Neutron flux optimization in irradiation channels at NUR research reactor

Meftah, B.; Zidi, T.; Bousbia-Salah, Anis

doi:10.1016/j.anucene.2006.08.003

Cited by 27 publications

(4 citation statements)

References 2 publications

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“…The equiv a lent cell model adopted in the cal cula tions is a three re gions model, as rec om mended in ref. [8]. The geo met ri cal rep re sen ta tion of such a cell is given in fig.…”

Section: Cal Cu La Tion Con DI Tionsmentioning

confidence: 99%

Fuel depletion calculation in MTR-LEU NUR reactor

et al. 2008

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In this article, we present the results of a few energy groups calculations for the NUR reactor fuel depletion analysis up to 45 000 MWd/tU taken as the maximum fuel burn up. The WIMSD-4 cell code has been employed as a calculation tool. In this study, we are interested in actinides such as the uranium and plutonium isotopes, as well as fission products Xe-135, Sm-149, Sm-151, Eu-155, and Gd-157. Calculation results regarding the five energy groups are in a good agreement with those obtained with only two energy groups which can, therefore, be used in all subsequent calculations. Calculation results presented in this article can be used as a microscopic data base for estimating the amount of radioactive sources randomly dispersed in the environment. They can also be used to monitor the fuel assemblies inventory at the core level

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“…The equiv a lent cell model adopted in the cal cula tions is a three re gions model, as rec om mended in ref. [8]. The geo met ri cal rep re sen ta tion of such a cell is given in fig.…”

Section: Cal Cu La Tion Con DI Tionsmentioning

confidence: 99%

Fuel depletion calculation in MTR-LEU NUR reactor

et al. 2008

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“…In this paper the previous research was upgraded by performing measurements with multiple in-core FCs simultaneously. In small research reactors such as TRIGA, the neutron flux profile inside the reactor core changes significantly in the axial and radial direction (Chiesa et al, 2015;Lin et al, 2006;Meftah et al, 2006;Stamatelatos et al, 2007;Štancar et al, 2012Zerovnik et al, 2015). The major effect of neutron flux redistribution is due to the control rod (CR) movement.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers

Goričanec

Žerovnik

Barbot

et al. 2018

Annals of Nuclear Energy

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Within the bilateral project between the CEA Cadarache and the Jožef Stefan Institute (JSI) a wide variety of measurements using multiple fission chambers simultaneously inside the reactor core were performed. The fission rate axial profiles were measured at different measuring positions and at different control rod configurations. A relative comparison of calculated fission rates using the MCNP code and the measured fission rates was performed. In general the agreement between the measurements and calculations is good, with deviations within the uncertainties. For better observation and understanding of neutron flux redistributions due to the control rod movement, the neutron flux and fission rate had been tallied through the entire reactor core at different control rod configurations. The optimal detector position with minimum signal variations due to the control rod movement was determined.

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“…The water is used as coolant, moderator, and reflector. The reactivity control system of the reactor is made of five absorbing rods: four control and safety rods and one fine regulating rod [6]. Among accidents that may affect this reactor are loss of flow, loss of coolant, reactivity insertion accidents, and loss of power supply.…”

Section: Introductionmentioning

confidence: 99%

Online monitoring and accident diagnosis aid system for the Nur Nuclear Research Reactor

Allalou¹,

Tadjine²,

Boucherit³

2016

Turk J Elec Eng & Comp Sci

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This paper deals with the design of a computerized monitoring and diagnosis aid system (CMDAS) for the Nur Nuclear Research Reactor based on real-time plant-specific safety parameters. The CMDAS carries out early detection and identification of accidents that might affect this reactor using supervised neural networks. The graphical programming language LabVIEW is used for creating a human-operator interface, networking, embedding the diagnosis procedure, and handling and storing the data. The methodology presented in this paper can be adapted for any nuclear research reactor.

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Neutron flux optimization in irradiation channels at NUR research reactor

Cited by 27 publications

References 2 publications

Fuel depletion calculation in MTR-LEU NUR reactor

Fuel depletion calculation in MTR-LEU NUR reactor

Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers

Online monitoring and accident diagnosis aid system for the Nur Nuclear Research Reactor

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