Neutronics of Rectangular Parallelepiped Polyethylene Moderator in Wing Geometry for Accelerator Based Thermal Neutron Source

Numerical and experimental studies of the wing geometry moderator are performed in order to examine (a) the effects of the target position and the moderator thickness on the beam intensity and on the pulse shapes emitted from a polyethylene thermal moderator, and (b) the optimum thickness of the moderator.

The beam intensity emitted from the moderator is expressed by an integration of the product of the source neutron distribution and the beam intensity produced by a unit intensity point source in the moderator. By applying this expression mechanism is analyzed for the optimum target position and the saturation phenomena of the intensity and the pulse width emitted from the moderator. The optimum target position is at about 2 cm from the neutron emission surface for moderators thicker than 4 cm and at about half of the moderator thickness for thinner ones. The intensity and the pulse shapes emitted from the moderator vary little if the target distance is varied around the optimum one and become close to the saturated ones at about 8 cm thickness. It is indicated by the analysis of figures of merit that a moderator of 4~6 cm thickness is optimum.     

Neutronics of Polyethylene Thermal Moderator of Wing and Slab Geometries on Pulsed Neutron Source

Pulse width and intensity of thermal neutrons emitted from a polyethylene moderator on a pulsed neutron source are compared in two geometries of a moderator and target, namely, slab (radial type) and wing geometries (tangential type).

The pulse width for a 10cm thick moderator of the wing geometry, at which thickness saturated beam intensity is achieved, corresponds nearly to that of a 4 cm thick moderator of the slab geometry, although the maximum beam intensity for the wing geometry is some-what less than that of slab geometry. Analysis of figures of merit indicates that the wing geometry can be adopted in scattering experiments which require neutron beams that are not contaminated much by other radiations, even if it causes slight deterioration of neutronic characteristics in comparison with the slab geometry.     

Pulsed Neutron Intensity from Rectangular Shaped Light Water Moderator with Fast-Neutron Reflector

With a view to enhancing the thermal-neutron intensity obtained from a pulsed neutron source, an experimental study has been made to determine the optimum size of a rectangular shaped light water moderator provided with fast neutron reflector of beryllium oxide or graphite, and decoupled thermal-neutronically by means of Cd sheet. The optimum dimensions for the moderator are derived for the neutron emission surface and the thickness, for the cases in which the neutron-producing target is placed beneath the moderator (“wing geometry”) or immediately behind the moderator (“slab geometry”). The major conclusions drawn from the experimental results are as follows. The presence of the Cd decoupler inserted between the moderator and reflector prevent the enhancement of thermal-neutron emission time gained by the provision of reflector. with a graphite reflector about 14 cm thick, (a) the optimum area of emission surface would be 25x25 cm² for wing geometry and still larger for slab geometry, and (b) the optimum moderator thickness would be 5.5 cm for slab geometry and 8.5 cm for wing geometry. It is thus concluded that a higher neutron emission intensity can be obtained with slab than with wing geometry provided that a large emission surface can be adopted for the moderator.     

Comparison between Pulsed Cold Neutron Intensities from Liquid Hydrogen Moderator and from Solid Methane Moderator in Decoupling Type Moderator Assembly

Although liquid hydrogen is at present a unique cold moderator applicable to high intensity neutron sources, the reported pulsed cold neutron intensity from a liquid hydrogen moderator is significantly lower than that from a solid methane moderator. In this report, a reflected assembly with a thick hydrogen moderator is used to enhance the pulsed cold neutron intensity and the intensity is compared with that from a solid methane moderator. For comparison, 5 and 15 cm thick moderators were used for liquid hydrogen moderators. The thicker one was used to obtain the saturated intensity of pulsed cold neutrons. The thickness of a solid methane was 5 cm.

The cold neutron intensity from the 15 cm thick hydrogen moderator is about 1.6 times as high as that from the 5 cm one, in the case of the graphite reflected moderator assembly with a Cd decoupler. However, even in the case of the reflected assembly, the cold neutron intensities from the liquid hydrogen moderators are much less than that from the solid methane moderator; intensity ratios of the cold neutrons emitted from the hydrogen moderator to the solid methane one are about 36% for the thin hydrogen moderator and about 56% for the thick one. These results show that although the thick hydrogen moderator should be used to increase the pulsed cold neutron intensity, the pulsed cold neutron intensity from the liquid hydrogen moderator cannot be increased up to that from the solid methane moderator regardless of the use of a reflector, only by thickening the moderator.     

Effects of Reflector on Intensity of Thermal Neutrons Emitted from Moderator for Pulsed Neutron Source

Intensity of the thermal neutrons emitted from the moderator with a reflector was calculated to study the effects on the intensity caused by a macroscopic total neutron cross section and an average logarithmic energy loss of the reflector materials.

A reflector with a large macroscopic total neutron cross section produced higher thermal neutron intensity than that with a small cross section if they had the same average logarithmic energy loss. Among the reflectors with the same total macroscopic neutron cross section, the thermal neutron intensity was not changed by decreasing the average logarithmic energy loss to a range less than about 0.1 but above this value the intensity was weakened. From this result it was found that a large macroscopic total cross section and a small average logarithmic energy loss are preferable characteristics for reflector materials.

As actual reflector materials, three reflector materials were examined, namely beryllium, graphite and lead, which are now considered to be candidates. The lead reflector was effective for the moderator with a large emission-surface and the beryllium reflector for the moderator with a small one. This result indicates that the moderator size is important for choosing the best reflector material to produce the highest beam intensity.     

Measurements of neutronic characteristics of rectangular and cylindrical coupled hydrogen moderators

Extensive simulation calculations were performed in the design studies of the coupled hydrogen moderator for the pulsed spallation neutron source of the Japan Proton Accelerator Research Facility (J-PARC). It was indicated that a para-hydrogen moderator had an intensity-enhanced region at the fringe part, and that pulse shapes emitted from a cylindrical para-hydrogen moderator gave higher pulse-peak intensities with narrower pulse widths than those from a rectangular one without penalizing the time-integrated intensities. To validate the peculiar distribution and advantages in pulse shapes experimentally, some measurements were performed at the neutron source of the Hokkaido University electron linear accelerator facility. It was observed that the neutron intensity was enhanced at edges of the para-hydrogen moderators, whereas it decreased at the same part of the ortho-rich-hydrogen moderator, where the dimension of those moderators was 50 mm in thickness and 120 mm in width and height. The spatial distribution and pulse shapes were also measured for a cylindrical coupled para-hydrogen moderator that has the same dimensions as for the coupled moderator employed for J-PARC. The measured results from the cylindrical moderator were consistent with the results obtained in the design studies for the moderator for J-PARC.     

Considerations for a cold moderator on a pulsed neutron source

The purpose of a cooled moderator on a pulsed neutron source may be to extend to longer wavelengths the neutron slowing down range with its narrow pulse widths, or to enhance the long wavelength intensity. The intensity and pulse length as a function of wavelength are determined by the rate of energy exchange, and by leakage and capture of neutrons. Energy deposition and radiation damage present serious problems, and restrict the choice of moderators. Radiation damage, in particular, may limit the lifetime and stability of the moderator, giving rise to problems of corrosion and, in the case of solid moderators, stored energy release. The advantages of solid ammonia are its high hydrogen atom density, and its thermal neutron absorption cross-section which allows the moderator to act as its own homogeneous poison. On the other hand this impairs its use for cold neutron production in those instances where neutron intensity rather than burst width is important. In such cases solid methane is favourable, though the radiation damage problem for methane at high intensity sources is severe, and liquid hydrogen is indicated.     

在线中子活化分析系统关键参数的蒙特卡罗模拟

针对在线瞬发γ中子活化分析（PGNAA）系统的要求,利用MCNP程序对不同慢化材料（重水、石蜡、聚乙烯等）厚度、铅屏蔽厚度、样品厚度及大小进行模拟计算分析。计算结果表明,以厚9cm的石蜡作慢化材料,厚2cm的铅作γ屏蔽层,厚7cm、半径10cm的硫、钙和水泥类样品为最优设计方案,从而为实际设计在线PGNAA系统提供了科学依据。     

强流加速器D-Be中子源中子慢化引出研究

为优化成像中子束注量率和能谱,在考虑中子源能谱、角分布、面源结构及靶系统条件下,利用MCNP程序模拟源中子的慢化和输运过程,记录不同模型时慢化体内热中子注量率分布和成像中子束成分。结果表明,聚乙烯更适合用作小型热中子源慢化反射材料;D+束轰击靶面的束斑大小影响热中子在慢化体内的分布,束斑半径在1cm内变化对中子慢化影响较小;增加热中子引出孔道与D+束轴线的夹角能有效提高引出热中子束的纯度。     

Neutron Spectrum in Small Iron Pile Surrounded by Lead Reflector

In order to save the quantity of sample material, a possibility to assess group constants of a reactor material through measurement and analysis of neutron spectrum in a small sample pile surrounded by a reflector of heavy moderator, was investigated. As the sample and the reflector, we chose iron and lead, respectively. Although the time dispersion in moderation of neutrons was considerably prolonged by the lead reflector, this hardly interferes with the assessment of group constants. Theoretical calculation revealed that both the neutron flux spectrum and the sensitivity coefficient of group constants in an iron sphere, 35 cm in diameter surrounded by the lead reflector, 25 cm thick, were close to those of the bare iron sphere, 108 cm in diameter.

The neutron spectra in a small iron pile surrounded by a lead reflector were experimentally obtained by the time-of-flight method with an electron linear accelerator and the result was compared with the predicted values.

It could be confirmed that a small sample pile surrounded by a reflector, such as lead, was as useful as a much larger bulk pile for the assessment of group constants of a reactor material.     

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.     

Neutronics analysis of the target-moderator–reflector (TMR) configuration for compact long pulsed neutron sources

The compact pulsed neutron source can play an important role in the research, education, user training, and development of the advanced neutron scattering instruments. The materials for the target, moderator, reflector (TMR) and their configurations must be optimized to get the optimal yield of neutrons with energy in the range of 0.001–0.1 eV order. Several kinds of materials of the TMR, their configurations, and their dimensions are investigated by the Monte Carlo simulation and optimized for developing the compact pulsed neutron source. The results would contribute to the construction of the Compact Pulsed Hadron Source (CPHS) at Tsinghua University, China.     

利用MOCA程序模拟PGNAA技术探测地雷的方法

利用MOCA程序设计地雷探测装置，并模拟瞬发γ中子活化分析（prompt gamma neutron activation analysis, PGNAA）技术探测地雷过程。采用东北师范大学NG-9型中子发生器为中子源，研究其内部绝缘材料（聚酰亚胺等）对中子能量分布的影响。在此基础上设计并优化装置，确定钨、碳化钨、钨+含硼聚乙烯+铅组合，分别作为慢化体、反射体与屏蔽体。相比单能中子源分布情况，慢化体、反射体、屏蔽体厚度降低。使用硅酸钇镥（lutetium yttrium oxyortho silicate, LYSO）探测器探测埋藏于含水量5%的土壤中、不同深度下地雷产生的伽玛射线。对氢、碳、氮、氧元素进行分析，定性确定了反坦克、步兵地雷的有效探测深度，结果表明，设计的装置具有可行性，可利用该装置进行实际PGNAA测试研究。     

蒙特卡罗方法在中子活化在线分析系统设计中的应用

选取重水、石墨、聚乙烯等6种慢化材料，利用MCNP程序对不同的慢化材料进行模拟计算分析。计算结果表明，中子活化在线分析系统的最优化慢化材料为聚乙烯。实验测定了以聚乙烯为慢化材料的中子活化分析系统的热中子注量率随源到引出孔之间的距离以及探测器处于不同位置时的分布关系，为下一步进行中子活化在线分析研究提供了依据。     

Neutron spectrum change with thermal moderator temperature in a compact electron accelerator-driven neutron source and its effects on spectroscopic neutron transmission imaging

Recently, Compact Accelerator-driven Neutron Sources (CANSs) are attracting attention. In CANSs, a simple thermal neutron moderator such as polyethylene is often used from the viewpoints of cost, simplicity and maintainability. In most cases, the temperature of such a moderator has not been controlled although it is natural that the moderator temperature and the neutron spectrum will change with accelerator-operation. Thus, we simultaneously measured neutron spectra and the temperature of a polyethylene moderator at the Hokkaido University Neutron Source (HUNS) driven by a compact electron accelerator to observe the effect of any temperature change on the reliability of spectroscopic transmission measurement. The ratio of the neutron effective temperature and the moderator temperature was constant in HUNS case, although both increased by 4–5 K within one hour after the start of accelerator-operation. This indicated that the neutron effective temperature was well estimated by the moderator temperature. The effect of the temperature change can be easily avoided by excluding data collection before the moderator warms up. These results suggested that the monitoring of moderator temperature is recommended in compact electron accelerator-driven neutron sources with a thermal neutron moderator to guarantee reliability of spectroscopic transmission measurement without sacrifices of cost, simplicity and maintainability.     

Effects of Spatial Harmonics on Thermal Neutron Spectra Measured by Time-of-Flight Method

Spatial effect—the variations in space of transient neutron flux noted in pulsed neutron experiments, and which is ascribable to the occurrence in moderator of spatial harmonics—is studied on the measured flight time spectra of neutrons reentering the atmosphere from parametrically varied depths of a graphite moderator. Measurements were made using moderator slabs of two different axial lengths, to examine the influence of differences in moderator size on the spatial effect. The master equation representing the scalar neutron flux as function of time and energy is solved by a semi-analytic method that takes account of spatial harmonics. Simulation of the solution thus obtained of the master equation proved to reproduce the measured flight time spectra with good accuracy. It was indicated that the spatial effect on the thermal neutron spectrum is stronger with a larger than with a smaller moderator slab. The neutron temperature in graphite moderator was calculated by formula fitted in Maxwellian distribution to the peaks of the thermal neutron spectra. It was indicated that in a graphite moderator of 120 cm axial length, spatial harmonics caused a variation of more than 40 K in neutron temperature between depths in moderator differing by 30 cm.     

TOPAZ-Ⅱ系统启动过程模拟

对前苏联热离子反应堆电源系统TOPAZ-Ⅱ进行相应的简化,分别建立了堆芯热工水力模型、中子物理学模型以及热排放系统模型。冷却剂回路采用一维热工水力模型,堆芯导热及翅片辐射导热计算采用二维分析模型。选用6组缓发中子点堆模型,考虑了二氧化铀燃料、热离子发电电极、慢化剂与反射层的温度反馈以及控制转鼓对反应性的控制,计算得到TOPAZ-Ⅱ在正常启动工况下的各处温度、功率、反应性反馈等参数的变化。计算结果与TITAM程序的计算结果符合较好,同时本程序可对启动过程进行更为精细的分析,可为控制系统的设计提供参考。     

Moderator poison design and burn-up calculations at the SNS

The spallation neutron source (SNS) at Oak Ridge National Laboratory was commissioned in April 2006. At the nominal operating power (1.4 MW), it will have thermal neutron fluxes approximately an order of magnitude greater than any existing pulsed spallation source. It thus brings a serious challenge to the lifetime of the moderator poison sheets. The SNS moderators are integrated with the inner reflector plug (IRP) at a cost of ∼$2 million a piece. A replacement of the inner reflector plug presents a significant drawback to the facility due to the activation and the operation cost. Although there are a lot of factors limiting the lifetime of the inner reflector plug, like radiation damage to the structural material and helium production of beryllium, the bottle-neck is the lifetime of the moderator poison sheets. Increasing the thickness of the poison sheet extends the lifetime but would sacrifice the neutronic performance of the moderators. A compromise is accepted at the current SNS target system which uses thick Gd poison sheets at a projected lifetime of 6 MW-years of operation. The calculations in this paper reveal that Cd may be a better poison material from the perspective of lifetime and neutronic performance. In replacing Gd, the inner reflector plug could reach a lifetime of 8 MW-years with ∼5% higher peak neutron fluxes at almost no loss of energy resolution.     

The optimization of longitudinal convective fins with internal heat generation

The solution of the optimization problem for longitudinal convective fins of constant thickness, triangular or parabolic profile, and uniform internal heat generation, is presented. The cases considered are those of a given heat generation density, total heat generation, and heat generation per unit width of the fin, when either the heat dissipation or the width of the fin is prescribed. The results are set forth in a nondimensional form, which are presented graphically. The effect of the fin's thermal conductivity upon the optimum dimensions is discussed, and limiting values for the heat generation and the heat dissipation, which may be imposed on the fin for a feasible optimization, are also obtained.     

Neutron generator for the array borehole logging

The performance mechanism of the array neutron generator to be used to porosity logging is presented.The neutron generator utilizes a drive-in target ceramic neutron tube,which cursts nerutron with fast-slow period selectively pressure.Regulation of the neutron tube is accomplished by pulse width modulation.The high voltage power supply is poerated at optimum frequency.