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Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Author(s)
Broadhead, B. L. ,
DeHart, M. D. ,
Ryman, J. C. ,
Tang, J. S. ,
Parks, C. V.
Publication Date
The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site.
burnup credit spent fuel transport lwr ornl/tm-12742 nuclide used fuel

Monitored Retrievable Storage Facility Conceptual Design Report

Monitored Retrievable Storage Facility Conceptual Design Report

Author(s)
TRW Environmental Safety Systems, Inc.
Publication Date
This conceptual design report presents results of the monitored retrievable storage facility (MRS) conceptual design effort. Six design concepts were investigated for handling and storing spent nuclear fuel assemblies at the MRS and are presented in this report. All six of these design concepts satisfy program requirements and provide safe and efficient methods to handle and store spent nuclear fuel. This conceptual design is an important step towards furthering the civilian radioactive waste management system program.
spent fuel tso.92.0323.0257 mrs radioactive waste waste management used fuel

Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft

Author(s)
Duke Engineering & Services, Inc.
Publication Date
The Design Criteria Policy Document will provide guidance on the types of Design Events, Design Basis Accidents, and Design Criteria for Important To Radiological Safety Systems, Structures, and Components (SSCs) to be assumed during the design of the MRS facility. Definitions of key terms associated with Design Events are also included with this document. Appropriate combinations of Design Events and criteria is identified.
structure analysis spent fuel mol.19970729.0629 mrs radioactive waste radiation protection storage used fuel

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

Author(s)
Parks, C. V. ,
Gauld, I. C. ,
Wagner, J. C. ,
Broadhead, B. L. ,
DeHart, M. D. ,
Ebert, D. D.
Publication Date
The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities. The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).
burnup credit transport cask storage cask criticality safety analysis

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

Author(s)
Hermann, O. W. ,
Bowman, S. M.
Publication Date
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit for the negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark computational methods against spent fuel critical configurations.
burnup credit scale pwr ornl/tm-12294/v3 surry

Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, Rev. 0

Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, Rev. 0

Author(s)
Office of Civilian Radioactive Waste Management
Publication Date

The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system as developed under the Nuclear Waste Policy Act of 1982. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document.

high level waste spent fuel radioactive waste used fuel

Characteristics of Potential Repository Wastes

Characteristics of Potential Repository Wastes

Author(s)
Oak Ridge National Laboratory
Publication Date

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.

high level waste spent fuel repository doe/rw-0184-r1 radioactive waste used fuel

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

Author(s)
Gauld, I. C. ,
Sanders, C. E.
Publication Date

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

burnup credit criticality analysis nureg/cr-6798 ornl/tm-2001/259 spent fuel composition

CSNF Loading Curve Sensitivity Analysis

CSNF Loading Curve Sensitivity Analysis

Author(s)
Sandia National Laboratories
Publication Date

The purpose of this scientific analysis report, CSNF Loading Curve Sensitivity Analysis, is to establish the required minimum burnup as a function of initial enrichment for both pressurized water reactor (PWR) and boiling water reactor (BWR) commercial spent nuclear fuel (CSNF) that would allow permanent disposal of these waste forms in the geologic repository at Yucca Mountain. The relationship between the required minimum burnup and fuel assembly initial enrichment forms a loading curve.

burnup credit transportation, aging and disposal (tad) yucca mountain commercial spent nuclear fuel criticality analysis repository loading curves

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Author(s)
Spent Fuel Project Office, NRC

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1

burnup credit pwr spent fuel transport cask storage cask criticality safety analysis isg-8 interim staff guidance used fuel

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

Author(s)
Okuno, Hiroshi ,
Naito, Yoshitaka ,
Suyama, Kenya
Publication Date

The report describes the final results of the Phase IIIB Benchmark conducted by the
Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy
Agency (NEA) of the Organization for Economic Cooperation and Development (OECD).
The Benchmark was intended to compare the predictability of current computer code and
data library combinations for the atomic number densities of an irradiated BWR fuel
assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM

burnup credit criticality analysis nea jaeri nea/nsc/doc(2002)/2 composition calculations
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