Ex-core neutron flux monitoring system in graphite prism for gen. IV reactors

Kód výsledku v 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>

Nalezeny alternativní kódy

RIV/68407700:21730/19:00339553

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Ex-core neutron flux monitoring system in graphite prism for gen. IV reactors

Popis výsledku v původním jazyce

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&amp;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.

Název v anglickém jazyce

Ex-core neutron flux monitoring system in graphite prism for gen. IV reactors

Popis výsledku anglicky

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&amp;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.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2019

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings of the 27th International Conference on Nuclear Engineering (ICONE27)

ISBN

978-4-88898-305-1

ISSN

—

e-ISSN

2424-2934

Počet stran výsledku

10

Strana od-do

1-10

Název nakladatele

American Society of Mechanical Engineers (ASME)

Místo vydání

New York

Místo konání akce

Ibaraki, Japan

Datum konání akce

19. 5. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—