Test plan for long-term, low-temperature oxidation of spent fuel, Series 1
Description
Preliminary studies indicated the need for more spent fuel oxidation data in order to determine the probable behavior of spent fuel in a tuff repository. Long-term, low-temperature testing was recommended in a comprehensive technical approach to: (1) confirm the findings of the short-term thermogravimetric analyses scoping experiments; (2) evaluate the effects of variables such as burnup, atmospheric moisture and fuel type on the oxidation rate; and (3) extend the oxidation data base ot representative repository temperatures and better define the temperature dependence of the operative oxidation mechanisms. This document presents the Series 1 test plan to study, on a large number of samples, the effects of atmospheric moisture and temperature on oxidation rate and phase formation. Tests will run for up to two years, use characterized fragmented, and pulverized fuel samples, cover a temperature range of 1100C to 1750C and be conducted with an atmospheric moisture content rangeing from <-550C to approx. 800C dew point. After testing, the samples will be examined and made available for leaching testing
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A04/MF A01 as DE86014756.
Files
Additional details
Additional titles
- Augmented title (English)
- NNWSI project
Publishing Information
- Imprint Pagination
- 53 p.
- Report number
- HEDL--7560
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18012950
- Subject category
- S36: MATERIALS SCIENCE; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- HIGH TEMPERATURE; HUMIDITY; MEDIUM TEMPERATURE; OXIDATION; PHASE STUDIES; SPENT FUELS; TEMPERATURE DEPENDENCE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES