Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
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
Description
The Chinese high-temperature gas-cooled reactor pebble-bed module, HTR-PM, began fuel loading in August 2021. The reactor refuels continuously, while the spent fuel is discharged from the core. The spent fuel conveying and loading system was designed to convey the spent fuel pebbles to the spent fuel building and load them into dry canisters for on-site interim storage. This study describes the operating principles of the main functions and introduces the experiments and commissioning tests of the system. Functional tests were carried out to indicate the items of mechanical and electrical equipment are functioning in accordance with the designed requirements. Experience learned from commissioning activities was also presented as feedback for future operation and design improvement.
Files
10.1155_2022_1817191.pdf
Files
(1.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:10769d4a47c0309ec630e66e78ecef27
|
1.6 MB | Preview Download |
System files
(27.2 kB)
| Name | Size | Download all |
|---|
Additional details
Identifiers
- DOI
- 10.1155/2022/1817191;
- Crossref Funder ID
- 10.13039/501100018537;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2022
- 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; S42: ENGINEERING;
- Descriptors DEI
- CASKS; CHINA; CLOSED FUEL CYCLE; COMMISSIONING; DESIGN; DRY STORAGE; ELECTRICAL EQUIPMENT; FEEDBACK; FUEL RACKS; HTGR TYPE REACTORS; HTR-10 REACTOR; PEBBLE BED REACTORS; REACTOR CORES; SPENT FUEL STORAGE; SPENT FUELS; WASTE STORAGE
- Descriptors DEC
- ASIA; CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FUEL CYCLE; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; MANAGEMENT; MATERIALS; MECHANICAL STRUCTURES; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; STORAGE; SUPPORTS; TEST FACILITIES; TEST REACTORS; WASTE MANAGEMENT
Optional Information
- Copyright
- © Author(s)
- Contract/Grant/Project number
- ZX069
- Notes
- Record automatically processed
- Funding organization
- National Science and Technology Major Project