Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM
Author:
Affiliation:
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
Abstract
Funder
National Science and Technology Major Project
Publisher
Hindawi Limited
Subject
Nuclear Energy and Engineering
Link
http://downloads.hindawi.com/journals/stni/2022/1817191.pdf
Reference15 articles.
1. The Shandong Shidao Bay 200 MW e High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation
2. Research on the fuel loading patterns of the initial core in Chinese pebble-bed reactor HTR-PM
3. Research on detection scheme of pebbles in fuel handling system pipelines in pebble-bed HTGR based on γ-ray measurement
4. The Optimization of Radiation Protection in the Design of the High Temperature Reactor-Pebble-Bed Module
5. Physical Analysis of the Initial Core and Running-In Phase for Pebble-Bed Reactor HTR-PM
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1. Recent Development of Heat Transfer and Fluid Flow of Supercritical CO2 in Tubes: Mechanisms and Applications;Journal of Thermal Science;2024-09-07
2. Effect of heat recovery steam generator on characteristics of combined cycle NPP with gas-cooled reactors;Progress in Nuclear Energy;2023-10
3. A Limited-Scope Probabilistic Risk Assessment Study to Risk-Inform the Design of a Fuel Storage System for Spent Pebble-Filled Dry Casks;Eng;2023-06-08
4. Flow distribution in the air cooler of HTGR passive cavity cooling system;Annals of Nuclear Energy;2023-01
5. Air-Cooler Structure Optimization of HTGR Passive Cavity Cooling System;Springer Proceedings in Physics;2023
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