Evaluation of Lithium Gadolinium Borate Capture-Gated Spectrometer Neutron Efficiencies

Menaa, N.; Villani, M.; Croft, Stuart; McElroy, R.B.; Philips, S. A.; Czirr, J.B.

doi:10.1109/tns.2009.2015299

Cited by 18 publications

(24 citation statements)

References 1 publication

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“…A typical example is lithium gadolinium borate (LGB) doped with cerium [17,18]a which makes scintillating microcrystals that can be blended in PVT matrix (BC-490), for a possible neutron spectrometry [19]. This work demonstrated an increased resolution on standard samples (60 cm 3 ) for monoenergetic proton beam, but also claimed that higher volumes do not increase the resolution [18]b due to the weak light output and the diffusive nature of the dispersed LGB.…”

Section: Lithium Boron Cadmium and Gadolinium Loadings For Thermal mentioning

confidence: 99%

Pulse shape discrimination between (fast or thermal) neutrons and gamma rays with plastic scintillators: State of the art

Bertrand

Hamel

Normand

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

107

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Section: Lithium Boron Cadmium and Gadolinium Loadings For Thermal mentioning

confidence: 99%

Pulse shape discrimination between (fast or thermal) neutrons and gamma rays with plastic scintillators: State of the art

Bertrand

Hamel

Normand

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

107

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“…LGB/scintillating-plastic detectors for possible use as a handheld neutron spectrometer [9]. Flaska, Pozzi, and Czirr have also studied a 12.7 cm (5") diameter, 10.2 cm (4") long detector [10].…”

Section: Et Al Have Evaluated Cylindricalmentioning

confidence: 99%

Performance of Large Neutron Detectors Containing Lithium-Gadolinium-Borate Scintillator

Slaughter¹,

Stuart²,

Klaass³

et al. 2016

IEEE Trans. Nucl. Sci.

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This paper describes the development and testing of a neutron counter, spectrometer, and dosimeter that is compact, efficient, and accurate. The 1.3 liter detector head for this instrument is a composite detector with an organic scintillator containing uniformly distributed 6 Li6 nat Gd 10 B3O9:Ce (LGB:Ce) microcrystals. Moderating neutrons that have slowed sufficiently in the plastic, capture in one of the Lithium-6, Boron-10, or Gadolinium-157/155 atoms in the LGB:Ce scintillator, which then releases the capture energy in a characteristic cerium emission pulse. The measured captured pulses indicate the presence of neutrons. When a scintillating fluor is present in the plastic, the light pulse resulting from the neutron moderating in the plastic is paired with the LGB:Ce capture pulse to identify the energy of the neutron. This data was used to assist in the unfolding of the neutron spectra. The unfolded spectra were then validated with known spectra, at both neutron emitting isotopes and fission/accelerator facilities, Los Alamos Neutron Science Center (LANSCE), Edwards Accelerator Laboratory (EAL) at Ohio University. The instrument can measure neutrons and their spectra over the range between 0.8 MeV and 150 MeV with an average uncertainty in neutron rate of only +/-8%.

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“…While boron-lined proportional counting tubes have shown promise [2,3], several groups have been working on novel neutron detection materials with promising recent results, notably Cs 2 LiYCl 6 (or simply CLYC) [4] and PSD-enabled plastic scintillators [5,6]. Other groups have investigated composite scintillators -heterogenous materials composed of neutron-sensitive grains embedded in a supporting plastic matrix -for their potential application in both basic neutron detection [7][8][9] and capture-gated neutron spectrometry [10,11].…”

Section: The 3 He Supply Problemmentioning

confidence: 99%

Fabrication and characterization of a lithium-glass-based composite neutron detector

Rich

Kazkaz

Martínez

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

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A novel composite, scintillating material intended for neutron detection and composed of small (1.5 mm) cubes of KG2-type lithium glass embedded in a matrix of scintillating plastic has been developed in the form of a 2.2 in.diameter, 3.1 in.-tall cylindrical prototype loaded with (5.82 ± 0.02) % lithium glass by mass. The response of the material when exposed to 252 Cf fission neutrons and various γ-ray sources has been studied; using the charge-integration method for pulse shape discrimination, good separation between neutron and γ-ray events is observed and intrinsic efficiencies of (1.15 ± 0.16) × 10 −2 and (2.28 ± 0.21) × 10 −4 for 252 Cf fission neutrons and 60 Co γ rays are obtained; an upper limit for the sensitivity to 137 Cs γ rays is determined to be < 3.70 × 10 −8 . The neutron/γ discrimination capabilities are improved in circumstances when a neutron capture signal in the lithium glass can be detected in coincidence with a preceding elastic scattering event in the plastic scintillator; with this coincidence requirement, the intrinsic efficiency of the prototype detector for 60 Co γ rays is (2.42 ± 0.61) × 10 −6 while its intrinsic efficiency for unmoderated 252 Cf fission neutrons is (4.31 ± 0.59) × 10 −3 . Through use of subregion-integration ratios in addition to the coincidence requirement, the efficiency for γ rays from 60 Co is reduced to (7.15 ± 4.10) × 10 −7 while the 252 Cf fission neutron efficiency becomes (2.78 ± 0.38) × 10 −3 .

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Evaluation of Lithium Gadolinium Borate Capture-Gated Spectrometer Neutron Efficiencies

Cited by 18 publications

References 1 publication

Pulse shape discrimination between (fast or thermal) neutrons and gamma rays with plastic scintillators: State of the art

Pulse shape discrimination between (fast or thermal) neutrons and gamma rays with plastic scintillators: State of the art

Performance of Large Neutron Detectors Containing Lithium-Gadolinium-Borate Scintillator

Fabrication and characterization of a lithium-glass-based composite neutron detector

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