Experiment Safety Assurance Package for the 40- to 50-GWd/MT Burnup Phase of Mixed Oxide Fuel Irradiation in Small I-Hole Positions in the Advanced Test Reactor Metadata
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Title
- Main Title Experiment Safety Assurance Package for the 40- to 50-GWd/MT Burnup Phase of Mixed Oxide Fuel Irradiation in Small I-Hole Positions in the Advanced Test Reactor
Creator
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Author: Khericha, S. T.Creator Type: Personal
Contributor
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Sponsor: United States. Office of Nuclear Energy, Science, and Technology.Contributor Type: OrganizationContributor Info: USDOE Office of Nuclear Energy, Science and Technology (NE) (United States)
Publisher
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Name: Idaho National Engineering and Environmental LaboratoryPlace of Publication: Idaho Falls, IdahoAdditional Info: Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States)
Date
- Creation: 2002-06-30
Language
- English
Description
- Content Description: This experiment safety assurance package (ESAP) is a revision of the last MOX ESAP issued in February 2001(Khericha 2001). The purpose of this revision is to identify the changes in the loading pattern and to provide a basis to continue irradiation up to {approx}42 GWd/MT burnup (+ 2.5%) as predicted by MCNP (Monte Carlo N-Particle) transport code before the preliminary postirradiation examination (PIE) results for 40 GWd/MT burnup are available. Note that the safety analysis performed for the last ESAP is still applicable and no additional analysis is required (Khericha 2001). In July 2001, it was decided to reconfigure the test assembly using the loading pattern for Phase IV, Part 3, at the end of Phase IV, Part 1, as the loading pattern for Phase IV, Parts 2 and 3. Three capsule assemblies will be irradiated until the highest burnup capsule assembly accumulates: {approx}50 GWd/MT burnup, based on the MCNP code predictions. The last ESAP suggests that at the end of Phase IV, Part 1, we remove the two highest burnup capsule assemblies ({at} {approx}40 GWd/MT burnup) and send them to ORNL for PIE. Then, irradiate the test assembly using the loading pattern for Phase IV, Part 2, until the highest burnup capsule reaches {approx}40 GWd/MT burnup per MCNP-predicted values.
- Physical Description: 1,249 Kilobytes pages
Subject
- Keyword: Safety Analysis
- Keyword: Postirradiation
- Keyword: Irradiation
- Keyword: Mixed Oxide Fuels
- Keyword: Capsule
- Keyword: Ornl
- STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
- STI Subject Categories: 22 General Studies Of Nuclear Reactors
- Keyword: Safety
- Keyword: Test Reactors
- Keyword: Transport Postirradiation
- Keyword: Burnup
Source
- Other Information: PBD: 30 Jun 2002
Collection
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Name: Office of Scientific & Technical Information Technical ReportsCode: OSTI
Institution
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Name: UNT Libraries Government Documents DepartmentCode: UNTGD
Resource Type
- Report
Format
- Text
Identifier
- Report No.: INEEL/EXT-02-00826
- Grant Number: AC07-99ID13727
- DOI: 10.2172/820814
- Office of Scientific & Technical Information Report Number: 820814
- Archival Resource Key: ark:/67531/metadc734024
Note
- Display Note: INIS; OSTI as DE00820814