Published 2024 | Version v1
Conference paper Open

Design and Analysis of Separate Heat Pipe-based Passive Residual Heat Removal System for HTR-PM

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University Nengke Building, Qinghuayuan Street, Haidian District, Beijing, 100084, China

Description

The high-temperature gas-cooled reactor pebble-bed module (HTR-PM) is a promising advanced nuclear reactor. The passive residual heat removal system is an indispensable safety system guaranteeing the inherent safety of HTR-PM. This study presents a novel design of a separate heat pipe passive residual heat removal system for HTR-PM. The effects of the inlet air temperature, condensation area, air cooling tower height, and height difference between the evaporator and the condenser are systematically investigated. The results demonstrate that the system can effectively handle maximum residual heat removal capacity under accident conditions. Additionally, the study explores the feasibility of condenser miniaturization, revealing that a 70% reduction in size is achievable. The steady-state operation is also calculated based on the optimal design scheme. The outcome indicates that it is possible and advantageous to miniaturize the condenser to prepare and operate the separate heat pipe-based passive residual heat removal system. These findings present new opportunities for miniaturization and mobilization of the passive residual heat removal system for the high-temperature gas-cooled reactor. Further experiments should focus on implementing this strategy on small-scale separate heat pipe heat removal systems. (authors)

Files

64.pdf

Files (515.7 kB)

Name Size Download all
md5:4adafce5aae44ebee593cfca872a93c2
515.7 kB Preview Download
Part of:
The 11th International Topical Meeting on High Temperature Reactor Technology

Additional details

Publishing Information

Imprint Pagination
10 p.

Conference

Title
The 11th International Topical Meeting on High Temperature Reactor Technology
Acronym
HTR 2024
Dates
14-18 October, 2024
Place
Beijing, China
Website
http://htr2024.thutech.cn/

INIS

Country of Publication
China
Country of Input or Organization
International Atomic Energy Agency (IAEA)
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT REMOVAL; AIR; COOLING; COOLING SYSTEMS; DESIGN; FEASIBILITY STUDIES; HEAT EXCHANGERS; HEAT PIPES; HEIGHT; HTGR TYPE REACTORS; HTR-10 REACTOR; OPERATION; RHR SYSTEMS; SAFETY; STEADY-STATE CONDITIONS; STEAM CONDENSERS

Optional Information

Notes
21 refs., 13 figs., 2 tabs.