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
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F25%3A00385577" target="_blank" >RIV/68407700:21220/25:00385577 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.net.2025.103734" target="_blank" >https://doi.org/10.1016/j.net.2025.103734</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.net.2025.103734" target="_blank" >10.1016/j.net.2025.103734</a>
Alternative languages
Result language
angličtina
Original language name
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
Original language description
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.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20303 - Thermodynamics
Result continuities
Project
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Continuities
R - Projekt Ramcoveho programu EK
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Technology
ISSN
1738-5733
e-ISSN
2234-358X
Volume of the periodical
57
Issue of the periodical within the volume
11
Country of publishing house
KR - KOREA, REPUBLIC OF
Number of pages
16
Pages from-to
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UT code for WoS article
001516808100001
EID of the result in the Scopus database
2-s2.0-105008178198