Ex-core neutron flux monitoring system in graphite prism for gen. IV reactors
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F19%3A43955249" target="_blank" >RIV/49777513:23220/19:43955249 - isvavai.cz</a>
Alternative codes found
RIV/68407700:21730/19:00339553
Result on the web
<a href="https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_1627/_article/-char/en" target="_blank" >https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_1627/_article/-char/en</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1299/jsmeicone.2019.27.1627" target="_blank" >10.1299/jsmeicone.2019.27.1627</a>
Alternative languages
Result language
angličtina
Original language name
Ex-core neutron flux monitoring system in graphite prism for gen. IV reactors
Original language description
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given to the safety and security requirements of these reactors. One of the most critical safety criteria is connected to the control of the chain reaction and thus to the neutron flux monitoring system. The neutron flux monitoring system is an integral part of the instrumentation and control system (I&C) on reactor that has to be able to provide a full monitoring range information throughout the whole operation cycle. Neutron flux can be in general monitored via ex-core or in-core instrumentation. The measurement can be conducted by fission chambers, selfpowered neutron detectors (SPND), proportional counters, ionization chambers and other detectors such as plastic organic scintillators etc. The accurate positioning of neutron flux detectors has to be determined for each type of Gen. IV reactor with respect to all technical and physical aspects. This paper is aimed on ex-core measurement of neutron flux of Gen IV graphite moderated reactors, while discussing the international standards, safety requirements, technical requirements, quality requirements etc. This research will be applied to the molten salt modular reactor. The specification of the neutron flux monitoring system together with possible positioning is discussed with respect to the modular reactor dimensions and power. In the final part, first steps towards to the ex-core measurements for Gen IV are made. In order to be able to determine the correct position of the detector, the model of the reactor, where preliminary test will be made is created in Serpent code and this model is validated.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
Proceedings of the 27th International Conference on Nuclear Engineering (ICONE27)
ISBN
978-4-88898-305-1
ISSN
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e-ISSN
2424-2934
Number of pages
10
Pages from-to
1-10
Publisher name
American Society of Mechanical Engineers (ASME)
Place of publication
New York
Event location
Ibaraki, Japan
Event date
May 19, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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