{"title":"Verification of the ability of safe activation of the isolated DHR loop of the ALLEGRO reactor in the event of an accident with complete loss of power","authors":"Pavel Zácha, Václav Železný","doi":"10.1016/j.net.2025.103734","DOIUrl":null,"url":null,"abstract":"<div><div>The development of the ALLEGRO gas-cooled demonstration reactor dates back to the early days of Generation 4 reactors. A more detailed conceptual design is currently being developed, which includes thermohydraulic studies of the reactor's safety features. One of the key components is the emergency residual heat removal system provided by the Decay Heat Removal loop.</div><div>The proper operation of the DHR loop in a total loss of supply accident is strongly dependent on the initial phase of the accident, when helium stagnating throughout the loop volume creates a barrier to the start of its natural circulation in the loop.</div><div>This paper analyze in detail the 3D behavior of the isolated DHR loop both during the normal reactor operation and the operability of the system during the defined accident conditions. The results of the study confirm that the DHR system is designed to be able to safely start the reactor cooling process using natural circulation upon its activation and subsequently cool the hot helium continuously using the DHR exchanger.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103734"},"PeriodicalIF":2.6000,"publicationDate":"2025-06-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S173857332500302X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The development of the ALLEGRO gas-cooled demonstration reactor dates back to the early days of Generation 4 reactors. A more detailed conceptual design is currently being developed, which includes thermohydraulic studies of the reactor's safety features. One of the key components is the emergency residual heat removal system provided by the Decay Heat Removal loop.
The proper operation of the DHR loop in a total loss of supply accident is strongly dependent on the initial phase of the accident, when helium stagnating throughout the loop volume creates a barrier to the start of its natural circulation in the loop.
This paper analyze in detail the 3D behavior of the isolated DHR loop both during the normal reactor operation and the operability of the system during the defined accident conditions. The results of the study confirm that the DHR system is designed to be able to safely start the reactor cooling process using natural circulation upon its activation and subsequently cool the hot helium continuously using the DHR exchanger.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development