Properties of pellet cement-glass package
Creators
- 1. Hitachi Ltd., Ibaraki (Japan). Energy Research Lab.
- 2. Hitachi Works, 3-1-1 Saiwaicho Hitachi 317 (Japan)
Description
A new solidification technique using cement-glass, which is a mixture of sodium silicate, silicon phosphate and cement is presented. It was developed to solidify sodium sulfate or sodium borate pellets generated from nuclear power plants. The optimum composition of Na2O, SiO2 and P2O5 · 2SiO2, main components of cement-glass, was defined to be 1:2:1 by studying the solidification mechanism. Polymer impregnated concrete was selected as material of the container to increase the stability. Since the package consists of inorganic materials, it shows good fire resistance and radiation stability. Added cement absorbs free water which is generated by the solidification reaction of Na2O, SiO2 and P2O5 · 2SiO2. Then, soluble pellets can be solidified without dissolving some part of them. Since polymer impregnated concrete has little porosity, the pellet cement-glass package which uses a polymer impregnated concrete container shows very low leachability
Additional details
Publishing Information
- Publisher
- Arizona Board of Regents.
- Imprint Place
- Tucson, AZ (USA)
- Imprint Title
- Waste processing, transportation, storage and disposal, technical programs and public education
- Imprint Pagination
- 844 p.
- Journal Page Range
- p. 417-423.
Conference
- Title
- 15th international waste management symposium conference.
- Acronym
- Waste management '89
- Dates
- 26 Feb - 2 Mar 1989.
- Place
- Tucson, AZ (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22010234
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CEMENTS; CONCRETES; CONTAINERS; GLASS; LEACHING; NUCLEAR POWER PLANTS; POLYMERS; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; SOLIDIFICATION
- Descriptors DEC
- BUILDING MATERIALS; DISSOLUTION; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; RADIOACTIVE MATERIALS; SEPARATION PROCESSES; STORAGE; THERMAL POWER PLANTS; WASTE MANAGEMENT; WASTE STORAGE; WASTES
Optional Information
- Secondary number(s)
- CONF-890207--.