scholarly journals CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor

2021 ◽  
Vol 253 ◽  
pp. 04018
Author(s):  
Clément Fausser ◽  
Nicolas Thiollay ◽  
Christophe Destouches ◽  
Loïc Barbot ◽  
Damien Fourmentel ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Reactor Core ◽  
Nuclear Fission ◽  
Calculation Scheme ◽  
Experimental Program ◽  
Triga Reactor ◽  
Jozef Stefan Institute ◽  
Stefan Institute ◽  
Fission Reactors ◽  
Alternative Energies

Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation. In particular, nuclear sensors used in nuclear fission reactors (research or power reactors) or in nuclear fusion facilities are operated under intense mixed neutron and gamma-ray fields, and need to be calibrated and modeled to provide selective and accurate neutron and gamma-ray measurements. The French Atomic Energy and Alternative Energies Commission (CEA) and the Jožef Stefan Institute (JSI) have started an experimental program dedicated to a detailed experimental benchmark with analysis using Monte Carlo particle transport calculations and a series of neutron and gamma-ray sensor types used in the JSI TRIGA Mark II reactor. CEA has setup a simplified TRIPOLI-4® modeling scheme of the JSI TRIGA reactor based on the information available in the IRPhEP benchmark in order to facilitate analysis of future neutron and gamma-ray measurements. These allow the CEA to perform a TRIPOLI-4 instrumentation calculation scheme benchmarked with the JSI MCNP model. This paper presents the main results of this CEA calculation scheme application and the analysis of their comparison to the JSI results obtained in 2012 with the MCNP5 & ENDF/B-VII.0 calculation scheme. This paper will conclude with some information about the new experimental program to be carried out in 2022 in the TRIGA reactor core.

scholarly journals Calculations to Support On-line Neutron Spectrum Adjustment by Measurements with Miniature Fission Chambers in the JSI TRIGA Reactor

2018 ◽  
Vol 170 ◽  
pp. 04012 ◽  
Author(s):  
Tanja Kaiba ◽  
Vladimir Radulović ◽  
Gašper Žerovnik ◽  
Luka Snoj ◽  
Damien Fourmentel ◽  
...  
Keyword(s):  
Fuel Element ◽  
Reactor Core ◽  
Experimental Conditions ◽  
Triga Reactor ◽  
Jozef Stefan Institute ◽  
Stefan Institute ◽  
Transmission Filter ◽  
On Line ◽  
Flux Spectrum ◽  
Fission Chambers

Preliminary calculations were performed with the aim to establish optimal experimental conditions for the measurement campaign within the collaboration between the Jožef Stefan Institute (JSI) and Commissariat à l’Énergie Atomique et aux Énergies Alternatives (CEA Cadarache). The goal of the project is to additionally characterize the neutron spectruminside the JSI TRIGA reactor core with focus on the measurement epi-thermal and fast part of the spectrum. Measurements will be performed with fission chambers containing different fissile materials (235U, 237Np and 242Pu) covered with thermal neutron filters (Cd and Gd). The changes in the detected signal and neutron flux spectrum with and without transmission filter were studied. Additional effort was put into evaluation of the effect of the filter geometry (e.g. opening on the top end of the filter) on the detector signal. After the analysis of the scoping calculations it was concluded to position the experiment in the outside core ring inside one of the empty fuel element positions.

Simultaneous measurement of neutron and gamma-ray radiation levels from a TRIGA reactor core using silicon carbide semiconductor detectors

1999 ◽  
Vol 46 (3) ◽  
pp. 275-279 ◽  
Author(s):  
A.R. Dulloo ◽  
F.H. Ruddy ◽  
J.G. Seidel ◽  
C. Davison ◽  
T. Flinchbaugh ◽  
...  
Keyword(s):  
Silicon Carbide ◽  
Simultaneous Measurement ◽  
Gamma Ray ◽  
Reactor Core ◽  
Semiconductor Detectors ◽  
Triga Reactor

Evaluation of comparison and proficiency test results of gamma ray spectrometry at Jožef Stefan Institute from 1986 to 2014

2016 ◽  
Vol 109 ◽  
pp. 54-60 ◽  
Author(s):  
Denis Glavič-Cindro ◽  
Matjaž Korun ◽  
Marijan Nečemer ◽  
Branko Vodenik ◽  
Benjamin Zorko
Keyword(s):  
Proficiency Test ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Test Results ◽  
Jozef Stefan Institute ◽  
Stefan Institute

scholarly journals Computational support on the development of nuclear heating calorimeter detector design

2020 ◽  
Vol 225 ◽  
pp. 04033
Author(s):  
Klemen Ambrožič ◽  
Damien Fourmentel ◽  
Hubert Carcreff ◽  
Vladimir Radulović ◽  
Luka Snoj
Keyword(s):  
Energy Deposition ◽  
Detector Response ◽  
Heating Rates ◽  
Triga Reactor ◽  
Computational Support ◽  
Nuclear Heating ◽  
Gamma Flux ◽  
Fission Reactors ◽  
High Neutron ◽  
Detector Design

Heating due to energy deposition of intense ionizing radiation in samples and structural materials of nuclear reactors poses severe limitations in terms of cooling requirements for safe reactor operation, especially in high neutron and gamma flux environments of material testing fission reactors (MTRs) and novel fusion devices. A bilateral CEA-JSI research project was launched in 2018 with the objective to measure the gamma heating rates in standard reactor-related materials (graphite, aluminium, stainless steel and tungsten) as well as fusionrelevant materials (low-activation steel Eurofer-97 and Nb3Sn superconductor) in the JSI TRIGA reactor my means of gamma calorimeters. The calorimeter design will be based on the the CALMOS-2 calorimeter developed at the CEA and used to perform gamma heating measurements in the OSIRIS MTR in Saclay. In order to optimize the detector response inside the JSI TRIGA reactor field and not to perturb the measurement field, a detailed computational analysis was performed in terms of energy deposition assessment and measurement field perturbation using the MCNP v6.1 code, and in terms of heat transfer using the COMSOL Multiphysics code. The abovementioned activities enabled us to finalize the detector design with the experimental campaign planned for the end of year 2019.

scholarly journals Determination of backscattered neutrons/gammas from open beam port of a research reactor

2020 ◽  
Vol 225 ◽  
pp. 04032
Author(s):  
Anže Jazbec ◽  
Bor Kos ◽  
Vladimir Radulović ◽  
Klemen Ambrožič ◽  
Luka Snoj
Keyword(s):  
Research Reactor ◽  
Gamma Dose ◽  
Computation Model ◽  
Beam Tube ◽  
Horizontal Beam ◽  
Beam Port ◽  
Jozef Stefan Institute ◽  
Stefan Institute ◽  
Triga Mark Ii

Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Results were compared to the experimental measurements in order to verify the computation model. In addition, another set of calculations and measurements was carried out, where an additional shield made out of concrete and paraffin was installed. With that configuration, we were able to study neutron and gamma scattering.

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