Published April 23, 2022 | Version v1
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Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM

  • 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.

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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

Optional Information

Copyright
© Author(s)
Contract/Grant/Project number
ZX069
Notes
Record automatically processed
Funding organization
National Science and Technology Major Project