Study of neutron production and moderation for sulfur neutron capture therapy

Peng, Meng; He, Guo‐Zhong; Zhang, Qiwei; Shi, Bin; Tang, Hongqing; Zhou, Zuying

doi:10.1007/s41365-018-0529-3

Cited by 9 publications

(4 citation statements)

References 17 publications

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“…Sulfur-33, a stable isotope, is an intriguing isotope that has recently been presented as a neutron capture or cooperative target for boosting boron neutron therapy [11][12][13][14]. In the keV range, the 33 S (n, α) 30 Si cross section exhibits greater magnitude than that of the (n, γ) reaction.…”

Section: Introductionmentioning

confidence: 99%

A Monte Carlo study of the Cellular Dosimetry for SNCT Comparison with MIRD S Values

Zhang,

Lan,

Jiang

et al. 2023

Preprint

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Background An interesting isotope, sulfur-33 (a stable isotope), has been proposed as an additional neutron capture or a cooperating target for enhancing boron neutron capture therapy. Recently, 33S was considered as the substitute for boron-10 in neutron capture radiotherapy. The 33S (n, α)30Si reaction emits the α particles useful for neutron capture therapy. Based on the Monte Carlo method, we investigated the dosimetric characteristics of the cellular model of several geometries for the sulfur-33 neutron capture therapy (SNCT). Methods Monte Carlo N-Particle (MCNP) was used for simulating the transport of α particles emitted by SNCT from the cellular model surface (CS), cytoplasm (Cy), or nucleus (N) of a single cell model. The model cells were defined as two concentric spheres consisting of the nucleus and cytoplasm. The radius of the cell model was Rc=6 µm Rn=3 µm. The S values (SC←C, SC←CS, SN←N, SN←Cy, SN←CS) were compared to the results with the Medical Internal Radiation Dosimetry (MIRD) method. Finally, S values of the cellular model of several geometries were calculated. Results The relative differences of MCNP versus MIRD method S values for SNCT ranged from 0.28% to 4.29% for C to C (SC←C), -2.82% to 0.05% for Cs to C (SC←Cs), 0.54% to 4.42% for N to N (SN←N), 0.72% to 3.14% for Cy to N (SN ←Cy), and -1.76% to 0.36% for CS to N (SN←CS). The ratios of SN←N/ SC←C, SN←CS/SC←C, SN←Cy/ SC←C decreased with increasing the cell and nucleus size. Conclusion The S value simulated by MCNP is in agreement with the MIRD method, which is proved to be reliable for the cellular dosimetry of SNCT by the Monte Carlo method. The Model Carlo method can be used instead of the MIRD method to accurately calculate cellular S values, which solves the problem of cell shape limitation in MIRD method (which is suitable for regular spherical cellular model).

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Section: Introductionmentioning

confidence: 99%

A Monte Carlo study of the Cellular Dosimetry for SNCT Comparison with MIRD S Values

Zhang,

Lan,

Jiang

et al. 2023

Preprint

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“…Current adequate neutron sources derived from nuclear reactors are very expensive and it is almost impossible to build nuclear reactor in hospitals. Therefore, neutron sources from accelerators are developed [3,4]. A model of accelerator that is currently being developed and is suitable for laboratory and hospital purposes is the cyclotron [5].…”

Section: Introductionmentioning

confidence: 99%

Optimization and Verification of Double Layer Beam Shaping Assembly (Dlbsa) for Epithermal Neutron Generation

et al. 2022

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The designs of Beam Shaping Assembly (BSA) for moderating fast neutron into epithermal neutron have been conducted. Some BSA models that are previously developed are still having problems in generating epithermal neutron. Instead, we propose designs of double layer beam shaping assembly (DLBSA) to produce epithermal neutron. Optimization of the Double Layer Beam Shaping Assembly (DLBSA) design was carried out using the genetic algorithm (AG) method using MCNPX and verified using the Particle and Heavy Ion Transport code System (PHITS). The optimization resulted in four configurations up to the 21st generation capable of producing epithermal neutron beams that comply with the IAEA standards. The best four configurations are obtained by combining: (1) Al with one of the CaF2, BiF3 or PbF2 materials as moderator, (2) Pb with Pb, Ni, or Bi as a reflector, (3) Ni with FeC, or C as collimator, (4) (FeC + LiF) as fast neutron filter, Cd or B4C as thermal neutron filter. Verification of the four optimum configurations of the DLBSA model using PHITS code shows that the epithermal neutron beam produced by DLBSA has met the IAEA standards.

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“…For example, the properties of steel are dependent on their carbon content and its spatial distribution. The cross section and the resonances of the nuclear reaction help greatly to understand the structure of the materials at a micro level [6,7]. The last but not the least, the deuterated polyethylene (CD 2 ) n , is usually taken as the typical target for nuclear reactions induced by intensive lasers [8,9].…”

Section: Introductionmentioning

confidence: 99%

Yield ratio of neutrons to protons in $$^{12}$$C(d,n)$$^{13}$$N and $$^{12}$$C(d,p)$$^{13}$$C from 0.6 to 3 MeV

Zhang

et al. 2019

NUCL SCI TECH

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The neutron yield in 12 C(d,n) 13 N and the proton yield in 12 C(d, p) 13 C have been measured by deuteron beam from 0.6 MeV to 3 MeV which is delivered from a 4-MeV electro static accelerator bombarding on the thick carbon target. The neutrons are detected at 0 • , 24 • , 48 • and the protons at 135 • in the lab frame. The ratios of the neutron yield to the proton one have been calculated and can be used as an effective probe to pin down the resonances. The resonances are found at 1.4 MeV, 1.7 MeV, 2.5 MeV in 12 C(d, p) 13 C and at 1.6 MeV, 2.7 MeV in 12 C(d,n) 13 N. This method provides a way to reduce the systematic uncertainty and helps to confirm more resonances in compound nuclei.

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Study of neutron production and moderation for sulfur neutron capture therapy

Cited by 9 publications

References 17 publications

A Monte Carlo study of the Cellular Dosimetry for SNCT Comparison with MIRD S Values

A Monte Carlo study of the Cellular Dosimetry for SNCT Comparison with MIRD S Values

Optimization and Verification of Double Layer Beam Shaping Assembly (Dlbsa) for Epithermal Neutron Generation

Yield ratio of neutrons to protons in $$^{12}$$C(d,n)$$^{13}$$N and $$^{12}$$C(d,p)$$^{13}$$C from 0.6 to 3 MeV

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