Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code.

Kandiev Y; Kashaeva E; Malyshkin G; Bayanov B; Taskaev S

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Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code.

机译：通过PRIZMA代码通过中子和伽马输运的蒙特卡罗数值模拟，优化了加速器驱动的中子源的目标。

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At Budker Institute of Nuclear Physics, epithermal neutron source for neutron-capture therapy was built and neutron generation was realized. Source is based on tandem accelerator and uses near-threshold neutron generation from the reaction (7)Li(p,n)(7)Be. The paper describes target optimization through the numerical simulation of proton, neutron and gamma transport by Monte Carlo method (PRIZMA code). It is shown that the near-threshold mode attractive due low activation provides high efficiency of the dose and acceptable therapeutic ratio and advantage depth.

机译：在Budker核物理研究所，建立了用于中子俘获治疗的超热中子源，并实现了中子产生。源基于串联加速器，并使用从反应（7）Li（p，n）（7）Be产生的近阈值中子。本文通过蒙特卡罗方法（PRIZMA代码）对质子，中子和伽马输运进行数值模拟，描述了目标优化。已经表明，由于低活化而具有接近阈值模式的吸引力提供了高剂量效率以及可接受的治疗比率和优势深度。

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《Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine》 |2011年第12期|共3页
作者
Kandiev Y; Kashaeva E; Malyshkin G; Bayanov B; Taskaev S;
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正文语种 eng
中图分类原子核物理学、高能物理学;
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1. Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code. [J] . Kandiev Y, Kashaeva E, Malyshkin G, Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine . 2011,第12期

机译：通过PRIZMA代码通过中子和伽马输运的蒙特卡罗数值模拟，优化了加速器驱动的中子源的目标。
2. Neutronics studies of solid targets for spallation neutron source using Monte Carlo simulation [J] . Yin Wen, Liang Jiu-Qing Chinese physics . 2003,第6期

机译：利用蒙特卡洛模拟对散裂中子源固体靶的中子学研究
3. Neutronics studies of solid targets for spallation neutron source using Monte Carlo simulation [J] . Yin Wen, Liang Jiu-Qing Chinese physics . 2003,第6期

机译：使用蒙特卡洛模拟对散裂中子源固体目标进行中子学研究
4. CALCULATION AND USE OF MULTIGROUP CROSS SECTIONS INCLUDING ELECTRON-PHOTON CASCADE FOR A 3D MONTE CARLO NEUTRON-GAMMA TRANSPORT CODE. COMPARISONS WITH MCNP-4B. [C] . David RIZ ANS international topical meeting on advances in reactor physics and mathematics and computation into the next millennium (PHYSOR 2000) . 2000

机译：多组横截面的计算和使用，包括3D蒙特卡洛中子-伽马运输代码的电子光子梯级。与MCNP-4B的比较。
5. Neutron flux and energy characterization of a plutonium-beryllium isotopic neutron source by monte carlo simulation with verification by neutron activation analysis. [D] . Harvey, Zachary R. 2010

机译：mon-铍同位素中子源的中子通量和能量表征，通过蒙特卡罗模拟并通过中子活化分析进行验证。
6. Production of neutrons in laminated barriers of radiotherapy rooms: comparison between the analytical methodology and Monte Carlo simulations [O] . Gabriel Fonseca da Silva Rezende, Luiz Antonio Ribeiro da Rosa, Alessandro Facure 2014

机译：放射治疗室层压屏障中的中子产生：分析方法和蒙特卡洛模拟之间的比较
7. MORSE CODE: A MULTIGROUP NEUTRON AND GAMMA-RAY MONTE CARLO TRANSPORT CODE. [O] . Straker, E.A., Stevens, P.N., Irving, D.C., 1970

机译：mORsE CODE：多重中子和Gamma-RaY蒙特卡洛运输代码。

Optimization of the target of an accelerator-driven neutron source through Monte Carlo numerical simulation of neutron and gamma transport by the PRIZMA code.

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