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CALCULATION METHODOLOGY ASSESSMENT TO DETECT LOCALISED PERTURBATION IN SODIUM-COOLED FAST REACTOR WITH EX-CORE INSTRUMENTATION
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Physics and Astronomy, Applied Nuclear Physics. (Fission Diagnostics and Safeguards)
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Physics and Astronomy, Applied Nuclear Physics. (Fission Diagnostics and Safeguards)
(CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache)
(CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache)
2016 (English)In: CALCULATION METHODOLOGY ASSESSMENT TO DETECTLOCALISED PERTURBATION IN SODIUM-COOLED FAST REACTORWITH EX-CORE INSTRUMENTATION, 2016Conference paper, Published paper (Refereed)
Abstract [en]

Safety and reliability are essential requirements for development and operation of SodiumcooledFast Reactors. Development of a neutron flux monitoring system (NFMS) for the FrenchSFR is one of the key R&D areas identified. Diverse possibilities of detector system installationshould be studied for different locations in the reactor vessel in order to detect any perturbations inthe core. In this paper, we aim to explore two calculation routes available for neutron flux monitoring,assess them for their efficiency to detect fission rate variation at Above-core structure (ACS)location and discuss the associated pros and cons. The two calculational approaches we refer hereare criticality mode and external source mode. We discuss the feasibility of choosing this locationfor detecting in-core perturbations and evaluate the methodology needed to achieve it. The paperfocuses on the difficulties associated with neutron detection when the detectors are located at far-offdistances from the source. We found that for a difficult case such as ours where the detectors arelocated far-away from the source, criticality mode doesn’t work. Variance reduction techniques,employed in the external source mode are indispensable to drive neutrons to areas of interest.

Place, publisher, year, edition, pages
2016.
Keyword [en]
Sodium Cooled Fast reactors, Fission chambers, Instrumentation, Variance reduction
National Category
Subatomic Physics
Research subject
Physics with specialization in Applied Nuclear Physics
Identifiers
URN: urn:nbn:se:uu:diva-297045OAI: oai:DiVA.org:uu-297045DiVA: diva2:940606
Conference
PHYSOR 2016
Funder
Swedish Research Council, B0774801
Available from: 2016-06-21 Created: 2016-06-21 Last updated: 2017-05-09
In thesis
1. Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors
Open this publication in new window or tab >>Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors
2017 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems. The neutron flux monitoring system forms an integral part of the safety design of a nuclear reactor and must be able to detect any irregularities during all states of reactor operation. The work in this thesis mainly concerns the detection of in-core perturbations arising from unwanted movements of control rods with in-vessel neutron detectors in a sodium-cooled fast reactor. Feasibility study of self-powered neutron detectors (SPNDs) with platinum emitters as in-core power profile monitors for SFRs at full power is performed. The study shows that an SPND with a platinum emitter generates a prompt current signal induced by neutrons and gammas of the order of 600 nA/m, which is large enough to be measurable. Therefore, it is possible for the SPND to follow local power fluctuations at full power operation. Ex-core and in-core detector locations are investigated with two types of detectors, fission chambers and self-powered neutron detectors (SPNDs) respectively, to study the possibility of detection of the spatial changes in the power profile during two different transient conditions, i.e. inadvertent withdrawal of control rods (IRW) and one stuck rod during reactor shutdown (OSR). It is shown that it is possible to detect the two simulated transients with this set of ex-core and in-core detectors before any melting of the fuel takes place. The detector signal can tolerate a noise level up to 5% during an IRW and up to 1% during an OSR.

Place, publisher, year, edition, pages
Uppsala: Acta Universitatis Upsaliensis, 2017. 70 p.
Series
Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology, ISSN 1651-6214 ; 1508
Keyword
Protection systems, safety, accidents, sodium-cooled fast reactor, instrumentation, fission chamber, self powered neutron detector
National Category
Subatomic Physics
Identifiers
urn:nbn:se:uu:diva-319945 (URN)978-91-554-9897-9 (ISBN)
Public defence
2017-06-01, Polhemsalen, Ångströmlaboratoriet, Lågerhyddsvägen 1, Uppsala, 09:15 (English)
Supervisors
Available from: 2017-05-10 Created: 2017-04-11 Last updated: 2017-05-23

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