Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM

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 fue...

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Main Authors: Bin Wu, Jinhua Wang, Yue Li, Haitao Wang, Tao Ma
Format: Article
Language:English
Published: Wiley 2022-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2022/1817191
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author Bin Wu
Jinhua Wang
Yue Li
Haitao Wang
Tao Ma
author_facet Bin Wu
Jinhua Wang
Yue Li
Haitao Wang
Tao Ma
author_sort Bin Wu
collection DOAJ
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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institution Kabale University
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language English
publishDate 2022-01-01
publisher Wiley
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series Science and Technology of Nuclear Installations
spelling doaj-art-1e8053e19cbe4855bff920696c5b86cb2025-02-03T06:05:11ZengWileyScience and Technology of Nuclear Installations1687-60832022-01-01202210.1155/2022/1817191Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PMBin Wu0Jinhua Wang1Yue Li2Haitao Wang3Tao Ma4Institute of Nuclear and New Energy TechnologyInstitute of Nuclear and New Energy TechnologyInstitute of Nuclear and New Energy TechnologyInstitute of Nuclear and New Energy TechnologyInstitute of Nuclear and New Energy TechnologyThe 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.http://dx.doi.org/10.1155/2022/1817191
spellingShingle Bin Wu
Jinhua Wang
Yue Li
Haitao Wang
Tao Ma
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
Science and Technology of Nuclear Installations
title Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
title_full Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
title_fullStr Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
title_full_unstemmed Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
title_short Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
title_sort design experiment and commissioning of the spent fuel conveying and loading system of htr pm
url http://dx.doi.org/10.1155/2022/1817191
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AT haitaowang designexperimentandcommissioningofthespentfuelconveyingandloadingsystemofhtrpm
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