Application of 252Cf neutron source for precise nuclear data experiments

Schulc, Martin; Košťál, Michal; Novák, Evžen; Kubín, Rostislav; Šimon, Jan

doi:10.1016/j.apradiso.2019.06.012

Cited by 29 publications

(9 citation statements)

References 11 publications

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“…4. The efficiency calibration was tested using Cf point neutron source [6]. The same source was used for estimation of deconvolution uncertainty, which was estimated being lower than 5 % [7].…”

Section: Iiib Stilbene Measurementsmentioning

confidence: 99%

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Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Košťál

Matěj

Schulc

et al. 2023

Nuclear Science and Engineering

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The integral experiments covering the neutron leakage from geometrically simple assemblies with a 252 Cf source inside are very valuable tools usable in validation of transport cross section data, since geometric uncertainties play a much smaller role in simple geometric assemblies than in complex assemblies as for example reactor pressure vessel geometry. Since 252 Cf(s.f.) is standard neutron source, the uncertainties connected with the source neutron spectrum can be even neglected. The paper refers on validation efforts of neutron leakage from stainless steel block ~50×50×50 cm in Research Center Rez. Both the neutron leakage flux at a distance of 1 m from the center of the cubical assembly using stilbene spectrometry and the activation rates at different positions of the assembly were evaluated. In addition to experiments, main sources of uncertainty were identified and evaluated. The results of the stilbene measurements are consistent with the activation measurements results.

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Section: Iiib Stilbene Measurementsmentioning

confidence: 99%

“…1). The purpose of the study is to bring an additional set of experimental data to the historical measurements of pure iron in spherical geometries [1] used by nuclear data evaluators to test the consistency of their theories. Current benchmarking efforts and detailed results are summarized in the OECD-NEA report [2].…”

Section: Introductionmentioning

confidence: 99%

Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Košťál

Matěj

Schulc

et al. 2023

Nuclear Science and Engineering

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“…The experiments were performed during source emission between 2.9E8 n/s and 8.0E8 n/s. The experimental uncertainties and irradiation geometry of low and high volume sources were extensively described in [15]. The performed set of experiments involving 252 Cf was described in [16][17][18][19].…”

Section: Neutron Sources Descriptionmentioning

confidence: 99%

Spectral averaged cross sections as a probe to a high energy tail of ²³⁵U PFNS

et al. 2023

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The systematic evaluations of spectrum averaged cross sections of dosimetric reactions over a broad range of energies were performed in 252Cf (spontaneous fission) and 235U(nth,f) neutron fields. The neutron sources used in this study were LR-0, VR-1 zero power research light water reactors, LVR-15 10 MW research light water reactor, and 252Cf neutron source with emission specified precisely by the manganese sulphate bath. All spectral averaged cross sections were inferred from measured reaction rates which were derived from gamma spectrometry. These gamma spectrometry measurements were performed using a single detector in all cases. The ratios of 252Cf and 235U spectral averaged cross sections can be used to specify the high energy tail of the 235U prompt fission neutron spectrum as the 252Cf spontaneous fission spectrum is considered as a standard. Furthermore, ratios are independent of cross section uncertainties since uncertainties in the cross sections are eliminated. Theoretical models of fission can be tested based on our measurements. The calculations were performed in MCNP6.2 transport code using different prompt fission neutron spectra and IRDFF-II cross sections for threshold reactions. The ratios are in good agreement using only ENDF/B-VIII.0 235U prompt fission neutron spectrum suggesting it to be harder than in other evaluations.

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“…According to the calculation results, the magnetic trap has the following parameters: the magnetic field in the injection side plug B inj = 1.6 T, B min = 0.26 T, B ext = 1.49 T, total weight of magnets M = 550 kg, V plasma = 288 cm 3 , S plasma = 30 cm 2 , L = 210 mm. To heat the plasma in a CW mode, it is proposed to use a technological gyrotron with frequency of 28 GHz and power of up to 10 kW [34].…”

Section: New Magnetic Systemmentioning

confidence: 99%

“…Neutron sources are widely used in fundamental and applied studies [1]. There are different types of neutron sources (nuclear reactors [2], radioisotope sources [3], accelerator-based sources [4][5][6][7][8][9][10][11][12], etc.). They are in demand for various applications (neutronography, boron neutron capture therapy (BNCT), neutron tomography etc.…”

Section: Introductionmentioning

confidence: 99%

Ion beam source upgrade of the neutron source at IAP RAS

Skalyga

et al. 2022

Technical Physics

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The results of the ion source of the neutron generator upgrade, which makes it possible to operate in a CW mode, are presented. A magnetic trap consisting of permanent magnets (NdFeB) was developed. A 3-electrode extraction system equipped with a magnetic lens was used to extract the deuterium ion beam. Calculations are made for the formation of a deuterium ion beam with a current over 500 mA and an energy of 100 keV with practically no losses in the extraction system. Keywords: extraction system, magnetic trap, neutron generator, ion beam.

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Application of 252Cf neutron source for precise nuclear data experiments

Cited by 29 publications

References 11 publications

Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Spectral averaged cross sections as a probe to a high energy tail of ²³⁵U PFNS

Ion beam source upgrade of the neutron source at IAP RAS

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Application of 252Cf neutron source for precise nuclear data experiments

Cited by 29 publications

References 11 publications

Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez

Spectral averaged cross sections as a probe to a high energy tail of 235U PFNS

Ion beam source upgrade of the neutron source at IAP RAS

Contact Info

Product

Resources

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Spectral averaged cross sections as a probe to a high energy tail of ²³⁵U PFNS