Thermal Release of LiCl Waste Salt from Pyroprocessing
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The decay heat of Cs and Sr contained in a LiCl waste salt, generated from an electrolytic reduction process in pyroprocessing of spent nuclear fuel, has been calculated. The calculation has been carried out under some assumptions that most of the LiCl waste is purified and recycled to main process, and the residual is fabricated to make a waste form. As a result, the decay heat from daughter nuclides such as Ba and Y seems to be maximum 4.6 times higher than that from their parent nuclides such as Cs and Sr. The thermal release from Cs and Sr in the LiCl waste is the maximum around the first one month, so an cooling system operation for some time at the beginning would be suggested to control a rapid increase in the temperature of the LiCl waste salt.
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Radioactive Waste Society
- Journal Volume
- 7
- Journal Issue
- 2
- Series
- 14 refs, 3 figs, 3 tabs
- Journal Page Range
- p. 73-78
- ISSN
- 1738-1894
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42074816
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- AFTER-HEAT; COMPUTER CALCULATIONS; CONTROL; COOLING SYSTEMS; REDUCTION; SPENT FUELS; WASTE FORMS
- Descriptors DEC
- CHEMICAL REACTIONS; ENERGY SOURCES; ENERGY SYSTEMS; FUELS; MATERIALS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; WASTES