Aluminum Clad Spent Nuclear Fuel Task 3: Sealed and Vented Systems Episodic Breathing and Gas Generation Modeling Plan
Creators
- 1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Description
This document presents the test plan for Task 3 of the Aluminum Clad Spent Nuclear Fuel Long Term Dry Storage Technical Issues Action Plan, which covers modeling and predictions of the generations of corrosive gases within both sealed and vented, subject to episodic breathing, storage systems. This includes aluminum clad spent nuclear fuel (ASNF) that is currently or may in the future be held in dry storage for an extended period. The overall objectives of the Task 3 modeling plan are to: 1. Comprehensively model the combined effects of episodic breathing in vented storage systems/canisters using INL INTEC CPP-603 facility as an example. Both bulk gas phase radiolysis reactions and aluminum cladding surface gas generation reactions will be included into a 3-dimensional computational fluid dynamics (CFD) model to model and predict long-term evolutions of the temperature and concentrations of corrosive gases within unsealed canisters subjected to episodic breathing. 2. Comprehensively model sealed and inert canister storage system using DOE standard canister as an example. 3. Closely integrate with Task 1 and Task 2 for identification of main gas-generation reactions and kinetics and provide simulation results back to Task 1 and 2 to further refine experimental designs. This test plan lays out the technical activities that will be performed to achieve the test objectives described above. Simulations will be performed using the Idaho National Laboratory super computer Falcon.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1469388; https://www.osti.gov/biblio/1469388; 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
- 19 p.
- Report number
- INL-EXT--18-45860-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 51097959
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALUMINIUM; CLADDING; CONTAINERS; DRY STORAGE; FLUID MECHANICS; GASES; IDAHO NATIONAL LABORATORY; SPENT FUELS
- Descriptors DEC
- DEPOSITION; ELEMENTS; ENERGY SOURCES; FLUIDS; FUELS; MATERIALS; MECHANICS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; REACTOR MATERIALS; STORAGE; SURFACE COATING; US DOE; US ORGANIZATIONS
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Environmental Management - EM (United States)
- Secondary number(s)
- OSTIID--1469388