WA) from discharge to emplacement.

Spent Fuel Project Office Interim Staff Guidance - 8

The attached documents are an extensive list of references relevant to burnup credit criticality analysis. Some of the references may be available within the CURIE document collection.

The objective of these calculations is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) Three Mile Island- Unit 2 (TMI-2) spent nuclear fuel (SNF) in canisters. This analysis evaluates codisposal in a 5-Defense High-Level Waste (5-DHLW/DOE SNF) Long Waste Package (Civilian Radioactive Waste Management System Management and Operating Contractor [CRWMS M&O] 2000b, Attachment V), which is to be placed in a potential monitored geologic repository (MGR).

The Disposal Subcommittee of the Blue Ribbon Commission on America’s Nuclear Future (BRC) addressed a wide-ranging set of issues, all bearing directly on the central question: “How can the United States go about establishing one or more disposal sites for high-level nuclear wastes in a manner and within a timeframe that is technically, socially, economically, and politically acceptable?”

The purpose of this analysis is to identify, extract, and reformat weather (meteorological) data that is appropriate for use as input to an infiltration model, within the Yucca Mountain region. The analysis uses relevant meteorological data (e.g., precipitation and temperature) from source stations, and reformats or converts the data into a form suitable for the generation of meteorological conditions for a 10,000-year future climate in the Yucca Mountain region.

The purpose of this calculation is to apply the process described in the Preclosure Criticality Analysis Process Report (Ref. 2.2.12) to establish the bias for keff calculations performed for commercial nuclear fuels using the MCNP code system. This bias will be used in criticality safety analyses as part of the basis for establishing the upper subcritical limit (USL). This calculation also defines the range of applicability (ROA) for which the bias may be used directly without need to consider additional penalties on the USL.

NRC/NEI, January 24, 2014 Public Meeting Presentations

This evaluation investigates the potential benefits of separating the transuranic elements from spent reactor fuel before it is disposed of in geologic repositories. It addresses the question: Would the benefits to radioactive waste disposal justify both processing the spent fuel and deploying liquid metal reactors (LMRs) to transmute the separated transuranics?

http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=NP-7…

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013