Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan
This document presents a test plan developed to assess the fundamental effectiveness of two widely accepted processes for drying spent nuclear fuel: vacuum drying and helium forced-gas drying. The experimental activities planned for Task 5 follow from the “Aluminum Clad Spent Nuclear Fuel Long Term Dry Storage Technical Issues Action Plan.” The objectives are to evaluate the response of the oxide corrosion layer on aluminum clad spent nuclear fuel (ASNF), processed at temperatures above 100°C, to understand and compare the behavior of oxide corrosion layer compositions resulting from a range of credible procedural variations during the transition of ASNF from wet storage to dry storage.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1529905
- Report Number(s):
- INL/EXT-19-54019-Rev.000
- Country of Publication:
- United States
- Language:
- English
Similar Records
Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan
Aluminum Clad Spent Nuclear Fuel Task 1: Oxyhydroxide Layer Behavior and Chemistry Experimental Test Plan
Evaluation of Aluminum-clad Spent Nuclear Fuel during Drying and Dry Storage
Technical Report
·
Wed Aug 21 00:00:00 EDT 2019
·
OSTI ID:1529905
Aluminum Clad Spent Nuclear Fuel Task 1: Oxyhydroxide Layer Behavior and Chemistry Experimental Test Plan
Technical Report
·
Tue Sep 11 00:00:00 EDT 2018
·
OSTI ID:1529905
Evaluation of Aluminum-clad Spent Nuclear Fuel during Drying and Dry Storage
Conference
·
Thu Aug 22 00:00:00 EDT 2019
·
OSTI ID:1529905
+2 more