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Title: Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan

Abstract

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.”[1] 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.

Authors:
ORCiD logo [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Environmental Management (EM)
OSTI Identifier:
1529905
Report Number(s):
INL/EXT-19-54019-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 - MATERIALS SCIENCE; drying; spent nuclear fuel; adsorbed water

Citation Formats

Smith, Rebecca E. Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan. United States: N. p., 2019. Web. doi:10.2172/1529905.
Smith, Rebecca E. Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan. United States. doi:10.2172/1529905.
Smith, Rebecca E. Thu . "Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan". United States. doi:10.2172/1529905. https://www.osti.gov/servlets/purl/1529905.
@article{osti_1529905,
title = {Aluminum Clad Spent Nuclear Fuel Task 5: Oxide Layer Response to Drying Experiment Test Plan},
author = {Smith, Rebecca E},
abstractNote = {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.”[1] 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.},
doi = {10.2172/1529905},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {5}
}

Technical Report:

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