UO2 HALEU Transportation Package Evaluation and Recommendations
Creators
- 1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- 2. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- 3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Description
This M3FT-19IN030205042 milestone report presents the current status on investigations related to the development of HALEU transportation capabilities in the U.S. The report initially reviews potential short-term HALEU production options and describes an expected HALEU composition. It then discusses the regulatory bases for HALEU transportation and identifies two compliant packaging designs: (1) the TN Americas TN-LC and (2) the NAC International OPTIMUS™-L. To modify these designs for HALEU transportation, an inner canister concept, and modular metal and foam basket concepts were developed, and this is described in the report. The expected activity, criticality tendency, radiation level, and decay heat of the package content are evaluated considering the specific system characteristics. Based on the results of the investigations, the research team consisting of INL, PNNL, and ORNL staff concluded that, given the anticipated source material composition, the OPTIMUS™-L, or a comparable design, is the preferred candidate. This is due to its larger HALEU payload per LWT, lighter weight, and simpler handling procedures compared to the TN-LC. Thus, ongoing research efforts for the scope of this project will focus on more thorough evaluations of the OPTIMUS™-L packaging for HALEU transportation. A tentative timeline is presented for the remaining work that is planned for FY 2020. The goal is the development of F&Rs that provide guidance to a potential HALEU transportation package vendor on critical specifications by August 2020.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1578279; https://www.osti.gov/biblio/1578279; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo periodAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- 80 p.
- Report number
- INL-EXT--19-56333-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 54044282
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT; CONTAINERS; CRITICALITY; FISSILE MATERIALS; FOAMS; FUEL CYCLE; METALS; NUCLEAR FUELS; PACKAGING; REACTOR DESIGN; RECOMMENDATIONS; SPECIFICATIONS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COLLOIDS; DESIGN; DISPERSIONS; ELEMENTS; ENERGY SOURCES; FISSIONABLE MATERIALS; FUELS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; REACTOR LIFE CYCLE; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1578279