Characterization of the neutron/<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline" id="d1e269" altimg="si34.svg"><mml:mi>γ</mml:mi></mml:math>-ray discrimination performance in an EJ-301 liquid scintillator for application to prompt fission neutron spectrum measurements at CSNS

Feng, Shiping; Hu, Chuangye; Zhen-hua, Zhang; Wang, Haoqiang; Ke-di, Zhu; Liu, Zijun; Chen, Chaomin; Zheng, B.; Huang, Hanxiong

doi:10.1016/j.radmeas.2022.106703

Radiation Measurements

2022

DOI: 10.1016/j.radmeas.2022.106703

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Characterization of the neutron/γ-ray discrimination performance in an EJ-301 liquid scintillator for application to prompt fission neutron spectrum measurements at CSNS

Shiping Feng

Chuangye Hu

Zhang Zhen-hua

et al.

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Cited by 11 publications

(1 citation statement)

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“…the physical design has been completed [21,22]. With the FAST spectrometer, the experimental uncertainty of the neutron-induced total cross-sections in the energy region of eV to keV will be improved due to the smooth reaction cross-section of 6 Li(n, α)T, and the statistical uncertainty will also be improved for the high detection effi-ciency of the FAST spectrometer.…”

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confidence: 99%

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Xue 薛,

Feng 冯,

Chen 陈

et al. 2023

Chinese Phys. C

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The neutron-induced total cross-section of 209Bi is crucial for the physical design and safety assessment of lead-based fast reactors, and the quality of experimental data should be improved for evaluation and application. A recent experiment was conducted on the back-streaming white neutron beamline (Back-n) at the China Spallation Neutron Source (CSNS) using the neutron total cross-section spectrometer (NTOX). The neutron energy was determined using a fast multi-cell fission chamber and the time-of-flight technique. Two high-purity bismuth samples, 6 mm and 20 mm in thickness, were chosen for neutron transmission measurements and comparisons. The neutron total cross-sections of 209Bi, ranging from 0.3 eV to 20 MeV, were derived considering neutron flight time determination, flight path calibration, and background subtraction. A comparison of the experimental results with the data in the ENDF/B-VIII.0 library showed fair agreement, and the point-wise cross-sections were found to be consistent with existing experimental data. Special attention was given to the determination of resonance parameters, which were analyzed using the R -matrix code SAMMY and Bayesian method in the 0.5 keV to 20 keV energy range. The extracted resonance parameters were compared to previously reported results and evaluated data. This study is recognized as the first one where the neutron total cross-section of bismuth across such a broad energy spectrum is measured in a single measurement or experiment, and it provides valuable data for the assessment of related reaction information for evaluated libraries and the advancement of lead-bismuth-based nuclear systems.

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mentioning

confidence: 99%

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Xue 薛,

Feng 冯,

Chen 陈

et al. 2023

Chinese Phys. C

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Fabrication of a Liquid Scintillator based on 7-Diethylamino-4-Methylcoumarin for Radiation Detection

et al. 2023

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Organic scintillation detectors are widely used to measure the presence or absence of radiation. With these devices, there are advantages in that they are easy to manufacture, large in size, and have a short uorescence decay time. However, they are not suitable for gamma measurements because they are composed of a low-atomic-number material. In this regard, alternative materials for the secondary solute used in basic organic scintillators have been investigated, and the applicability of alternative materials, the detection characteristics, and neutron/gamma identi cation tests were all assessed. 7-Diethylamino-4-methylcoumarin (DMC), selected as an alternative material, is a benzopyrone derivative in the form of colorless crystals with high uorescence, a high quantum yield in the visible region, and excellent light stability. In addition, it has a large Stokes shift, and solubility in a solvent is good. Through an analysis in this study, it was found that the absorption wavelength range of DMC coincides with the emission wavelength range of PPO, which is the primary solute used with DMC. Finally, it was con rmed that the optimal concentration of DMC was 0.08 wt%. As a result of performing gamma and neutron measurement tests using a DMC-based liquid scintillator, it was found to perform well (FOM = 1.42) compared to a commercial liquid scintillator, BC501A.

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Conceptual design of a Cs2LiLaBr6 scintillator-based neutron total cross section spectrometer on the back-n beam line at CSNS

Feng¹,

Cheng²,

Liu³

et al. 2023

NUCL SCI TECH

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Characterization of the neutron/γ-ray discrimination performance in an EJ-301 liquid scintillator for application to prompt fission neutron spectrum measurements at CSNS

Cited by 11 publications

References 23 publications

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Fabrication of a Liquid Scintillator based on 7-Diethylamino-4-Methylcoumarin for Radiation Detection

Conceptual design of a Cs2LiLaBr6 scintillator-based neutron total cross section spectrometer on the back-n beam line at CSNS

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Characterization of the neutron/γ-ray discrimination performance in an EJ-301 liquid scintillator for application to prompt fission neutron spectrum measurements at CSNS

Cited by 11 publications

References 23 publications

Measurement and analysis of the neutron-induced total cross-sections of 209Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Measurement and analysis of the neutron-induced total cross-sections of 209Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Fabrication of a Liquid Scintillator based on 7-Diethylamino-4-Methylcoumarin for Radiation Detection

Conceptual design of a Cs2LiLaBr6 scintillator-based neutron total cross section spectrometer on the back-n beam line at CSNS

Contact Info

Product

Resources

About

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*

Measurement and analysis of the neutron-induced total cross-sections of ²⁰⁹Bi from 0.3 eV to 20 MeV on the Back-n at CSNS*