Aluminum-clad Spent Nuclear Fuel Engineering Scale Drying Experiment Design
Creators
- 1. University of South Carolina, Columbia, SC (United States)
Description
The purpose of this document is to provide the technical specifications for the Engineering Scale Design for the drying tests of aluminum-clad spent nuclear fuel (ASNF). The engineering scale design is to accommodate both forced helium drying (FHD) as well as vacuum drying. The experiments will employ mock ASNF assemblies with a limited number of chemically treated aluminum plates to simulate the aluminum hydroxides found on ASNF. The goal here is to understand the transformation that may occur in plates including the loss of chemisorbed water and changes in morphology. Physiosorbed and bulk water found in experiments will be dried in the process and the effect on drying operations noted. Decay heat will be simulated in one assembly using a custom designed resistance heating element. A typical radial arrangement of assemblies will be employed using a modified Type 1A Basket design. For the chamber/canister, a single assembly layer with full radial dimension will be employed. Modifications to the standard canister design and configuration include the addition of a siphon tube to enable recirculation of hot gas for forced helium drying. A ring of ports/flanges are added near the top of the chamber to accommodate the feedthroughs for instrumentation and power needed for the experiment and data collection. Four viewports are added to the main section of the chamber with two in line with one of the fuel assembly and siphon tube. The other two viewports are on the opposite side of the chamber. The purpose here is to provide the option of thermal imaging in addition to the nearly four dozen thermocouples available inside the chamber. Modeling of the chamber, basket, and mock ASNF assemblies was conducted to estimate temperature distributions throughout the chamber during forced helium drying and over the anticipated drying period. This modeling was used as input to decisions on the Engineering Scale Design. Work on modeling continues in the period during setup and testing to develop preliminary drying models. Analysis of experimental results will later be used to validate these and subsequent models.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1572393; https://www.osti.gov/biblio/1572393; 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
- 39 p.
- Report number
- INL-EXT--19-56017-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 54044280
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT; ALUMINIUM; CHEMISORPTION; COMPUTERIZED SIMULATION; CONTAINERS; CORROSION; DESIGN; DRY STORAGE; ELECTRIC HEATING; EXPERIMENT DESIGN; FUEL ASSEMBLIES; HELIUM; MORPHOLOGY; NUCLEAR ENGINEERING; PLATES; SPECIFICATIONS; SPENT FUELS; TEMPERATURE DISTRIBUTION; TESTING; THERMOCOUPLES
- Descriptors DEC
- CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; ENGINEERING; FLUIDS; FUELS; GASES; HEATING; MATERIALS; MEASURING INSTRUMENTS; METALS; NONMETALS; NUCLEAR FUELS; RARE GASES; REACTOR MATERIALS; SEPARATION PROCESSES; SIMULATION; SORPTION; STORAGE
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Environmental Management - EM (United States)
- Secondary number(s)
- OSTIID--1572393