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HIGH-FIDELITY MCNP MODELING OF A D-T NEUTRON GENERATOR FOR ACTIVE INTERROGATION OF SPECIAL NUCLEAR MATERIAL

机译:用于特殊核材料主动询问的D-T中子发生器的高精度MCNP建模

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Fast and robust methods for interrogation of special nuclear material (SNM) are of interest to manyagencies and institutions in the United States. It is well known that passive interrogation methodsare typically sufficient for plutonium identification because of a relatively high neutron productionrate from 240Pu [1]. On the other hand, identification of shielded uranium requires active methodsusing neutron or photon sources [2]. D-D (2.45 MeV) and D-T (14.1 MeV) neutron-generatorsources have been previously tested and proved to be relatively reliable instruments for activeinterrogation of nuclear materials [3, 4]. In addition, the newest generators of this type are smallenough for applications requiring portable interrogation systems.Active interrogation techniques using high-energy neutrons are being investigated as a method todetect hidden SNM in shielded containers [4]. Due to the thickness of some containers, penetratingradiation such as high-energy neutrons can provide a potential means of probing shielded SNM. Inan effort to develop the capability to assess the signal seen from various forms of shielded nuclearmaterials, the University of Michigan Neutron Science Laboratory’s D-T neutron generator and itsshielding were accurately modeled in MCNP. The generator, while operating at nominal power,produces approximately 1 × 10~(10) neutrons/s, a source intensity which requires a large amount ofshielding to minimize the dose rates around the generator. For this reason the existing shieldingcompletely encompasses the generator and does not include beam ports. Therefore, several MCNPsimulations were performed to estimate the yield of uncollided 14.1-MeV neutrons from thegenerator for active interrogation experiments and to determine the expected dose with a port in thebiological shielding. Beam port diameters of 5, 10, 15, 20, and 25 cm were modeled to assess theresulting neutron fluxes and doses were calculated for a 10-cm port. The neutron flux outside thebeam ports was estimated to be approximately 2 × 10~4 n/cm~2-s and the dose rate in the same regionexceeded 1 rem/hr.
机译:快速而可靠的讯问特殊核材料(SNM)的方法受到许多人的关注 美国的代理机构。众所周知,被动审讯方法 由于中子产量较高,通常足以用于typically的鉴定 速率从240Pu [1]开始。另一方面,鉴定屏蔽铀需要积极的方法 使用中子或光子源[2]。 D-D(2.45 MeV)和D-T(14.1 MeV)中子发生器 来源已经过测试,并被证明是相对可靠的有源仪器 核材料的审讯[3,4]。此外,这种类型的最新发电机很小 对于需要便携式询问系统的应用来说足够了。 使用高能中子的主动询问技术正在研究中 在屏蔽容器中检测隐藏的SNM [4]。由于某些容器的厚度,会穿透 辐射(例如高能中子)可以提供探测屏蔽SNM的潜在手段。在 努力发展评估从各种形式的屏蔽核中看到的信号的能力 材料,密歇根大学中子科学实验室的D-T中子发生器及其 屏蔽已在MCNP中精确建模。发电机以标称功率运行时, 产生大约1×10〜(10)中子/ s,这是需要大量的中子强度的源强度 屏蔽以最小化发生器周围的剂量率。因此,现有的屏蔽 完全包含发生器,不包括光束端口。因此,几种MCNP 进行了模拟,以估算非碰撞的14.1MeV中子的收率。 生成器进行主动询问实验,并通过端口中的端口确定预期剂量 生物屏蔽。对5、10、15、20和25 cm的光束端口直径进行建模以评估 计算出10厘米端口的中子通量和剂量。外部的中子通量 光束端口估计约为2×10〜4 n / cm〜2-s,并且在相同区域的剂量率 超过1 rem / hr。

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