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Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities

Abstract

The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) demonstrate 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 has been investigating the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses. It is also investigating the use of 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. RESEARCH PROGRESS AND IMPLICATIONS

Authors:
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Publication Date:
Research Org.:
Oak Ridge National Lab., Oak Ridge, TN (US)
Sponsoring Org.:
USDOE Office of Environmental Management (EM) (US)
OSTI Identifier:
828520
Report Number(s):
EMSP-60077-2000
R&D Project: EMSP 60077; TRN: US0404010
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Jun 2000
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 54 ENVIRONMENTAL SCIENCES; CRITICALITY; FISSILE MATERIALS; IMPLEMENTATION; RADIATION PROTECTION; RADIATION TRANSPORT; SAFETY ANALYSIS; SPENT FUELS; WASTE MANAGEMENT; WASTES

Citation Formats

Parks, C V, Rearden, B T, Broadhead, B L, Petrie, L M, DeHart, M D, and Hopper, C M. Development of Nuclear Analysis Capabilities for DOE Waste Management Activities. United States: N. p., 2000. Web. doi:10.2172/828520.
Parks, C V, Rearden, B T, Broadhead, B L, Petrie, L M, DeHart, M D, & Hopper, C M. Development of Nuclear Analysis Capabilities for DOE Waste Management Activities. United States. doi:10.2172/828520.
Parks, C V, Rearden, B T, Broadhead, B L, Petrie, L M, DeHart, M D, and Hopper, C M. Thu . "Development of Nuclear Analysis Capabilities for DOE Waste Management Activities". United States. doi:10.2172/828520. https://www.osti.gov/servlets/purl/828520.
@article{osti_828520,
title = {Development of Nuclear Analysis Capabilities for DOE Waste Management Activities},
author = {Parks, C V and Rearden, B T and Broadhead, B L and Petrie, L M and DeHart, M D and Hopper, C M},
abstractNote = {The objective of this project is to develop and demonstrate prototypical analysis capabilities that can be used by nuclear safety analysis practitioners to: (1) demonstrate 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 has been investigating the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses. It is also investigating the use of 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. RESEARCH PROGRESS AND IMPLICATIONS},
doi = {10.2172/828520},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {6}
}

Technical Report:

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