Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo

Two methods of nuclear data uncertainty propagation are compared, using the same nuclear data uncertainties and criticality-safety benchmarks. The first method, based on perturbation theory uses covariance files, covariance processing and the perturbation card of MCNP. The second method makes use of a large number of MCNP calculations, all alike, but using different random nuclear data libraries, consistent with the covariance files of the first method. The consistency of the nuclear data used by both methods is checked and results for 33 criticality-safety benchmarks are presented. Relatively good agreements are found, but depending on the benchmark cases, differences due to the elastic cross-section, ν-bar, angular and energy distributions are observed.     

车载放射性废物体在线监测结果的不确定度评定

基于BECK公式建立了车载放射性废物体在线监测模型,其复杂的测量公式使得公式的求导、各影响因素之间的相关系数难以采用解析计算方法实现,导致利用不确定度传播定律进行不确定度评定存在困难。应用蒙特卡罗不确定度合成方法评价了车载放射性废物体在线监测结果的不确定度,解决了就地γ能谱测量中的不确定度评定问题。其评定流程是首先采用A、B类不确定度评定方法评价各测量参数的不确定度,然后使用蒙特卡罗不确定度合成方法对不确定度分项进行合成。结果表明,241Am测量结果的不确定度<40%(1σ),137Cs、60Co和152Eu测量结果不确定度<34%(1σ)。     

超级蒙特卡罗核计算仿真软件系统SuperMC

蒙特卡罗方法对于复杂核系统的模拟具有明显优势,然而在实际工程应用中存在巨大的挑战,如复杂结构与材料分布精准建模难度大、计算收敛速度慢、海量数据难以及时有效分析等。超级蒙特卡罗核计算仿真软件系统SuperMC设计为支持以辐射输运为核心,包含燃耗、辐射源项/剂量/生物危害、材料活化与嬗变等的综合中子学计算,支持热工水力学、结构力学、化学、生物学等多物理耦合模拟。SuperMC目前已发展了精准建模、高效计算、四维可视化等关键技术,通过2 000余个国际基准模型及实验的验证与确认,在反应堆工程等方面获得广泛应用,本文对其发展概况进行介绍。     

Nuclear heating and helium production at the inboard divertor rail for DEMO

Monte Carlo simulations were carried out for the DEMO model. Distributions of both the nuclear heating and the helium production in the area between the blanket and the divertor were calculated with the MCNP5 code for the reference case, when the DEMO geometry was not changed. Next a segment of the divertor and the lower part of the manifold were modified. Two new arrangements were studied. The simulations show that for one of the examined cases the helium production and the nuclear heating can be reduced roughly three or even four times in the investigated area. Besides the nuclear heating and the He production were estimated at the fastener (bolt head). The use of the modified divertor and a rail protecting the blanket is essential in the DEMO design.     

Benchmarking of JEFF-3.2, FENDL-3.0 and TENDL-2014 evaluated data for tungsten with 14.8 MeV neutrons

Integral experiments on tungsten slab samples were carried out on the D-T neutron source facility at China Institute of Atomic Energy.Leakage neutron spectra from the irradiated tungsten target were measured by the time-of-flight technique.Accuracy of the nuclear data for tungsten was examined by comparing the measured neutron spectra with the leakage neutron spectra simulated using the MCNP-4C code with evaluated nuclear data of the JEFF-3.2,FENDL-3.0 and TENDL-2014 libraries.The results show that the calculations with JEFF-3.2 agree well with the measurements in the whole energy range and all angles,whereas the spectra calculated with FENDL-3.0 and TENDL-2014 have some discrepancies with the experimental data.     

Benchmarking of JEFF-3.2, FENDL-3.0 and TENDL-2014 evaluated data for tungsten with 14.8 MeV neutrons

Integral experiments on tungsten slab samples were carried out on the D-T neutron source facility at China Institute of Atomic Energy.Leakage neutron spectra from the irradiated tungsten target were measured by the time-of-flight technique.Accuracy of the nuclear data for tungsten was examined by comparing the measured neutron spectra with the leakage neutron spectra simulated using the MCNP-4C code with evaluated nuclear data of the JEFF-3.2,FENDL-3.0 and TENDL-2014 libraries.The results show that the calculations with JEFF-3.2 agree well with the measurements in the whole energy range and all angles,whereas the spectra calculated with FENDL-3.0 and TENDL-2014 have some discrepancies with the experimental data.     

CARR上的应力测量中子衍射谱仪概念设计和模拟研究

中子衍射法是迄今为止可直接测量材料或工程部件内部深处应力场分布的唯一非破坏性方法，在工程上具有重要的应用。中国先进研究堆（CARR)中子散射工程拟建造一台应力测量中子衍射谱仪，其主要功能是测量材料中的残余应力和载荷应力。本文介绍了该谱仪的概念设计方案，并应用蒙特卡罗模拟软件MCSTAS对设计方案进行了模拟研究，对部分中子部件参数进行了优化设计。     

现场校准用便携式X射线照射装置的优化设计及辐射特性研究

中国原子能科学研究院计量测试部研制了一款用于校准现场固定式X、γ辐射剂量仪的便携式X射线照射装置。首先利用蒙特卡罗软件建立模型,对出射口准直光阑结构进行优化设计,随后,对所建参考辐射场射束范围、均匀性及散射辐射进行模拟计算,并利用TW32005电离室进行了实验验证。在本研究所选辐射质、管电流及参考点-焦斑距离条件下,所建立的辐射场能量范围为60～164 keV,空气比释动能率在0.08～565 mGy/h,周围剂量当量率在0.13～892 mSv/h,为后续利用便携式X射线照射装置开展现场校准技术研究奠定了基础。结果表明,经优化设计后的准直光阑在满足准直限束需求的同时有效减轻了自身重量,便携式X射线参考辐射场特性满足GB/T 12162.1—2000要求,验证了所建模型的正确性及蒙特卡罗方法用于便携式X射线参考辐射场特性研究的有效性。     

Design study of neutron flux intensity monitor between ten and several hundred keV for BNCT

Based on the activation method using ⁷¹Ga(n,γ)⁷²Ga reaction, two spherical monitors with gallium nitride (GaN) wafers as activation material were designed by Monte Carlo simulations to precisely measure the absolute integral neutron flux intensity between ten and several hundred keV. The two monitors are almost the same in shape and have an absorber/moderator/absorber/GaN arrangement from outside to inside. The differences between the two monitors are the kind of materials, the thicknesses of the absorbers and the diameter of the moderator. By making difference of the sensitivities between these two monitors, the contributions of thermal, epithermal and very high energy fast neutrons were removed completely, and constant monitor sensitivity to neutrons between ten and several hundred keV was extracted. The simulation results and related analysis indicated that the absolute integral neutron flux intensity between ten and several hundred keV could be precisely measured by the presently designed two monitors.     

Optimization of moderator assembly for neutron flux measurement: experimental and theoretical approaches

A moderator of paraffin wax assembly has been demonstrated where its thickness can be optimized to thermalize fast neutrons. The assembly is used for measuring fast neutron flux of a neutron probe at different neutron energies, using BF03(U10and 200) and3He(U0.500)neutron detectors. The paraffin wax thickness was optimized at 6 cm for the neutron probe which contains an Am–Be neutron source. The experimental data are compared with Monte Carlo simulation results using MCNP5 version 1.4. Neutron flux comparison and neutron activation techniques are used for measuring neutron flux of the neutron probe to validate the optimum paraffin moderator thickness in the assembly. The neutron fluxes are measured at(1.17 ± 0.09) 9 105 and(1.19 ± 0.1) 9 105n/s, being in agreement with the simulated values. The moderator assembly can easily be utilized for essential requirements of neutron flux measurements.     

The range of penetration and the backscattering coefficient by using both the analytic and the stochastic theoretical ways of electron slowing down in solid targets: Comparative study

The aim of this paper is to determine the best theoretical way (stochastic or analytic) to use in the study of the range of penetration and the backscattering coefficient of electron impinging in solid target, by adopting the same input in the form of collision cross-sections. For this purpose, differential elastic cross sections has been calculated by using our semi-empirical model [A. Bentabet, Z. Chaoui, A. Aydin, A. Azbouche, Vacuum 85 (2010) 156]; and that of inelastic cross sections has been calculated by using Gryzinski’s excitation function. Moreover, in stochastic case, the obtained quantities are calculated by using both Monte Carlo schemes based on continuous slowing down approximation (CSDA) and on individual electron scattering events methods.     

Ar~+/Ar,O_2~+/O_2 and N_2~+/N_2 Elastic Momentum Collision Cross Sections: Calculation and Validation Using the Semi-Classical Model

The aim of this paper is to obtain relevant sets of collision cross sections of the parent ions in low pressure discharges in argon, oxygen, and nitrogen, i.e., Ar＋ in Ar, O2＋ in O2 and N2＋ in N2. These ion data are first discussed and then validated from comparisons between the calculated transport coefficients and those measured in the literature. The elastic momentum transfer collision cross sections are determined from a semi-classical approximation for the phase shift calculation based on a 12-6-4 inter-particle potential while ion transport coefficients are determined versus the reduced electric field from Monte Carlo simulations.