Development of Nuclear Analysis Capabilities for DOE Waste Management Activities

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Description

The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) provide a more thorough understanding of the underlying physics phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations related to the handling, storage, transportation, and disposal of fissile material and DOE spent fuel. To address these problems, this project will investigate the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses, as well as within a new deterministic code that allows for ... continued below

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Creation Information

Parks, Cecil V. June 1, 1999.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Oak Ridge National Laboratory
    Publisher Info: Oak Ridge National Lab., Oak Ridge, TN (United States)
    Place of Publication: Oak Ridge, Tennessee

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Description

The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) provide a more thorough understanding of the underlying physics phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations related to the handling, storage, transportation, and disposal of fissile material and DOE spent fuel. To address these problems, this project will investigate the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses, as well as within a new deterministic code that allows for specification of arbitrary grids to accurately model geometric details required in a criticality safety analysis. This capability can facilitate improved estimations of the required subcritical margin and potentially enable the use of a broader range of experiments in the validation process. The new arbitrary-grid radiation transport code will also enable detailed geometric modeling valuable for improved accuracy in application to a myriad of other problems related to waste characterization. Application to these problems will also be explored.

Physical Description

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  • Other Information: PBD: 1 Jun 1999

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  • Report No.: EMSP-60077--1999
  • DOI: 10.2172/828519 | External Link
  • Office of Scientific & Technical Information Report Number: 828519
  • Archival Resource Key: ark:/67531/metadc787755

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • June 1, 1999

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

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  • April 21, 2016, 1:15 p.m.

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Parks, Cecil V. Development of Nuclear Analysis Capabilities for DOE Waste Management Activities, report, June 1, 1999; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc787755/: accessed October 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.