Production, distribution and applications of californium-252 neutron sources

Martin, R.C.; Knauer, J.B.; Balo, P.A.

doi:10.1016/s0969-8043(00)00214-1

Cited by 97 publications

(33 citation statements)

References 6 publications

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“…The neutron sources used in the MCNP simulation are a radioisotope spontaneous fission 252 Cf neutron source [16] and a 2.5 MeV D-D neutron generator [17][18][19].…”

Section: The Results Of Mcnp Simulation Of Neutron Radiation Sterilismentioning

confidence: 99%

“…Cf source [16], a D-D neutron generator or a T-D neutron generator [17]. In this study, a Monte Carlo N-particle (MCNP) code was used to simulate neutrons from a 252 Cf neutron source, or a D-D neutron generator, and to calculate the neutron energy deposition, neutron fluence and neutron radiation dose that are needed to sterilise anthrax contamination.…”

mentioning

confidence: 99%

“…The radioisotope 252 Cf is an intense neutron emitter that is routinely encapsulated in compact, cylindrical source capsules [16]. Decay by a emission and spontaneous fission result in an overall half-life of 2.645 years and neutron emission of 2.314610 9 s 21 mg…”

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confidence: 99%

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Monte Carlo N-particle simulation of neutron-based sterilisation of anthrax contamination

Liu

Xu²,

Liu³

et al. 2012

BJR

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Objective: To simulate the neutron-based sterilisation of anthrax contamination by Monte Carlo N-particle (MCNP) 4C code. Methods: Neutrons are elementary particles that have no charge. They are 20 times more effective than electrons or c-rays in killing anthrax spores on surfaces and inside closed containers. Neutrons emitted from a 252 Cf neutron source are in the 100 keV to 2 MeV energy range. A 2.5 MeV D-D neutron generator can create neutrons at up to 10 13 n s 21 with current technology. All these enable an effective and low-cost method of killing anthrax spores. Results: There is no effect on neutron energy deposition on the anthrax sample when using a reflector that is thicker than its saturation thickness. Among all three reflecting materials tested in the MCNP simulation, paraffin is the best because it has the thinnest saturation thickness and is easy to machine. The MCNP radiation dose and fluence simulation calculation also showed that the MCNP-simulated neutron fluence that is needed to kill the anthrax spores agrees with previous analytical estimations very well. Conclusion: The MCNP simulation indicates that a 10 min neutron irradiation from a 0.5 g 252 Cf neutron source or a 1 min neutron irradiation from a 2.5 MeV D-D neutron generator may kill all anthrax spores in a sample. This is a promising result because a 2.5 MeV D-D neutron generator output .10 13 n s 21 should be attainable in the near future. This indicates that we could use a D-D neutron generator to sterilise anthrax contamination within several seconds.

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“…The neutron sources used in the MCNP simulation are a radioisotope spontaneous fission 252 Cf neutron source [16] and a 2.5 MeV D-D neutron generator [17][18][19].…”

Section: The Results Of Mcnp Simulation Of Neutron Radiation Sterilismentioning

confidence: 99%

mentioning

confidence: 99%

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Monte Carlo N-particle simulation of neutron-based sterilisation of anthrax contamination

Liu

Xu²,

Liu³

et al. 2012

BJR

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“…[27] The californium source used for these tests is 23 alloyed with a noble metal in the form of a small wire, which is secured within two nested, stainless-steel cylinders. 24…”

Section: Neutron Source 15mentioning

confidence: 99%

Fast-neutron spectrometry using a 3He ionization chamber and digital pulse shape analysis

Chichester

Johnson

Seabury

2012

Applied Radiation and Isotopes

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7Digital pulse shape analysis (dPSA) has been used with a Cuttler-Shalev type 3 He ionization chamber to 8 measure the fast-neutron spectra of a deuterium-deuterium electronic neutron generator, a bare 252 Cf spontaneous 9 fission neutron source, and of the transmitted fast neutron spectra of a 252 Cf source attenuated by water, graphite, 10 liquid nitrogen, and magnesium. Rise-time dPSA has been employed using the common approach for analyzing 11 n + 3 He ĺ 1 H + 3 H ionization events and improved to account for wall-effect and pile-up events, increasing the 12 fidelity of these measurements. Simulations have been performed of the different experimental arrangements and 13 compared with the measurements, demonstrating general agreement between the dPSA-processed fast-neutron 14 spectra and predictions. The fast neutron resonance features of the attenuation cross sections of the attenuating 15 materials are clearly visible within the resolution limits of the electronics used for the measurements, and the 16 potential applications of high-resolution fast-neutron spectrometry for nuclear nonproliferation and safeguards 17 measurements are discussed. 18 19

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“…Energy and intensity of neutron beam should be chosen to maximize thermal neutron density in the proximity of the tumor area (Bisceglie et al, 2002), so the appropriate therapeutic neutron energy is in the 0.4 eV-10 keV range at the beam port. There are several neutron sources for BNCT (Patil et al, 2012;Burian et al, 2006;Martin et al, 2000;Durisi et al, 2007). Linear electron accelerators are rather cheap, compact, easy handling, low cost with less complexity.…”

Section: Introductionmentioning

confidence: 99%

Design of photon converter and photoneutron target for High power electron accelerator based BNCT

Rahmani

Seifi

Tavakoli-Anbaran

et al. 2015

Applied Radiation and Isotopes

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Production, distribution and applications of californium-252 neutron sources

Cited by 97 publications

References 6 publications

Monte Carlo N-particle simulation of neutron-based sterilisation of anthrax contamination

Monte Carlo N-particle simulation of neutron-based sterilisation of anthrax contamination

Fast-neutron spectrometry using a 3He ionization chamber and digital pulse shape analysis

Design of photon converter and photoneutron target for High power electron accelerator based BNCT

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