Total System Model Version 6.0 Dose Estimating Routines Design and Bases

This manual discusses the routines to estimate radiological doses from normal operations used in Version 6.0 of the Total System Model (TSM) as described in the TSM User Manual prepared for the U.S. Department of Energy (DOE) by Bechtel SAIC Company (BSC) (BSC 2007a). The TSM estimates doses during the simulation of the Civilian Radioactive Waste Management System (CRWMS) mission. The TSM is not intended to provide a robust dose evaluation tool and should only be used for relative comparisons of scenarios to general understand if doses are

Validation Issues for Depletion and Criticality Analysis in Burnup Credit

This paper reviews validation issues associated with implementation of burnup credit in transport, dry storage, and disposal. The issues discussed are ones that have been identified by one or more constituents of the United States technical community (national laboratories, licensees, and regulators) that have been exploring the use of burnup credit. There is not necessarily agreement on the importance of the various issues, which sometimes is what creates the issue. The broad issues relate to the paucity of available experimental data

Phenomena and Parameters Important to Burnup Credit

Since the mid-1980s, a significant number of studies have been directed at understanding the phenomena and parameters important to implementation of burnup credit in out-of-reactor applications involving pressurizedwater- reactor (PWR) spent fuel. The efforts directed at burnup credit involving boiling-water-reactor (BWR) spent fuel have been more limited. This paper reviews the knowledge and experience gained from work performed in the United States and other countries in the study of burnup credit. Relevant physics and analysis

Temperature Effects on Reactivity of Commercial Reactor Criticals

Temperature Effects on Reactivity of Commercial Reactor Criticals

Overview of the Burnup Credit Activities at OECD/NEA/NSC

Value Rankings of Selected Critical Experiments for Burnup Credit Validations

The Effect of Half-Life and Branching Fraction Uncertainties on the Effective Neutron Multiplication Factor

Dry Cask Storage and Transportation Burnup Credit

NRC Burnup Credit Research Program

The Nuclear Energy Research Initiative Burnup Credit Critical Experiment

Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks

IAEA TCM 2000: An International Meeting on Burnup Credit Applications

Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel

This report has been prepared to review relevant background information and provide technical discussion that will help initiate a PIRT (Phenomena Identification and Ranking Tables) process for use of burnup credit in light-water reactor (LWR) spent fuel storage and transport cask applications. The PIRT process will be used by the NRC Office of Nuclear Regulatory Research to help prioritize and guide a coordinated program of research and as a means to obtain input/feedback from industry and other interested parties.

Safety Evaluation Report for Disposal Criticality Analysis Methodology Topical Report, Revision 0

In January 1999, the U.S. Department of Energy (DOE)/Office of Civilian Radioactive Waste Management (OCRWM) submitted the Disposal Criticality Analysis Methodology Topical Report, Revision 0 (TR) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. The TR presents an overall approach for consideration of postclosure disposal criticality of commercial and defense high-level waste to be placed at the proposed Yucca Mountain site. During the course of the review and interactions

Applicability of CRC Benchmark Experiments for Burnup Credit Validation

Disposal Criticality Analysis Methodology Topical Report

The fundamental objective of this topical report is to present the planned risk-informed disposal criticality analysis methodology to the NRC to seek acceptance that the principles of the methodology and the planned approach to validating the methodology are sound. The design parameters and environmental assumptions within which the waste forms will reside are currently not fully established and will vary with the detailed waste package design, engineered barrier design, repository design, and repository layout.

Axial Burnup Profile Database for Pressurized Water Reactors

The data were obtained directly from utilities whose reactors represent the range of commercial PWR fuel lattices. The work was performed by Yankee Atomic Electric for Sandia National Laboratory. All axial burnup profiles were calculated from 3-D depletion analyses of the core configuration. The organizations and utilities providing axial burnup profiles for the database used different model codes for the 3D-depletion calculations. The model codes used were: SIMULATE-3, NEMO, ANC, and PRESTO-II. Cross-section inputs describing the assemblies are derived from assembly lattice calculations.

Regulations for the Safe Transport of Radioactive Material - 2005 Edition

101. These Regulations establish standards of safety which provide an acceptable level of control of the radiation, criticality and thermal hazards to persons, property and the environment that are associated with the transport of radioactive material. These Regulations utilize the principles set forth in both the “Radiation Protection and the Safety of Radiation Sources”, Safety Series No. 120 [1] and the “International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources”, Safety

ANSI/ANS-8.27-2008: Burnup Credit for LWR Fuel

This standard provides criteria for accounting for reactivity effects of fuel irradiation and radioactive decay in criticality safety control of storage, transportation, and disposal of commercial LWR UO2 fuel assemblies. This standard assumes the fuel and any fixed burnable absorbers are contained in an intact assembly. Additional considerations could be necessary for fuel assemblies that have been disassembled, consolidated, damaged, or reconfigured in any manner.

Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask

The Interim Staff Guidance on burnup credit (ISG-8) for spent fuel in storage and transportation casks, issued by the Nuclear Regulatory Commission’s Spent Fuel Project Office, recommends a burnup measurement for each assembly to confirm the reactor record and compliance with the assembly burnup value used for loading acceptance. This recommendation is intended to prevent unauthorized loading (misloading) of assemblies due to inaccuracies in reactor burnup records and/or improper assembly identification, thereby ensuring that the appropriate subcritical margin is maintained.

Full Burnup Credit in Transport and Storage Casks--Benefits and Implementation

Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D

Updated Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-Capacity Cask Designs

Current Status and Potential Benefits of Burnup Credit for Spent Fuel Transportation