A Study on Wasteform Properties of Spent Salt Treated with Zeolite and SAP
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
This paper investigated the characteristics of wasteform containing a spent zeolite used as a separating agent of FPs for recycling LiCl waste which would be generated from pyrochemical process of spent PWR fuel. In this study, a conventional borosilicate and Ca-rich glass were used as a consolidating agent for spent zeolite and it's mixing ratio was changed in the range, 25-35 wt% . The leach rates of Cs and Sr had about 0.1 - 0.01 g/m2day and 0.001 - 0.0001 g/m2day, respectively. The leach resistance of Cs increased with amount of SAP and it showed about 10 times higher in the Ca-rich glass wasteform than in the conventional borosilicate glass wasteform. The compressive strength of wasteform was affected with the amount of glass. Thermal expansion rate of containing 30 wt% glass has relatively lower than others. Also, the melting temperature was little changed in given mixing ratio of glass.
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Radioactive Waste Society
- Journal Volume
- 8
- Journal Issue
- 2
- Series
- 5 refs, 5 figs, 3 tabs
- Journal Page Range
- p. 99-105
- ISSN
- 1738-1894
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45012293
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BOROSILICATE GLASS; LEACHING; LITHIUM CHLORIDES; MELTING; PWR TYPE REACTORS; SPENT FUELS; THERMAL EXPANSION; WASTE FORMS; ZEOLITES
- Descriptors DEC
- ALKALI METAL COMPOUNDS; CHLORIDES; CHLORINE COMPOUNDS; DISSOLUTION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPANSION; FUELS; GLASS; HALIDES; HALOGEN COMPOUNDS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; LITHIUM COMPOUNDS; LITHIUM HALIDES; MATERIALS; MINERALS; NUCLEAR FUELS; PHASE TRANSFORMATIONS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SILICATE MINERALS; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS