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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&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.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • 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

  • 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