混合评价核数据库HENDL1.0/MG/MC研制

根据世界几个主要核评价数据库,如ENDF/B 6(美国)、JEF 2.2(欧盟)、JENDL 3.2(日本)、BROND 2.2(俄罗斯)、CENDL 2.1(中国)和FENDL 2(IAEA/NDS),兼顾聚变、裂变以及聚变 裂变次临界混合堆设计研究的多种需要,经过甄别、筛选,最后集成为包含213个核素的基本评价文件,名为HENDL1.0/E的核评价数据库.在此基础上,利用目前流行的群常数加工程序系统NJOY和输运截面制备程序TRANSX制作两套用于中子或/和光子输运计算的输运截面工作库:①参考Vitamin J能群结构制作了175群中子和42群光子、中子 光子耦合多群工作数据库HENDL1.0/MG,可用于离散纵标Sn法程序计算;②连续能群结构、紧凑ENDF(ACE)格式中子截面库HENDL1.0/MC,可用于蒙特卡罗方法输运计算,如MCNP.另外还制作了可用于燃耗(嬗变)计算的燃耗库BURNUP.LIB和响应函数库RESPONSE.LIB两个专用数据库.同时,也对HENDL1.0综合评价核数据库的有效性进行了抽样测试、基准检验和初步确认. A Hybrid Evaluated Nuclear Data Library(HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDL1.0 contains one basic evaluated sub-library naming HENDL1.0/E and two processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing...     

一种用于RIBLL2的纵向场多次取样型电离室

为兰州第二条放射性束流线（RIBLL2）研制了一台用于ΔE测量的纵向场多次取样型电离室。 利用3组分α源（239Pu为3.435 MeV, 241Am为3.913 MeV, 244Cm为4.356 MeV）对取样单元进行了测试, 确定了电离室的最佳工作电压为－500 V, 沉积能量为3.435 MeV时, 取样单元的能量分辨为271.4 keV(FWHM)。 利用Geant4对此电离室的整体性能进行了模拟, 表明可以对Z≥4的离子实现较好的粒子鉴别。 A longitudinal field MUltiple Sampling Ionization Chamber (MUSIC), which makes multiple measurements of energy loss for very high energy heavy ions at RIBLL2, has been constructed and tested with 3 constituent α source （239Pu: 3.435 MeV, 241Am: 3.913 MeV, 244Cm: 4.356 MeV）. The voltage plateau curve has been plotted and －500 V is determined as a proper work voltage. The energy resolution is 271.4 keV FWHM for the sampling unit when 3.435 MeV energy deposited. A Geant4 Monte Carlo simulation is made and it indicates the detector can provide unique particle identification for ions Z≥4.     

双核模型下超重核117的生成截面研究

Within the framework of the dinuclear system model, the capture of two colliding nuclei, and the formation and de-excitation process of a compound nucleus are described by using an empirical coupled channel model, solving the master equation numerically and the statistical evaporation model, respectively. In the process of heavy-ion capture and fusion to synthesize superheavy nuclei, the barrier distribution function is introduced and averaging collision orientations are considered. Based on this model, the production cross sections of the cold fusion system ^76-82Se＋^209Bi and the hot fusion systems ^55Mn＋^238U, ^51V＋^244pu, ^59Co＋^232Th, ^48Ca＋^247-249Bk and ^45Sc＋^246-248Cm are calculated. The isotopic dependence of the largest production cross sections is analyzed briefly, and the optimal projectile-target combination and excitation energy of the 1n-4n evaporation channels are proposed. It is shown that the hot fusion systems ^48Ca＋^247-249Bk in the 3n evaporation channels and ^45Sc＋248Cm in the 2n-4n channels are optimal for synthesizing the superheavy element 117.     

重离子碰撞复合体系碎化产生超重核可能性的探讨

讨论了通过重核碰撞形成的复合体系破裂产生超重核的问题。评述了两种主要的理论模型:即早期发展的在碎化理论框架下的量子涨落理论和本课题组尝试发展的微观输运理论模型。概括阐述了微观输运理论研究^197Au＋^197Au,^238U＋^238U和^244Pu＋^244Pu等反应的主要结果,即反应中产生的超重碎块的几率与入射能的关系,复合体系和超重碎块的衰变机制以及所形成的超重碎块的结合能和形状的分布。In this paper, the possibility of producing superheavy fragments through composite system breaking up in massive nuclear reactions is investigated. Two main theoretical models, which are the quantum fluctuations with in the fragmentation theory developed at 1980＇s and improved quantum molecular dynamics model developed recently by our group, are briefly reviewed. The dependence of the production probability of superheavy fragments on the incident energy, the decay mechanism of composite system and superheavy fragments, and the distribution of binding energy of Superheavy fragments are discussed for reactions of ^244Pu＋^244Pu, ^238U＋^238U, 197Au＋^197Au based on the improved quantum molecular dynamics model.     

Monte Carlo simulation of indoor external exposure due to gamma-emitting radionuclides in building materials

The use of building materials containing naturally occurring radionuclides such as^40K,^238U,^232Th and their progeny, could lead to external exposures to the residents of such buildings. In this paper, a set of models are constructed to calculate the specific effective dose rates（the effective dose rate per Bq/kg of ^40K, the ^238U series,and the ^232Th series） imposed on residents by building materials with the MCNPX code. The effect of chemical composition, position concerned in the room and thickness as well as density of material is analyzed. In order to facilitate more precise assessment of indoor external dose due to gamma-emitting radionuclides in building materials,three regressive expressions are proposed and validated by measured data to calculate specific effective rates for40 K,the238U series and the232 Th series, respectively.     

Measurement and analysis of the 238U(n, 2n) reactionrate in depleted uranium/polyethylene shells

In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of the ²³⁸U(n, 2n) reaction rate was carried out using an activation technique, by measuring the 208 keVγ rays emitted from ²³⁷U. The self-absorption of depleted uranium foils with different thicknesses was experimentally corrected. The distribution of the ²³⁸U(n, 2n) reaction rate at 90° to the incident D⁺ beam was obtained, with uncertainty between 5.3% and 6.0%. The experiment was analyzed using MCNP5 code with the ENDF/BVI library, and the calculated results are all about 5% higher than the measured results.     

Primary result of ^236U measurement with accelerator mass spectrometry at CIAE

The rare isotope ^236U has a half-life of 2.342（3）×107 years, and is produced principally by thermal neutron capture on ^235U. The isotopic atom ratio of ^236U/^238U depends on the integral thermal neutron flux received by the material of interest. ^236U is potentially useful as a ＂fingerprint＂ for indicating the presence of neutron-irradiated uranium usually originating from nuclear activity. By extracting negative molecular ion UO^- from the uranium oxide target, simulating the ^236U^16O^- beam transport with ^238U^16O^- and ^208Pb2^16O^- pilot molecular ion beam, transporting the ^236U-containing ion beam with a high resolution injection magnet analyzer and electrostatic analyzer system, and finally identifying and detecting ^236U with a time-of-flight detector （TOF）, a method for AMS （Accelerator Mass Spectrometry） measurement of ^236U was established on the HI-13 Accelerator AMS system at China Institute of Atomic Energy.     

对先进核能系统中U-Pu循环的研究

利用新开发的数据库和程序对加速器驱动的次临界反应堆中的Ｕ－Ｐｕ循环进行了详细的理论研究．通过对反应堆功率、临界系数、γ和中子通量以及裂变核的演化等计算,得到了令人满意的中子学结果.The U-Pu cycle in accelerator driven subcritical reactor is studied by means of new data library and code. The satisfactory neutronics results are obtained by calculating the reactor power, critical value, gamma and neutron flux and evolution of fissioning nuclear density. The detailed analysis is also presented.     

Fusion reactions around the barrier for Be+~(238)U

Fusion-evaporation cross sections of ~(238)U (~9Be,5n)~(242)Cm are measured over a wide energy range around the Coulomb barrier.These measured cross sections are compared with model calculations using two codes,namely HIVAP2 and KEWPIE2.HIVAP2 calculations overestimate the measured fusion-evaporation cross sections by a factor of approximately 3.In KEWPIE2 calculations,two approaches,namely the Wentzel-Kramers-Brillouin(WKB) approximation and the empirical barrier-distribution (EBD) method,are used for the capture probability;both of them properly describe the measured cross sections.Additionally,fusion cross sections of ~(7,9)Be+~(238)U measured in two experiments are applied to constrain model calculations further through three codes,i.e.,HIVAP2,KEWPIE2,and CCFULL.Parameters in these codes are also examined by comparison with measured fusion cross sections.All the comparisons indicate that the KEWPIE2 calculations using the WKB approximation agree well with the measured cross sections of both fusion reactions ~(7,9)Be+~(238)U and the fusion-evaporation reaction ~(238)U (~9Be,5n)~(242)Cm.Calculations using the fusion code CCFULL are also in good agreement with the measured fusion cross sections of ~(7,9)Be+~(238)U.     

ITER 试验包层模块活化计算与环境安全分析

运用聚变堆放射性计算程序FDKR 和衰变链数据库AFDC-DLIB, 计算了ITER 中国氦冷固态增殖试验包层模块设计中活化产物的放射性、衰变余热和潜在生物危害因子BHP 值。计算结果表明: 对于试验包层模块来说, 在500MW 聚变功率下运行一年, 停堆时的总放射性、余热和BHP 值分别为2. 10× 10¹⁶B_q 、5. 06 × 10^{- 3}MW 和 68. 6km³•( kW) ^{- 1}。结果表明: 中国氦冷实验包层模块不存在突出的安全问题。     

厚靶D（d,n）^3He反应加速器中子源的产额、能谱和角分布

给出一种计算氘钛厚靶D(d,n)3He反应加速器中子源的产额、能谱和角分布的方法,并发展了一个计算机模拟程序,程序能够计算氘束流能量小于1.0 MeV的中子源的产额、能谱和角分布.计算时使用推荐的D(d,n)3He反应截面数据和来自SRIM-2003程序的氘在氘钛靶中的阻止本领数据.给出一些典型计算结果,包括中子积分产额、中子能谱和角分布.     

锥形慢波结构波导谐振腔微波发生器

 利用二维半的PIC等离子体物理程序设计了一种新的结构简单、体积小、重量轻、频率稳定的高功率、高效率的微波器件。此器件采用了锥形慢波结构波导谐振腔,不用外加引导磁场。微波频率可以设计为f=1.6 ~12GHz,功率P_out可达GW。     

Study of neutron response for two hybrid RPC setups using the GEANT4 MC simulation approach

The present article describes a detailed neutron simulation study in the energy range 10~(-10) MeV to 1.0 GeV for two different RPC configurations.The simulation studies were taken by using the GEANT4 MC code.Aluminum was utilized on the GND and readout strips for the (a) Bakelite-based and (b) glass-based RPCs.For the former type of RPC setup the neutron sensitivity for the isotropic source was S_n=2.702×10~(-2) at E_n=1.0 GeV, while for the latter type of RPC, the neutron sensitivity for the same source was evaluated as S_n=4.049×10~(-2) at E_n=1.0 geV.These results were further compared with the previous RPC configuration in which copper was used for ground and pickup pads.Additionally A1 was employed at (GND+strips) of the phosphate glass RPC setup and compared with the copper-based phosphate glass RPC.Good agreement with sensitivity values was obtained with the current and previous simulation results.     

加速器驱动快/热耦合次临界系统的概念设计

对加速器驱动快／热耦合次临界系统进行了概念设计研究。在该系统中,内区的快包层和外区的热包层是相互独立的,快、热包层之间为空腔和B4C包层以实现单向耦合。快包层装以合金（MA＋Pu）Zr为燃料,热包层初始循环装以氧化物（Th＋Pu）O₂为燃料,平衡循环装以（Th＋^233 U＋Pu）O2为燃料。^99Tc,^129I和^135Cs分别以单质、NaI和CsCl的形式装入热包层。该系统具有较高的能量放大倍数、嬗变效率和燃料转换比:系统能量放大系数不低于320;锕系元素（MA）和裂变产物（FP）的嬗变支持比分别为1个和2个压水堆;热包层的燃料转换比为0．715。 Accelerator driven coupled fast/thermal subcritical system is conceptually designed. In the system, the inner/fast blanket and the outer/thermal blanket are separated each other by large vacuum and B4C coating for on edirection coupling. The metal type fuel （MA ＋ Pu）Zr is loaded into the fast blanket. The oxide type fuels （Th ＋ Pu） O2 and （Th ＋ ^233U ＋ Pu）O2 are loaded into the thermal blanket during the initial cycle and the equilibrium cycle, respectively. ^99Tc, ^129I and ^135Cs are loaded respectively in the form of pure technetium metal, sodium iodide and cesium chlorine into the thermal blanket. The system has good transmutation efficiency, high energy amplification factor and good fuel conversion ability: the energy amplification factor is above 320; the transmutation support ratios of MA and FP are about 1.0 and 2.0 PWRs respectively; the fuel conversion ratio in the thermal blanket is about 0. 715.     

Quantitative and sensitive detection of prohibited fish drugs by surface-enhanced Raman scattering

Rapid and simple detections of two kinds of prohibited fish drugs, crystal violet(CV) and malachite green(MG),were accomplished by surface-enhanced Raman scattering(SERS). Based on the optimized Au/cicada wing, the detectable concentration of CV/MG can reach 10~(-7) M, and the linear logarithmic quantitative relationship curves between log I and log C allows for the determination of the unknown concentration of CV/MG solution. The detection of these two analytes in real environment was also achieved, demonstrating the application potential of SERS in the fast screening of the prohibited fish drugs, which is of great benefit for food safety and environmental monitoring.