Experimental validation of photon-heating calculation for the Jules Horowitz Reactor

Lemaire, Matthieu; Vaglio–Gaudard, C.; Lyoussi, A.; Reynard-Carette, C.; Salvo, J. Di; Gruel, A.

doi:10.1016/j.nima.2015.01.054

Cited by 6 publications

(6 citation statements)

References 22 publications

(22 reference statements)

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“…MCNP / TRIPOLI-4.9 ® COMPARISON FOR ABSORBED-DOSE AND KERMA CALCULATIONS Reference [13] presented an interpretation with the TRIPOLI-4.9 ® code of photon-heating measurements carried out during the AMMON program [14] in the EOLE critical mock-up at Cadarache. One of the goals of the AMMON experiment consisted in validating the calculations of photon parameters for JHR.…”

Section: Results and Analysismentioning

confidence: 99%

“…We presented in [13] an interpretation with the TRIPOLI-4.9 ® code of photon-heating measurements carried out with TLDs and OSLDs in the AMMON experiment conducted in the critical mock-up EOLE of CEA Cadarache. We analyze in this section to what extent the Calculation / Experiment (C/E) values obtained in [13] would change if the interpretation was conducted with MCNP instead of TRIPOLI-4.9 ® .…”

Section: Impact On the Ammon Interpretationmentioning

confidence: 99%

“…We analyze in this section to what extent the Calculation / Experiment (C/E) values obtained in [13] would change if the interpretation was conducted with MCNP instead of TRIPOLI-4.9 ® . Table VI shows that an absorbed-dose value calculated by MCNP in a JHR-representative geometry is approximately 3% greater than the value calculated by TRIPOLI-4.9 ® .…”

Section: Impact On the Ammon Interpretationmentioning

confidence: 99%

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Impact Study on the Methodology used for Photon-Heating Determination in Material-Testing Reactors

Lemaire

Vaglio–Gaudard

Lyoussi

et al. 2016

IEEE Trans. Nucl. Sci.

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Abstract-Determination of photon heating by calculation is an important issue for the Jules Horowitz Reactor (JHR), the next international Material-Testing Reactor (MTR) under construction at CEA Cadarache research center in the south of France. Accurate knowledge of photon heating in structure materials and irradiation devices is necessary for JHR design and safety studies. In this paper, we quantify the impact of different photon-heating calculation routes by comparing absorbed dose and KERMA calculations (Kinetic Energy Released per MAss) from two different Monte Carlo codes, TRIPOLI-4.9® and MCNP (Monte Carlo N-Particle transport code). These calculations are carried out in JHR-representative geometries with the nuclear-data library JEFF3.1.1 and the photon-data library EPDL97. Discrepancies amounting to up to 18% between absorbed dose and KERMA are found in JHR irradiation devices and are linked to charged-particle transport effects taking place in heterogeneous materials of small dimensions. In a JHRassembly cell, discrepancies of about 1% on photon KERMA and of about 3% on absorbed dose are highlighted between the two Monte Carlo codes. These latter discrepancies are small compared to typical sources of uncertainty for Monte Carlo calculation (for instance, nuclear data uncertainty) and are supposed to be due to differences in the processing of gammaproduction data by neutron interactions and to differences in electromagnetic-shower models and implementation between the two codes.

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Section: Results and Analysismentioning

confidence: 99%

Section: Impact On the Ammon Interpretationmentioning

confidence: 99%

Section: Impact On the Ammon Interpretationmentioning

confidence: 99%

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Impact Study on the Methodology used for Photon-Heating Determination in Material-Testing Reactors

Lemaire

Vaglio–Gaudard

Lyoussi

et al. 2016

IEEE Trans. Nucl. Sci.

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“…DOSE AND KERMA CALCULATIONS Reference [9] presented an interpretation with the TRIPOLI-4.9 ® code of photon-heating measurements carried out during the AMMON program [10] in the EOLE critical mock-up at Cadarache. One of the goals of the AMMON experiment consisted in validating the calculations of photon parameters for JHR.…”

Section: Mcnp / Tripoli-49 ® Comparison For Absorbed-mentioning

confidence: 99%

Impact study on the methodology used for photon-heating determination in material-testing reactors

Lemaire¹,

Vaglio–Gaudard²,

Lyoussi³

et al. 2015

2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (ANIMMA

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Determination of photon heating by calculation is an important issue for the Jules Horowitz Reactor (JHR), the next international Material-Testing Reactor (MTR) under construction in the south of France. Accurate knowledge of photon heating in structure materials and irradiation devices is necessary for JHR design and safety studies. In this paper, we quantify the impact of different photon-heating calculation routes by comparing absorbed dose and KERMA calculations (Kinetic Energy Released per MAss) from two different Monte Carlo codes, TRIPOLI-4.9® and MCNP (Monte Carlo N-Particle transport code). These calculations are carried out in JHRrepresentative geometries with the nuclear-data library JEFF3.1.1 and the photon-data library EPDL97. Discrepancies amounting to up to 18% between absorbed dose and KERMA are found in JHR irradiation devices and are linked to chargedparticle transport effects taking place in heterogeneous materials of small dimensions. In a JHR-assembly cell, discrepancies of about 1% on photon KERMA and of about 3% on absorbed dose are highlighted between the two Monte Carlo codes. These latter discrepancies are small compared to typical sources of uncertainty for Monte Carlo calculation (for instance, nuclear data uncertainty) and are supposed to be due to differences in the processing of gamma-production data by neutron interactions and to differences in electromagnetic-shower models and implementation between the two codes.

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“…HE accurate determination of nuclear heating in materials is a major issue for the development of nuclear technology and in particular the design of new core concepts, such as the Jules Horowitz material testing reactor [1].…”

Section: Introductionmentioning

confidence: 99%

Tests and Foreseen Developments of Fibered-OSLD Gamma-Heating Measurements in Low-Power Reactors

Gruel

Guillou

Blaise

et al. 2018

IEEE Trans. Nucl. Sci.

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Abstract-In this paper are presented test measurements of a fibered-OSLD system performed during a dedicated experimental phase in EOLE zero-power reactor. The measurement setup consists of an OSLD crystal connected onto the extremity of an optical fiber and a laser stimulation system, manufactured by the CEA/LIST in Saclay. The OSL sensor is remotely stimulated via an optical fiber using a diode-pumped solid-state laser. The OSL light is collected and guided back along the same fiber to a photomultiplier tube. Results obtained using this system are compared to usual gamma heating measurement protocol using OSLD pellets. The presence of induced radio-luminescence in the OSLD during the irradiation was also observed and could be used to monitor the gamma flux.The feasibility of remote measurements is achieved, whereas further developments could be conducted to improve this technique since the readout procedure still requires to withdraw the OSLD off the gamma flux (hence from the core) on account of the dose rate (around a few Gy.h -1 ), and the readout time remains quite long for on-line applications. Several improvements are foreseen, and will be tested in the forthcoming years.Index Terms-nuclear heating, optical fibers, optically stimulated luminescent dosimeters, remote readout I. INTRODUCTION HE accurate determination of nuclear heating in materials is a major issue for the development of nuclear technology and in particular the design of new core concepts, such as the Jules Horowitz material testing reactor [1].In material testing reactors the neutron and gamma flux levels allow to measure directly the nuclear heating by calorimetry based techniques for instance. In mock-ups or zero-power reactors (ZPRs), such as EOLE and MINERVE reactors at Cadarache [2], the low operating level -typically from some watts to some kilowatts -requires the use of different methods such as dosimetry. In the past few years, several experimental programs [3][4] were devoted to the improvement of gamma heating measurements using thermoluminescent and optically stimulated luminescent dosimeters (TLDs and OSLDs, respectively). However, the main drawback of nuclear heating measurement in low-power reactors remains the off-line gamma heating estimation, given that both TLD and OSLD stimulations (thermal and optical respectively) allowing the readout of the absorbed doses can only be performed after irradiation and out of core. To circumvent this disadvantage, an effort is being made on the development of in situ and on-line measurement of the gamma heating. One of the considered solutions is the use of optical fibered systems.In the first section are presented the main principles of gamma heating measurements in low-power reactors, and especially the system that was used for. In the second section are presented the results of test measurements performed in the EOLE reactor. II. GAMMA HEATING MEASUREMENTS USING OPTICAL FIBERS A. Overview and general principlesNuclear heating in material arises from the local deposition of energy carr...

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Experimental validation of photon-heating calculation for the Jules Horowitz Reactor

Cited by 6 publications

References 22 publications

Impact Study on the Methodology used for Photon-Heating Determination in Material-Testing Reactors

Impact Study on the Methodology used for Photon-Heating Determination in Material-Testing Reactors

Impact study on the methodology used for photon-heating determination in material-testing reactors

Tests and Foreseen Developments of Fibered-OSLD Gamma-Heating Measurements in Low-Power Reactors

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