Modeling Assumptions for the Advanced Test reactor Fresh Fuel Shipping Container

Conference · Sun Sep 13 00:00:00 EDT 2009

OSTI ID:968579

Migliore, Rick J. ^[1]

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1. Areva Federal Services LLC, Tacoma, WA (United States)

The Advanced Test Reactor Fresh Fuel Shipping Container (ATR FFSC) is currently licensed per 10 CFR 71 to transport a fresh fuel element for either the Advanced Test Reactor, the University of Missouri Research Reactor (MURR), or the Massachusetts Institute of Technology Research Reactor (MITR-II). During the licensing process, the Nuclear Regulatory Commission (NRC) raised a number of issues relating to the criticality analysis, namely (1) lack of a tolerance study on the fuel and packaging, (2) moderation conditions during normal conditions of transport (NCT), (3) treatment of minor hydrogenous packaging materials, and (4) treatment of potential fuel damage under hypothetical accident conditions (HAC). These concerns were adequately addressed by modifying the criticality analysis. A tolerance study was added for both the packaging and fuel elements, full-moderation was included in the NCT models, minor hydrogenous packaging materials were included, and fuel element damage was considered for the MURR and MITR-II fuel types.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Areva Federal Services LLC, Tacoma, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 968579
• Report Number(s): INL/CON-09-15971; TRN: US0904715
• Resource Relation: Conference: ANS Nuclear Criticality Safety Division Topical Meeting , Richland, WA (United States), 13-17 Sep 2009
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
CONTAINERS
CRITICALITY
FUEL ELEMENTS
HYPOTHETICAL ACCIDENTS
LICENSING
PACKAGING
RESEARCH REACTORS
SAFETY
SIMULATION
TEST REACTORS
TOLERANCE
TRANSPORT
Nuclear Criticality Safety Program (NCSP)
Advanced Test Reactor
Container Modeling
Nuclear Fuel
Shipping Container