Published August 5, 2018
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Moisture Transfer Model and Simulation for Dehumidification of HTGR Core
Creators
- 1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
- 2. Nuclear Power Institute of China, Chengdu 610231, China
Description
A large number of carbon materials are adopted in high-temperature gas-cooled reactor (HTGR). These carbon materials mainly include graphite IG-110 and boron-containing carbon material (BC), both of which are typical porous materials and normally absorb moisture. In order to inhibit the chemical corrosion reaction between core internals materials and moisture, the core needs to be strictly dehumidified before the reactor is put into operation. This paper mainly analyzed the moisture transfer mechanism in these carbon materials. Moisture transfer models were developed, and the dehumidification process of HTR-PM core was simulated. In addition, the influence of working temperature and system pressure on dehumidification was studied as well.
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10.1155_2018_4163914.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2018/4163914;
- Crossref Funder ID
- 10.13039/501100001809;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2018
- Journal Page Range
- 1-8
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BORON; CARBON STEELS; CORROSION; CORROSION PRODUCTS; DEHYDRATION; GRAPHITE; HTGR TYPE REACTORS; HTR REACTOR; HTR-10 REACTOR; HUMIDITY; MOISTURE; POROSITY; POROUS MATERIALS; REACTOR CORES; REACTOR MATERIALS; SIMULATION
- Descriptors DEC
- ALLOYS; CARBON; CARBON ADDITIONS; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MINERALS; MOISTURE; NONMETALS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEMIMETALS; STEELS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- © Author(s)
- Contract/Grant/Project number
- 11302117, 2182023, ZX06901
- Notes
- Record automatically processed
- Funding organization
- National Natural Science Foundation of China, Beijing Municipal Natural Science Foundation, Chinese National S&T Major Project