Depletion measurements using a new gamma transparency method of irradiated MTR-type fuel assemblies

Krakovich, A.; Aviv, O.; Danon, L.; Ben-Meir, Kobi; Yungrais, Z.; Halfon, S.; Hazenshprung, Nir; Neder, Izhar

doi:10.1016/j.nima.2018.06.083

Cited by 5 publications

(4 citation statements)

References 13 publications

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“…First, it is significantly depleted, where the level of depletion measures the percentage of 235 U already consumed within the fuel (for example, 20% depletion means 20% of the initial amount of 235 U was consumed). The local depletion in chosen FA ranges from 20% to 80%, and an average depletion of 58% [41,42], ensuring a distinctive depletion profile of the FA. Second, it was not irradiated in the last decade, allowing the relatively short-lived fission products to decay, reducing the noise level in post-irradiation measurements.…”

Section: Methodsmentioning

confidence: 99%

“…The postirradiation measurements were performed two weeks after the FA irradiation, using an experimental setup similar to the one described in Ref. [42]. The setup consisted of a high-purity germanium spectroscopic gamma detector (a Canberra Falcon 5000 HPGe detector) aligned with an airfilled collimator positioned above the FA, which was lying horizontally in the pool on a designated stage 2.5 meter below water level, as shown in Figure 4.…”

Section: Experimental Spectroscopy Measurementsmentioning

confidence: 99%

“…Rods. IRR1 is routinely operated with the control rods partially inserted into the upper part of the core to about 25% depth [41,42]. This translates into the upper 15 cm of the fuel's active zone.…”

Section: The Partially Inserted Controlmentioning

confidence: 99%

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High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

Abuzlf,

Castagna,

Makmal

et al. 2023

International Journal of Energy Research

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In this study, a high-fidelity Monte Carlo model was utilized to investigate the localized behavior of the power peaking factor in a reactor core. The model considered the effect of water gaps, also known as flux traps, on the local power peaking. The model, developed using the Serpent code, employs a fine spatial mesh to accurately describe the fission power and burnup distribution. The results obtained from the model were validated through comparison with experimental measurements of the power distribution obtained from the IRR1 facility. The study found that the local accumulation of thermal flux caused by enhanced neutron moderation in the flux trap leads to a highly localized increase in power density, affecting the power peaking factor. The quantification of this effect was a key finding of the study. The results obtained from the study were highly dependent on the model’s fidelity, with significant differences being observed between the power peaking factor calculated on a fine mesh as opposed to that calculated at the plate or assembly scale. Furthermore, the experimental validation of the model enabled the prediction of the power peaking factor in other regions within the fuel assembly, which are not accessible to measurement instrumentation, with a high degree of confidence. The study’s findings may be useful for optimizing reactor design and operation and assessing the safety margins in reactors with similar characteristics.

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Section: Methodsmentioning

confidence: 99%

Section: Experimental Spectroscopy Measurementsmentioning

confidence: 99%

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High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

Abuzlf,

Castagna,

Makmal

et al. 2023

International Journal of Energy Research

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“…Only data outside the ROIs was modified (i.e., nullified), while all spectral properties within the ROIs remained unchanged. These spectra simulate realistic sample measurements obtained from HPGe Debris from an atmospheric nuclear explosion Simulation 14 - [13] HEU samples irradiated by thermal neutrons Experimental 10-45 - [13] Natural uranium sample irradiated by 25-MeV protons Experimental 30 - [13] Samples with fission and activation products Experimental 14-70 - [13] Soil samples containing elevated amounts of radionuclides of natural origin Experimental -- [13] Fukushima reactor accident Experimental 2-720 - [14] In situ measurements performed in the framework of an OSI exercise Experimental -- [15] Spent fuel rods aged 2 months-27 years Experimental -- [16] detectors having a measurement restriction. For illustration, figure 3 shows examples of four of the tested spectra: (1) A simulated nuclear fission test sample aged 15 days; (2) A simulated fission sample aged 60 days with elevated level of environmental background radioactivity; (3) A measured spectrum following the Fukushima reactor accident; (4) A soil sample (background) measurement.…”

Section: Methods Testingmentioning

confidence: 99%

A method for limiting data acquisition in a high-resolution gamma-ray spectrometer during On-Site Inspection activities under the Comprehensive Nuclear-Test-Ban Treaty

Aviv

Lipshtat

2018

J. Inst.

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A: On-Site Inspection (OSI) activities under the Comprehensive Nuclear-Test-Ban Treaty (CTBT) allow limitations to measurement equipment. Thus, certain detectors require modifications to be operated in a restricted mode. The accuracy and reliability of results obtained by a restricted device may be impaired. We present here a method for limiting data acquisition during OSI. Limitations are applied to a high-resolution high-purity germanium detector system, where the vast majority of the acquired data that is not relevant to the inspection is filtered out. The limited spectrum is displayed to the user and allows analysis using standard gamma spectrometry procedures. The proposed method can be incorporated into commercial gamma-ray spectrometers, including both stationary and mobile-based systems. By applying this procedure to more than 1000 spectra, representing various scenarios, we show that partial data are sufficient for reaching reliable conclusions. A comprehensive survey of potential false-positive identifications of various radionuclides is presented as well. It is evident from the results that the analysis of a limited spectrum is practically identical to that of a standard spectrum in terms of detection and quantification of OSI-relevant radionuclides. A future limited system can be developed making use of the principles outlined by the suggested method.

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JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations

Pungerčič,

Haghighat,

Snoj

2024

Nuclear Engineering and Technology

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Depletion measurements using a new gamma transparency method of irradiated MTR-type fuel assemblies

Cited by 5 publications

References 13 publications

High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core

A method for limiting data acquisition in a high-resolution gamma-ray spectrometer during On-Site Inspection activities under the Comprehensive Nuclear-Test-Ban Treaty

JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations

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