Measurements and Calculations of Neutron Energy Spectra Behind Polyethylene Shields Bombarded by 40- and 65-MeV Quasi-Monoenergetic Neutron Sources

Measurements of neutron energy spectra behind 30.5-, 61.0-, 122.0-, 183.0-cm-thick polyethylene shields bombarded by 40- and 65-MeV quasi-monoenergetic neutrons are performed at the 90-MeV AVF cyclotron of the TIARA (Takasaki Ion Accelerator for Advanced Radiation Application) at JAERI (Japan Atomic Energy Research Institute). Source neutrons are produced at 3.6- and 5.2-mm-thick⁷ Li targets bombarded by 43- and 68-MeV protons, respectively. A BC501A organic liquid scintillator and multi-moderator spectrometer with a ³He counter (Bonner ball) are used for spectrometry of transmitted neutrons and their energy spectra are obtained with the unfolding technique. The energy spectra from a few MeV up to a peak energy are obtained by the BC501A scintillator measurement and those below a few MeV down to thermal energy are obtained by the Bonner ball measurement. The measurements are performed on the neutron beam axis and at off-center positions, and attenuation profiles of neutron fluxes along the beam axis are obtained. The MORSE Monte Carlo calculations are performed with the DLC119/HIL086 multi-group cross section library for comparison with the measured data. The calculation generally gives a little overestimated fluxes, and a few % longer attenuation lengths of peak flux and dose equivalent.     

BC501液体闪烁体对n-γ及能量的分辨与其尺寸的关系

BC501液体闪烁体广泛应用于探测快中子，但测量伴随着很高的γ本底。为寻找具有较好的n-γ及能量分辨的BC501闪烁体，利用脉冲上升时间法，对几种不同尺寸的BC501闪烁体进行n-γ及能量分辨测量。在下阈0.75和1MeV下，分别测量了Am-Be中子源的n-γ分辨谱以及相同条件下的γ上升时间-幅度谱。测量了d-T中子源14MeV的反冲质子脉冲高度分布。对不同尺寸BC501闪烁体的n-γ及能量分辨进行了比较。实验表明，综合考虑n-γ和能量分辨，闪烁体的体积不应太大，长度应在保证效率的条件下适中选择。      

252Cf裂变γ射线伴随飞行时间法刻度液体闪烁体中子探测效率

宏观检验实验是检验核数据正确性的重要实验方法之一。液体闪烁体中子探测器是中子核数据宏观检验实验中快中子能谱测量的主要探测器,其探测效率曲线的准确性关系到实验结果的精度。本文采用²⁵²Cf中子源的伴随γ射线和飞行时间法测得了液体闪烁体对2.0～10.0 MeV中子的相对探测效率曲线,同时利用飞行时间法和400 kV脉冲中子发生器的d-D反应中子源测得了2.9 MeV单能中子的绝对探测效率。将相对探测效率曲线归一到单能点的绝对效率,得到探测器在这一能区的绝对探测效率曲线。使用蒙特卡罗程序NEFF模拟相同参数的液体闪烁体探测器对10.0 MeV以下中子的探测效率曲线。最后将实验结果与模拟结果对比,结果表明实验得到的探测效率曲线合理、准确。     

板状Bi样品泄漏中子和γ谱实验测量与模拟计算

通过飞行时间法,测量了氘氘脉冲中子与不同厚度209Bi样品作用后61°和119°方向的泄漏中子飞行时间谱和泄漏γ能谱,样品尺寸分别为30 cm×30 cm×5 cm、30 cm×30 cm×10 cm和30 cm×30 cm×15 cm。采用BC501A液体闪烁体探测器测量0.8～3.2 MeV能区的泄漏中子飞行时间谱,钾冰晶石探测器（CLYC）测量0.2～0.8 MeV的泄漏中子飞行时间谱和泄漏γ能谱。用MCNP-4C程序对泄漏中子飞行时间谱和泄漏γ能谱进行了模拟计算,²⁰⁹Bi的评价中子核数据分别采用了CENDL-3.1库、ENDF/B-Ⅷ.0库、JENDL-4.0库以及JEFF-3.3库中的数据,模拟结果分别与实验结果进行比较分析,研究结果表明,泄漏中子谱CENDL-3.1库的模拟结果在119°方向弹性峰位置有较严重的低估现象,JENDL-4.0库在1.5 MeV附近（第二非弹能区）有一定高估,而在低能区有明显低估;泄漏γ能谱JENDL-4.0库和JEFF-3.3库的模拟结果与实验结果偏差明显,而CENDL-3.1库符合较好。     

Neutron Total Cross Section for Iron around Resonance Valley near 24 keV

A neutron leakage spectrum from a nickel sphere surrounding a 14-MeV neutron source is measured and analyzed in order to verify the accuracy of nickel cross sections. Measurement is done by means of a time-of-flight technique in the range of 2–15 MeV using an NE213 scintillator, and compared with calculations carried out with MCNP, a continuous energy Monte Carlo transport code, using JENDL-3PR1 and ENDFIB-IV neutron libraries.

In spite of an overestimation of neutron flux near 13 MeV, the calculated result employing JENDL-3PR1 shows generally better agreement with the measured spectrum. In ENDF/B-IV usage, there is disagreement between measured and calculated spectra between 5 and 12 MeV. Problems in evaluated nuclear data for nickel are also described.     

Measurements of induced activity in concrete by secondary particles at forward direction produced by intermediate energy heavy ions on an Fe target

Spallation and neutron capture reaction rate distributions were measured using activation detectors inside a 90-cm thick ordinary concrete pile exposed to a field of secondary particles escaping a thick (stopping length) iron target bombarded with various intermediate energy ions, 230 MeV/u He, 400 MeV/u C, and 800 MeV/u Si. Activation detectors of aluminum, bismuth, gold, and gold covered with cadmium were inserted at various depths in the concrete pile. In addition, the distributions of activation reaction rate were simulated by FLUKA and PHITS Monte-Carlo codes. Generally, comparison of measured and calculated reaction rates show agreement within a factor of two. The experimental data will be useful for benchmarking Monte-Carlo radiation transport simulation code capabilities in estimating radioactivity induced in accelerator radiation shielding.     

SND-S1型液体闪烁体光输出的能量响应

采用不同能量的γ射线标准源及D-D、D-T核反应的单能中子源分别测定了新型液体闪烁体SND-S1的光输出随粒子能量的变化,采用Monte-Carlo程序Penelope模拟计算了¹³⁷Csγ射线的能量分布谱,最大康普顿电子能量的计算值和实验值相差2.7%。将实验结果与文献值作了比较,能量低于3MeV时,符合较好;能量高于6MeV时,略有差别。结果表明,液体闪烁体的光输出与电子能量呈线性正比关系,而与中子能量呈非线性关系。     

Characterization of the neutron flux distribution at the Athens Tandem Accelerator NCSR “Demokritos”

Quasi-monoenergetic neutron beams, in the energy range 7-11.5 MeV, produced via the ²H(d,n) reaction, have been used at the 5.5 MV tandem T11/25 Accelerator Laboratory of NCSR “Demokritos”. The flux variation of the neutron beam is monitored with a BF₃ detector, while the absolute flux is obtained with respect to reference reactions. An investigation of the energy dependence of the neutron fluence has been carried out using two independent techniques: by a liquid scintillator BC501A detector and deconvolution of its recoil energy spectra performed by means of the DIFBAS code, as well as via the multiple foil activation technique in combination with the SULSA unfolding code. The neutron facility has also been characterized by means of Monte Carlo simulations with MCNP5.     

Calculation of Response Function of NE-213 Organic Liquid Scintillator for Gamma-Rays

A Monte Carlo code was newly developed to examine response functions of a 2 in. dia. by 2 in. long NE-213 liquid scintillator for γ-ray. This code included the electron transport and the electron-photon cascade calculation to handle the wall and end effect induced by high energy electrons. Results of the Monte Carlo calculation were compared with measured values for standard sources, reaction γ-ray and thermal neutron capture γ-ray, and fairly good agreement was obtained.

Response functions for monoenergetic γ-ray of energies 1~10 MeV were calculated at 1 MeV intervals. The calculations were made in parallel incident geometry without the peripheral material components surrounding the scintillator. The results are tabulated in this paper. A response matrix calculated from the above data was applied to the unfolding of NE-213 pulse height spectra using the FERDO code and fairly good results were obtained in absolute values.     

75MeV／u^16O离子在辐照生物实验区产生的中子角分布

应用Ａｌ为阈探测器对７５ＭｅＶ／ｕ＾１６Ｏ离子在辐照生物研究区产生的Ｅｎ〉６ＭｅＶ中子的角分布进行了实验测量，以了解辐照生物实验区的中子分布情况，为进一步开展的重离子冶癌研究提供辐射防护的实验数据。实验结果表明实验区产生的中子具有明显的前冲分布。     

镓样品泄漏中子谱的测量与分析

基于中国原子能科学研究院的中子学积分实验装置,利用BC501A液体闪烁体探测器,结合飞行时间法（TOF）测量了镓样品的泄漏中子谱。采用MCNP 4C程序进行了模拟并与实验泄漏中子谱进行了比较,对ENDF/B-Ⅶ.1、JEFF-3.2、TENDL-2015数据库中镓核中子评价数据进行了宏观基准检验分析,并与TALYS程序计算结果作对比。研究结果显示：在9 MeV以下能区,TENDL-2015库与实验结果符合很好;在弹性散射能区,JEFF-3.2和TENDL-2015库与实验结果符合较好;对于12 MeV左右的非弹性散射峰,JEFF-3.2库与实验结果符合较好,TALYS计算结果显示该部分主要来自镓核分离能级的贡献。     

基于信赖域算法的中子解谱方法研究

提出了一种新的基于信赖域算法的中子能谱求解方法。使用O5S软件仿真了能量范围为0.25～16 MeV、能量间隔为0.25 MeV的BC501A液体闪烁体探测器响应函数。利用该响应函数仿真验证了入射中子能谱分别为单峰和多峰情况下算法的解谱效果，并通过D-T单能中子源、^{241Am-Be和252Cf连续中子源对解谱方法进行了实验验证。结果表明，使用信赖域算法求得的能谱与参考谱线具有较好的一致性，初步验证了解谱方法的有效性。}     

Calculations of the transport of neutrons and secondary gamma rays through concrete for incident neutrons in the energy range 15 to 75 MeV

Earlier work by Alsmiller et al. considered coupled neutron and secondary-gamma-ray transport through a thick shield of silicon dioxide with 5% water by weight for neutron sources with energies of 50, 100, 200, 300 and 400 MeV. In that work, the approximation was made that gamma rays were produced only by neutron capture. In the present work, coupled neutron and secondary-gamma-ray transport through a thick shield of concrete for neutron sources with energies of 15, 25 and 75 MeV is considered. In this study, gamma-ray production for all interactions involving neutrons with energies up to 15 MeV was included; i.e., the approximation made here is that gamma-ray production can be neglected for interactions by neutrons with energies > 15 MeV.For incident neutron energies of 15, 25, 50, and 75 MeV, results of total and gamma-ray dose equivalents are given as a function of depth into the slab. For the 50- and 75-MeV incident neutron energies, the gamma-ray dose equivalent was found to be no more than 5% of the total dose equivalent at all depths considered ( 1500 g/cm²). For the 15- and 25-MeV incident neutron energies, however, the gamma-ray dose equivalent dominates at greater depths into the slab. A conservative estimate of the effect of including gamma rays produced in interactions with neutrons of energies > 15 MeV indicates that the calculated total dose equivalent would increase by no more than 5%.     

Preliminary Experiments on Accelerator-Driven Subcritical Reactor with Pulsed Neutron Generator in Kyoto University Critical Assembly

A series of preliminary experiments on an accelerator-driven subcritical reactor (ADSR) with 14 MeV neutrons were conducted at Kyoto University Critical Assembly (KUCA) with the prospect of establishing a new neutron source for research. A critical assembly of a solid-moderated and -reflected core was combined with a Cockcroft-Walton-type accelerator. A neutron shield and a beam duct were installed in the reflector region for directing as large a number as possible of the high-energy 14MeV neutrons generated by deuteron-tritium (D-T) reactions to the fuel region, since the tritium target is located outside the core. And then, neutrons (14MeV) were injected into a subcritical system through a polyethylene reflector. The objectives of this paper are to investigate the neutron design accuracy of the ADSR with 14MeV neutrons and to examine experimentally the neutronic properties of the ADSR with 14MeV neutrons at KUCA. The reaction rate distribution and the neutron spectrum were measured by the foil activation method for investigating the neutronic properties of the ADSR with 14 MeV neutrons. The eigenvalue and fixed-source calculations were executed using a continuous-energy Monte Carlo calculation code MCNP-4C3 with ENDF/B-VI.2 for the subcriticality and the reaction rate distribution, respectively; the unfolding calculation was done using the SAND-II code coupled with JENDL Activation Cross Section File 96 for the neutron spectrum. The values of the calculated subcriticality and the reaction rate distribution were in good agreement with those of the experiments. The results of the experiments and the calculations demonstrated that the installation of the neutron shield and the beam duct was experimentally valid and that the MCNP-4C3 calculations were accurately carried out for analyzing the neutronic properties of the ADSR with 14MeV neutrons at KUCA.     

Proposal of Method to Estimate Criticality Correction for Anisotropic Diffusion in Plate Lattice Fast Assembly

Measurements on the neutron and γ-ray attenuation in multi-legged air filled ducts have been carried out using a Cockroft-Walton type neutron generator. The measured spectra were obtained with an NE-213 liquid scintillator using pulse shape discrimination to resolve neutron and γ-ray pulse height data and using a spectral unfolding code to convert these data to energy spectra. Results are given for two rectangular duct geometries. A series of integral measurements have also been carried out with a long counter for fast neutrons and a radiation survey meter to measure the γ-ray dose. The biological dose arising due to the streaming of neutrons was measured with a rem counter. The results show the relative decrement of the integral counts along the axis of the duct. The spectral measurements reveal the presence of resonant windows of oxygen present in the concrete medium. Also the 14 MeV component is found to be dominant in the first leg of the duct whereas degraded neutrons dominate in the second leg. The results are compared with MORSE calculations.     

50MeV／u^12C离子实验靶区中子注量率的测量

用阈探测器中子活化法测量了50MeV/u~(12)C离子实验靶区出射的热中子以及E_n分别大于6、11、20、50MeV的中子注量率。     

Energy Loss Distribution of Recoil Protons in Stilbene Scintillator

Formulas are derived for calculating the energy loss distribution of recoil protons in a cylindrical organic scintillator with a broad beam of fast neutrons in the energy range 1 to 15 MeV perpendicularly incident on its base. The assumptions are: (1) the scintillator is composed solely of hydrogen and carbon; (2) only elastic scattering from hydrogen and carbon is considered in relation to the interaction of fast neutrons with the scintillator; (3) single and double scattering alone are considered; (4) wall effect is neglected for recoil protons produced in the second collisions; (5) the radius and the thickness of the scintillator are greater than the range of recoil protons of the highest energy.

As an example, the calculated results are shown for stilbene crystals of 1″ dia. and 1/8″ to 1″ thick. In scintillators of thicknesses below 1/4″, and for incident fast neutrons in the energy range from 3 to 15 MeV, the contribution of double scattering to the energy loss distribution of recoil protons is below about 10% of that of single scattering, while wall effect is quite significant, in particular, for incident neutrons of high energy.     

Application of a BC501A Liquid Scintillation Detector with a Gain Stabilization System on the EAST Tokamak

A 2"×2"BC501A liquid scintillation detector with a gain stabilization system is developed and applied to neutron andγ-ray measurement on the EAST tokamak.Energy calibration of a liquid scintillator using a fast coincidence method is presented and compared with the Monte Carlo simulation.Determination of the proton light output function of the BC501A is presented.Results from dedicated experiments with an Am-Be neutron source,γsource and quasi-monoenergetic neutron beams,and from measurements on EAST tokamak are presented and discussed.     

Measurement of neutron spectra through composed material block bombarded with D-T neutrons

A 2-dimensional composed material assembly made of the iron and hydric block has been established. The neutron spectra from the assembly bombarded with 14-MeV neutrons at neutron generator have been obtained using the proton recoil technique with a stillbene detector. The detector positions were selected at the 60°, 120°, 180° on the surface of the iron spherical shell. The background neutron spectra consisted of background and room return radiation were subtracted with combination of methods of experimental shielding and MCNP calculation. The uncertainty of results was 6.3-7.4%. The experiment results were analyzed and simulated by MCNP code and two data library. The difference is integral neutron flux (background neutron subtracted) of measured results greater than calculations with maximum of 21.2% in the range of 1-16 MeV.     

无屏蔽条件下用25.4cm单球雷姆计测量中能重离子反应中子剂量当量的理论修正

用重离子反应出射中子能谱和角分布估算了用25.4cm单球雷姆计测量100MeV/u~(12)C+C和41.7MeV/u~(12)C+Fe两个重离子反应中子剂量当量时的理论修正系数。