中子学积分实验

从６０年代开始，我所就开展了聚变中子积分实验，完成了造氚率、裂变率、穿透率及泄漏中子能谱测量等研究课题。１９８７年以来承担了“８６３”计划的聚变裂变混合堆包层中子学积分实验，开展了Ｂｅ、Ｐｂ的１４ＭｅＶ中子倍增率实验，其中Ｂｅ实验为中、美、日国际合作，实验误差为２．８％，实验结果为理论计算提供积分检验。     

用于中子测量的俘获探测器研究

为了在弱中子场和有限小空间内测量绝对裂变率, 制作了俘获探测器, 研究了俘获探测器的性能。 介绍了用于中子测量的俘获探测器和铅屏蔽室, 以及该探测器系统在特定条件下测量裂变反应率的结果, 并与裂变室测量结果进行了比较。 探讨了铅屏蔽室大小对测量结果的影响。 To detect the absolute neutron flux in a weak neutron field and restricted space, the fission fragment trapping detector was fabricated and the properties of the detector were studied. In this paper, the detector and shielding chamber used in neutron detection were described and the experimental measurements of the fission rate in specific condition were performed with the detection system and the result has been compared with that obtained by fission chamber. The influence of the shielding chamber on the measured results was analyzed.     

300＃堆在线产氚回路及其应用

本文介绍了３００~＃堆在线产氚回路的组成及其主要指标、回路运行和释氚实验概况,阐明了在线产氚回路在聚变裂变混合堆包层产氚研究中的应用和前景． An in-pile tritium production apparatus in SPRR-300 and its main charactersare introduced. The operation of the apparatus and the tritium release experiments arebriefly described. The utilization of the apparatus in tritium production study of fusionfission hybrid reactor blanket and its future are reviewed.     

11B快中子非弹性散射的理论计算

本文采用直接作用模型和扭曲波玻恩近似（ＤＷＢＡ）理论,计算了１１Ｂ的２．１４ＭｅＶ激发态在入射中子能量为７:５４～２０．０ＭｅＶ的非弹性散射的积分截面和角分布,计算结果与评价的实验值进行了比较,符合较好．对实验上所缺乏的数据作出了理论预期值． BY using the direct reaction mode and the DWBA theory, We calculate the integrated sections and angular distributions of inelastic neutron scattering of 11B(n, n )11B 2. 14MeV excited state in energy range from 7. 54MeV to 20. 0MeV. The calculated results are comparaed with the experimental values, and a good agreement has been obtained. The theory values are given for absent experimental data.     

235,238U核数据的快中子基准实验积分检验

用四个快中子基准实验检验了ＥＮＤＦ／Ｂ－ＶＩ、ＪＥＮＤＬ－３和ＣＥＮＤＬ－２三个评价核数据库中的２３５Ｕ和２３８Ｕ等数据．计算结果指出，ＥＮＤＦ／Ｂ－ＶＩ库的数据对快中子积分实验的预言更准确． Four fast benchmark experiments have been used to the data of 235,238U in testEndf/B-VI,JENDL-3 and CENDL-2 nuclear date libraries...     

中子散射对快中子照相质量影响的分析

通过一内空的圆柱体模型，对在快中子照相时由样品引起的散射中子强度与样品形状和探测距离之间的关系进行模拟，并用^241Am—Be作中子源对散射中子的影响进行实验验证。结果表明，在快中子照相时，由样品引起的散射中子的强度与探测距离以及样品形状有关。对于同一样品，探测距离增加，散射中子的影响则降低。The relationships between intensities of scattered neutrons by specimens and their shapes and detecting distances have been simulated using a hollow cylinder model, and the results were validated by experiments of fast neutron imaging using ^241Am-Be neutron source. The results showed that the intensities of scattered neutrons are closely related to the detecting distances and sample＇ s shapes. The influences of scattered neutronns in fast neutron imaging will be reduced while detecting distances increased.     

BC501A中子探测器的能量刻度及其在聚乙烯中子学积分实验中的应用

利用标准放射伽玛源（22Na,137Cs）测量了尺寸为Φ5.08 cm×2.54 cm的BC501A中子探测器的脉冲幅度谱,并利用MCNP软件进行了模拟,详细考虑了探测器的几何尺寸、材料、以及能量分辨函数,计算结果很好地再现了实验数据,精确地确定了康普顿边缘的位置,完成了BC501A中子探测器的能量刻度。并采用14.8 MeV的T（d,n）4He中子源对聚乙烯样品开展了中子学积分实验,结果表明,BC501 A中子探测器的能量刻度过程以及聚乙烯中子学积分实验数据的处理过程是完全合理并且可靠的。The pulse-height spectra of the BC501A scintillator (Φ5.08 cm×2.54 cm) were measured using 22Na, 137Cs γ-ray source, in which MCNP simulation was applied. The simulated pulse-height spectra show a good agreement with the measured data considering the geometry, material and energy resolution function of the scintillator. The position of the Compton edge has been precisely determined and an accurate energy calibration of BC501A scintillator was also achieved. An neutronics integral experiment of polythene with 14.8 MeV T(d, n)4He neutron source was carried out. The results indicate that the procedures of the energy calibration experiment of BC501A scintillator and the data analyzing in the polythene integral experiment are reasonable and reliable.     

A New Approach of Quantum Mechanics for Neutron Single-Slit Diffraction

Phenomena of electron, neutron, atomic and molecular diffraction have been studied in many experiments, and these experiments are explained by many theoretical works. We study neutron single-slit diffraction with a quantum mechanical approach. It is found that the obvious diffraction patterns can be obtained when the single- slit width a is in the range of 3λ - 60λ. We also lind a new quantum effect of the thickness of single-slit which can make a large impact on the diffraction pattern. The new quantum effect predicted in our work can be tested by the neutron single-slit diffraction experiment.     

加速器驱动次临界系统中堆外中子注量率监测方法（英文）

在加速器驱动的次临界（ADS）系统中,次临界反应堆的功率控制是通过控制束流强度来实现。监测堆外中子注量率,不仅提供了反应堆功率指示,也为反应堆保护系统在启动和运行阶段提供了重要的监测信息,因此,堆外中子注量率的监测在ADS系统的控制与保护中起着非常重要的作用。采用3套裂变室和3套非补偿电离室来监测ADS堆外中子注量率。由于裂变室有脉冲、电流和均方电压3种操作模式,1套裂变室可以监测源量程、中间量程和功率量程等宽范围的反应堆功率。所以,使用的监测方法有3个优点,即:增加了监测通道的冗余度,提高了保护系统的可靠性,以及能提供更多的轴向功率分布信息。由于这些中子探测器对中子能谱很敏感,提出了一种有效的校准方法,即先用一个标准的中子源校准这些中子探测器,然后再将中子注量率除以一个修正因素。基于Geant4仿真结果显示,所提取的裂变室和非补偿电离室的修正因素分别为5和42。In an accelerator driven sub-critical (ADS) system, power control in sub-critical reactor is achieved through the control of the beam current. Excore neutron flux monitoring in an ADS system, not only provides indication of reactor power, but also provides important inputs to reactor protection system during startup and power operation, and thus plays a very important role in the control and protection of ADS system. This paper presents the excore neutron flux monitoring method which uses three fission chambers (FCs) and three uncompensated ion chambers (UICs). With three operation modes, pulse mode, current mode, and mean square voltage mode, an FC can monitor reactor power over a wide range from the source range to the intermediate and power ranges. The proposed monitoring method increases the redundancy of independent monitoring channels, improves the reliability of the protection system, and provides more information on axial power distribution. Since these neutron detectors are sensitive to the neutron energy spectrum, we propose an effective calibration method to provide the exact value of neutron flux, i.e., these neutron detectors are calibrated with a standardized neutron source, and then, a correction factor is added in the calibration by comparing the neutron energy spectrum of the neutron source with that in ADS system. Based on Geant4 simulation, the correction factors of 5 and 42 are extracted for FCs and UICs, respectively.     

Thermal hydraulic and mechanical analysis of CH HCSB TBM

1 Introduction According to the proposed structure design, the neutronics analyses of the CH HCSB TBM in ITER D-T phase have been given [1]. Based on the heat loads conditions of the test blanket module and the results of neutronics calculation during ITE…     

均匀化模型对CFETR氦冷包层中子学影响研究

在CFETR氦冷固态包层及球床结构的最新概念设计方案中,基于均匀化模型、仅球床均匀化模型与高保真模型分别进行了中子学计算分析.研究了结构均匀化及球床空间自屏效应对包层中子学影响以及小球尺寸对氚增殖比的影响.结果表明,(1)结构均匀化模型对氦冷包层中子学影响较小;(2)随着小球直径的减少,球床空间自屏效应堆氚增殖比的影响...     

ITER ƫ�������Ѷ�̽�����������ƽ�չ

基于中国ITER氦冷固态增殖剂试验包层(CHHCSBTBM)3×3模块化结构设计,借助一维中子输运计算程序ONEDANT和二维中子输运计算程序TWODANT,对ITER实验包层模块(TBM)设计的中子学问题进行计算。计算出产氚增殖比以及不同材料区的功率密度、中子通量分布和产氚增殖率,并对计算结果进行分析比较。     

��배����о۱��������ϵͳ�ĸ�����ƺͼ���

根据第一壁后聚变中子通量和能谱的空间分布和 ITER 可能输出的聚变功率、聚变中子产额、第一壁(产氚包层)之后的中子通量的蒙塔-卡罗中子输运(MCNP)计算,对氦冷却固体增殖剂中子学和产氚包层模块(NT-TBM-HCSB)的聚变中子诊断提出概念性设计,本设计提出用固定位置微型裂变室探测器和可移动封装薄箔活化分析系统测量中子倍增器之后、固体氚增殖剂中及其后的中子通量;用可移动天然金刚石探测器的紧凑型能谱仪测量中子能谱。     

热中子分析探雷的中子源慢化装置设计与优化

与传统的地雷探测技术相比,热中子分析(Thermal Neutron Analysis,简称TNA) 探雷技术具有准确率高、虚警率低和对环境适应性强的特点,但探测速度较慢,制约了其广泛应用。为了提高地雷位置处的慢热中子通量,缩短探测时间,提出了一种基于252Cf 的中子源慢化装置设计构型,主要包含中子慢化层、中子反射层、本底 屏蔽层和侧向中子吸收层4 个部分。采用数值模拟的方法比较了4种常用中子慢化(反射) 材料的性能,优选高密度聚乙烯作为慢化材料,石墨作为反射材料。同时,为了满足辐射安全要求,对屏蔽材料的结构进行了优化计算。按照设计构型搭建了TNA 探雷实验平台。在104 n/s 中子源强下优化了慢化层和反射层的厚度,测试了装置慢化效能,在107 n/s 中子源强下评估了装置辐射安全性能。结果表明,采用该装置可使地雷位置处的慢热中子通量提升11 倍以上,并能有效保障辐射安全。Compared with the traditional landmine detection methods, Thermal Neutron Analysis (TNA) landmine detection has the advantages of high accuracy, low false alarm rate and strong adaptability to the environmental change.But the long detection time restrict the wide application of this technology. In order to shorten the detection time, one possible design of neutron moderation device based on 252Cf neutron source is proposed to enhance the moderated neutronflux in mine position. The device consists of four parts, the neutron moderator, the neutron reflector, the background shield and the useless neutron absorbing layer. Then, the performance of four widely used materials in neutronics was compared with MCNP5 code, and HDPE was chosen as the neutron moderator material, graphite as the neutron reflector material. The thickness of the useless neutron absorbing layer was optimized at the same time. Finally, an experimental platform of 252Cf neutron moderation device was assembled on the basis of simulation results, and a series of experiments were carried out to optimize the geometric dimensions and evaluate the dose equivalent with two different strengths neutron source, 104 and 107 n/s. The results indicate that this device can effectively enhance the thermal neutron flux at mine position by more than 11 times and ensure the radiation safety.     

CFETRˮ���մɰ�������ѧ����ģ�������������

针对中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂包层(WCCB)基本方案,进行了中子学试验模块初步设计与分析.试验模块由3个氚增殖区、2个中子倍增区、3个冷却板以及第一壁、钨保护层、背板组成,并在试验模块中放置碳酸锂探测器进行氚测量.通过MCNP输运程序和IAEA发布的聚变评价核数据库FENDEL-2.1对试验模块中子学性能进行评估,获得了试验模块各区域的中子能谱以及氚产生率(TPR)值;各个区域中子径向通量以及由中子能谱所得到的边缘效应,表明内部区域能谱最能代表原包层的中子能谱;加反射层能提高试验模块的TPR值,综合考虑能谱,TPR以及经济等因素,加钢反射层是较好的选择.     

Calibration of ITER Instant Power Neutron Monitors: Recommended Scenario of Experiments at the Reactor

Instant power is a key parameter of the ITER. Its monitoring with an accuracy of a few percent is an urgent and challenging aspect of neutron diagnostics. In a series of works published in Problems of Atomic Science and Technology, Series: Thermonuclear Fusion under a common title, the step-by-step neutronics analysis was given to substantiate a calibration technique for the DT and DD modes of the ITER. A Gauss quadrature scheme, optimal for processing “expensive” experiments, is used for numerical integration of ²³⁵U and ²³⁸U detector responses to the point sources of 14-MeV neutrons. This approach allows controlling the integration accuracy in relation to the number of coordinate mesh points and thus minimizing the number of irradiations at the given uncertainty of the full monitor response. In the previous works, responses of the divertor and blanket monitors to the isotropic point sources of DT and DD neutrons in the plasma profile and to the models of real sources were calculated within the ITER model using the MCNP code. The neutronics analyses have allowed formulating the basic principles of calibration that are optimal for having the maximum accuracy at the minimum duration of in situ experiments at the reactor. In this work, scenarios of the preliminary and basic experimental ITER runs are suggested on the basis of those principles. It is proposed to calibrate the monitors only with DT neutrons and use correction factors to the DT mode calibration for the DD mode. It is reasonable to perform full calibration only with ²³⁵U chambers and calibrate ²³⁸U chambers by responses of the ²³⁵U chambers during reactor operation (cross-calibration). The divertor monitor can be calibrated using both direct measurement of responses at the Gauss positions of a point source and simplified techniques based on the concepts of equivalent ring sources and inverse response distributions, which will considerably reduce the amount of measurements. It is shown that the monitor based on the average responses of the horizontal and vertical neutron chambers remains spatially stable as the source moves and can be used in addition to the staff monitor at neutron fluxes in the detectors four orders of magnitude lower than on the first wall, where staff detectors are located. Owing to low background, detectors of neutron chambers do not need calibration in the reactor because it is actually determination of the absolute detector efficiency for 14-MeV neutrons, which is a routine out-of-reactor procedure.     

ST嬗变堆中心柱的中子学及中子辐照效应研究

基于先进核数据库ENDF/B-VI和计算机程序对ST嬗变堆中心柱的中子学及辐照损伤的二维分析计算结果，分别对中心柱导体因中子辐照影响而引起电阻率、电阻、电流和欧姆电阻功率等的沿径向不均匀分布，以及辐照损伤对中心柱热工水力问题及更换寿命的影响进行了分析和计算。结果表明，中子辐照直接改变了中心柱导体材料的电阻率分布。热工-水力学分析和计算表明，电流不均匀分布可显著地延长中心柱的使用寿命，并估算出ST嬗变堆中心柱设计的更换寿命大约8年。     

Calculations of the 3-D neutronics for CH HCSB TBM with 3×3 sub-modules

Using three dimension MCNP code and FENDL2.0 data library, neutronics calculation for a HCSB (helium cooling solid breeder) TBM (test blanket module) with 3×3 sub-modules has been performed. Local tritium breeding ratio (TBR) of 0.907, total tritium generation rate of 0.0175g·d-1, peak power density of 9.27MW·m-3 and total power deposit of 0.422MW·m-3 are obtained under neutron wall loading of 0.78MW·m-2 and duty factor of 22%.     

CFETR水冷陶瓷包层中子学试验模块初步设计与分析

针对中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂包层(WCCB)基本方案,进行了中子学试验模块初步设计与分析。试验模块由3个氚增殖区、2个中子倍增区、3个冷却板以及第一壁、钨保护层、背板组成,并在试验模块中放置碳酸锂探测器进行氚测量。通过MCNP输运程序和IAEA发布的聚变评价核数据库FENDEL-2.1对试验模块中子学性能进行评估,获得了试验模块各区域的中子能谱以及氚产生率(TPR)值;各个区域中子径向通量以及由中子能谱所得到的边缘效应,表明内部区域能谱最能代表原包层的中子能谱;加反射层能提高试验模块的TPR值,综合考虑能谱,TPR以及经济等因素,加钢反射层是较好的选择。