Research on the high temperature resistant performance of concrete material for dry spent fuel storage
Creators
- 1. Jiangsu China Nuclear Huaxing Specialized Project Co., Ltd., Nanjing, Jiangsu (China)
Description
The dry spent fuel storage is widely applied in the construction of spent fuel storage facilities for its advantages, such as favorable protection of spent fuel components, low radiation dose, little cost for operation and maintenance, reliable safety, few radioactive waste, easy to decommission, etc. Concrete, an excellent radiation shielding material, is often used to manufacture dry storage shielding containers with its benefits, such as economical cost, accessible raw material, easy manufacturing technology and equipment. However, the effect of long-term decay heat to concrete performance during the storage is impossible to ignore. Based on the high temperature resistance requirements of concrete material for dry spent fuel storage, this paper studies the selection of thermal expansion coefficient of concrete raw materials, concrete mix design and puts forward the monitoring requirements for follow-up concrete performance tests to monitor the performance variation of concrete material in performance tests at elevated temperature of 180 ℃, 300 ℃ and 800 ℃ in order to research one high temperature resistant concrete material for dry spent fuel storage system of nuclear power plant. (authors)
Additional details
Publishing Information
- Publisher
- China Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 978-7-5022-8776-4
- Imprint Title
- Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.8--Nuclear Techniques in Industry sub-volume
- Imprint Pagination
- 241 p.
- Journal Page Range
- p. 183-187
Conference
- Title
- 2017 academic annual meeting of China Nuclear Society
- Dates
- 16-18 Oct 2017
- Place
- Weihai (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 53102437
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; CONCRETES; DRY STORAGE; MONITORING; NUCLEAR POWER PLANTS; PERFORMANCE; RADIOACTIVE WASTES; SPENT FUEL STORAGE; SPENT FUELS; STORAGE FACILITIES; THERMAL EXPANSION
- Descriptors DEC
- BUILDING MATERIALS; ENERGY SOURCES; EXPANSION; FUELS; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER PLANTS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; STORAGE; THERMAL POWER PLANTS; WASTES
Optional Information
- Notes
- 6 figs., 1 tab., 16 refs.