ADS熔盐散裂靶中子学性能研究

与传统加速器驱动次临界系统(ADS)采用金属靶作为散裂中子靶的设计不同,加速器驱动次临界熔盐堆(AD-MSRs)采用靶堆一体的设计,直接使用燃料熔盐作为散裂中子靶。由于熔盐靶的中子学性能直接影响AD-MSRs的能量放大系数、核废物的嬗变和核燃料增殖的效率,所以本研究基于MCNPX程序,详细计算了高能质子轰击氟盐和氯盐两种熔盐靶产生的散裂中子产额、散裂中子能谱、能量沉积分布以及散裂产物等中子学性能,并与液态Pb和铅铋共熔体(LBE)两种液态金属靶进行了对比。计算结果表明,熔盐靶在散裂中子产额上与液态金属靶有一定的差距,但熔盐靶内能量沉积分布的梯度较小,更有利于靶区的热量导出。与液态Pb和LBE靶相比,熔盐靶的散裂产物中包含更多的气体以及高质量数的α发射体核素。     

ADS熔盐散裂靶中子学性能研究

与传统加速器驱动次临界系统（ADS）采用金属靶作为散裂中子靶的设计不同，加速器驱动次临界熔盐堆（AD-MSRs）采用靶堆一体的设计，直接使用燃料熔盐作为散裂中子靶。由于熔盐靶的中子学性能直接影响AD MSRs的能量放大系数、核废物的嬗变和核燃料增殖的效率，所以本研究基于MCNPX程序，详细计算了高能质子轰击氟盐和氯盐两种熔盐靶产生的散裂中子产额、散裂中子能谱、能量沉积分布以及散裂产物等中子学性能，并与液态Pb和铅铋共熔体（LBE）两种液态金属靶进行了对比。计算结果表明，熔盐靶在散裂中子产额上与液态金属靶有一定的差距，但熔盐靶内能量沉积分布的梯度较小，更有利于靶区的热量导出。与液态Pb和LBE靶相比，熔盐靶的散裂产物中包含更多的气体以及高质量数的α发射体核素。     

能量到GeV的质子入射铅靶的散裂产物分布研究(英文)

由中高能质子入射靶引起的散裂碎片的分布关系到散裂靶经长期辐照后的放射性废物的累积。在量子分子动力学模型(QMD)中考虑剩余核的裂变过程(FISSION),利用QMD FISSION模型研究了322,660,759 MeV的质子入射铅靶的散裂产物的分布。计算结果很好地再现了实验测量值。     

ADS中液态铅铋靶流动管道屏蔽计算

对于具有独立回路冷却液态铅铋(Liquid Lead-bismuth Eutectic,LBE)散裂靶的加速器驱动的次临界系统(Accelerator Driven Sub-critical System,ADS),高能质子束流辐照靶体产生的散裂产物进入管道后,会持续释放光子,会对靠近流动管道的工作人员造成辐射损伤。本文利用高能粒子输运程序Fluka计算散裂靶的散裂产物累积产额,然后利用放射性衰变计算程序Origen2计算散裂产物释放的光子强度及分群能谱,最后利用Fluka进行流动管道内光子源项的屏蔽计算。对一种典型的Y型LBE有窗靶进行的流动管道屏蔽计算结果表明,参照GB18871-2002职业性放射性工作人员年剂量当量限值20 m Sv的标准,若使用铅作为屏蔽材料,流动管道的管壁应该加厚20 cm。本文工作可为ADS系统LBE有窗靶的回路屏蔽设计提供参考。     

基于GeTHU测量确定natPb(p,x)207Bi和natPb(p,x)194Hg的反应截面

加速器驱动次临界系统(Accelerator Driven Sub-critical System,ADS)是最具潜力的下一代核能系统选型之一，准确评估ADS散裂靶内产生的长寿命放射性核素含量是应用研究中的重要课题，利用质子活化法可以有效评价质子与散裂靶材料发生相互作用产生长寿命核素的反应截面。4个质子辐照天然铅样品分别被能量为40 MeV、70 MeV、100 MeV和400 MeV的质子照射90 min、75 min、40 min和25 min，在冷却约20 a后，利用中国锦屏地下实验室(China Jinping Underground Laboratory,CJPL)的超低本底γ谱仪GeTHU进行测量，使用SAGE(Simulation and Analysis for Germanium Experiments)模拟框架计算了GeTHU的探测效率，测定了能量为40 MeV、70 MeV、100 MeV和400 MeV质子与天然铅发生^natPb(p,x)²⁰⁷Bi和^natPb(p,x)¹⁹⁴...     

加速器驱动的次临界系统散裂靶泄漏中子谱研究

为研究加速器驱动的次临界系统（ADS）散裂靶的散裂中子学特性,采用Geant4计算不同能量质子轰击铅铋靶产生的泄漏中子产额、能谱、轴向积分分布。模拟得到1 GeV质子对应的靶的优化尺寸及优化后泄漏中子谱,计算结果可为ADS散裂靶件和堆芯设计提供参考。     

基于DEM的重金属颗粒流靶区输运过程研究

基于固体和液体散裂靶,近期国内外研究学者提出了一种新概念重金属颗粒流散裂靶。加速器驱动次临界系统(ADS)中重金属散裂靶在高能质子轰击作用下,出现能量沉积现象,而这些热量必须进行有效冷却以保证ADS的安全性。本文针对这种新概念颗粒流靶对靶区产生的高额热量的导出效果进行了模拟分析。首先采用蒙特卡罗程序计算450 Me V质子束轰击钨靶后能量沉积的空间分布,并将此作为颗粒流的体热源输入,基于计算流体力学-离散单元法(CFD-DEM)耦合方法对ADS靶区两种不同直径颗粒流的输运过程进行了模拟研究。结果表明,随颗粒直径的减小,靶区内温度分布更为均匀,颗粒流的流动特性更接近流体,颗粒导热性能增强;颗粒流靶中热应力可局限在单个颗粒内部而承受更高的能量沉积,具有更高的安全限值以及更广阔的应用前景。     

用放射性活度计测定^67Ga中杂质^66Ga的含量

一、序言枸椽酸镓(~(67)Ga)注射液是一种诊断性放射性药物,其中核素~(67)Ga是通过加速器加速质子或氘,轰击锌靶,利用(p,xn)或(d,xn)反应产生的,伴随产物会有一些放射性杂质,如~(65)Zn,~(66)Ga等。杂质的含量与加速粒子的能量、靶材料、打靶时间等有关。~(65)Zn可经化学分离,使之少于0.1%,而~(66)Ga无法用化学方法去除,只有靠放置衰变的办法达到药物     

强流脉冲质子束轰击19F靶产生6-7MeV准单能脉冲γ射线初步实验研究

给出了利用PIN半导体探测器和ST401塑料闪烁体配合光电倍增管测量的强流脉冲质子束轰击含^19F核素的靶产生的6—7MeV准单能脉冲γ射线的初步实验结果。理论上计算了质子束轰击C2F4靶产生的准单能脉冲γ射线产额和核反应截面随入射质子能量的变化曲线，提出了采用质子束传输法分离和降低轫致辐射干扰的方法，利用ST401配合光电倍增管和PIN半导体探测器测量了质子传输不同距离后轰击C2F4靶产生的6—7MeV准单能脉冲γ射线谱以及相对于轫致辐射的时间延迟数据，并根据飞行时间确定了束流峰值时刻的质子能量，还通过实验验证了Cu、Cr和不锈钢靶及其中所含的杂质不能产生明显的其它能量的γ射线干扰。     

利用MSDM分析1GeVP+208Pb散裂反应产物

利用Ignatyuk能级密度公式代替多步动力学模型(MSI)M)中的费米气体能级密度公式，并考虑壳效应对能级密度的影响，以改进其对质子引起散裂产物的形成截面研究。对1GeV p ^208Pb散裂产物的电荷、质量分布以及产物核同位素形成截面的计算结果好于利用费米气体能级密度的MSDM计算结果。利用该程序研究获得的散裂产物中的裂变核、散裂核以及二者之间的产物核的同位素形成截面和实验数据符合较好，并好于LAHET、YIELDX以及INCL4 KHSv3p模型计算结果。     

Accumulation and Transmutation of Spallation Products in the Target of Accelerator-Driven System

Analysis of the radiological burden of the spallation products (SP) was performed for various spallation targets (lead, tungsten, tin). The radiological burden was discussed in terms of toxicity based upon the concept of Annual Limit on Intake (ALI) shows that alpha-emitting rare earths (¹⁴⁶Sm, ¹⁴⁸Gd, ¹⁵⁰Gd, ¹⁵⁴Dy) are dominant. Their toxicity was estimated at equilibrium state with and without their transmutation. It is concluded that, in terms of toxicity, accumulation of SP in the target is quite comparable with transmutation of fission products (FP) in the blanket of Accelerator-Driven System (ADS).     

Recent progress in nuclear data measurement for ADS at IMP

Recent progress in nuclear data measurement for ADS at Institute of Modern Physics is reviewed briefly.Based on the cooler storage ring of the Heavy Ion Research Facility in Lanzhou, nuclear data terminal was established.The nuclear data measurement facility for the ADS spallation target has been constructed, which provides a very important platform for the experimental measurements of spallation reactions. A number of experiments have been conducted in the nuclear data terminal. A Neutron Time-of-Flight(NTOF)spectrometer was developed for the study of neutron production from spallation reactions related to the ADS project.The experiments of 400 MeV/u ~(16)O bombarded on a tungsten target were presented using a NTOF spectrometer.Neutron yields for 250 MeV protons incident on a thick grain-made tungsten target and a thick solid lead target have been measured using the water-bath neutron activation method. Spallation residual productions were studied by bombarding W and Pb targets with a 250 MeV proton beam using the neutron activation method. Benchmarking of evaluated nuclear data libraries was performed for D-T neutrons on ADS relevant materials by using the benchmark experimental facility at the China Institute of Atomic Energy.     

Materials researches at the Paul Scherrer Institute for developing high power spallation targets

For the R&D of high power spallation targets, one of the key issues is understanding the behavior of structural materials in the severe irradiation environments in spallation targets. At PSI, several experiments have been conducted using the targets of the Swiss spallation neutron source (SINQ) for studying radiation damage effects induced by high energy protons and spallation neutrons. As well, experiments have been performed to investigate liquid lead-bismuth eutectic (LBE) corrosion and embrittlement effects on T91 steel under irradiation with 72 MeV protons. In this paper, an overview will be given showing a selection of results from these experiments, which include the mechanical properties and microstructure of ferritic/maretensitic (FM) steels (T91, F82H, Optifer etc.) and austenitic steels (EC316LN, SS 316L, JPCA etc.) irradiated to doses higher than ever attained by irradiation in a spallation environment, and the behaviors of T91 irradiated with 72 MeV protons in contact with flowing LBE.     

Radiological hazard of long-lived spallation products in accelerator-driven system

The present paper focuses on analysis of radiological hazard of spallation products that appears to be an important factor that might affect the choice of beam/target performance in designing the accelerator-driven systems. The analysis is done in terms of toxicity expressed in units of Annual Limit on Intake (ALI). It reveals the significant contribution of alpha emitting rare earths (¹⁴⁶Sm, ¹⁴⁸Gd, ¹⁵⁰Gd, ¹⁵⁴Dy) into overall toxicity of spallation targets.     

Heat deposition in thick targets due to interaction of high energy protons and thermal hydraulics analysis

Heat deposition inside thick targets due to interaction of high energy protons (E_p ∼ GeV) has been estimated using an improved version of the Monte Carlo simulation code CASCADE.04.h. The results are compared with the available experimental data for thick targets of Be, Al, Fe, Cu, Pb and Bi at proton energies of 0.8 GeV, 1.0 GeV and 1.2 GeV. A more continuous heat deposition approach which has been adopted in CASCADE.04.h yields results which are in better agreement with the experimental data as compared to the ones from the earlier version of CASCADE.04. The results are also compared with the predictions of the FLUKA Monte Carlo code. Both CASCADE.04.h and FLUKA predictions are nearly similar for heavy targets and both agree with the experimental measurements. However, they do have differences in predictions for lighter targets where measurements also differ from the predictions. It is observed that the maximum heat loss in thick targets occurs at the beginning of the target due to increasing nuclear reaction contributions. This aspect is crucial in designing the window of a spallation neutron target employed in an accelerator driven sub-critical system (ADS) as this is the first material to be traversed by the proton beam and is subjected to the maximum temperature gradient. Optimization of the target-window parameters requires a careful estimation of heat deposition in the window region and this has been demonstrated through thermal hydraulic studies related to the design of a realistic lead bismuth eutectic (LBE) spallation neutron target for an ADS system.     

Reaction rate analyses of accelerator-driven system experiments with 100 MeV protons at Kyoto University Critical Assembly

At the Kyoto University Critical Assembly, a series of reaction rate experiments is conducted on the accelerator-driven system (ADS) with spallation neutrons generated by the combined use of 100 MeV protons and a lead–bismuth target in the subcritical state. The reaction rates are measured by the foil activation method to obtain neutron spectrum information on ADS. Numerical calculations are performed with MCNP6.1 and JENDL/HE-2007 for high-energy protons and spallation process, JENDL-4.0 for transport and JENDL/D-99 for reaction rates. That the reaction rates depend on subcriticality is revealed by the accuracy of the C/E (calculation/experiment) values. Nonetheless, the accuracy of the reaction rates at high-energy thresholds remains an important issue in the fixed-source calculations. From reaction rate analyses, the indium ratio is newly defined as another spectrum index with the combined use of ¹¹⁵In(n, γ)^116mIn and ¹¹⁵In(n, n′)^115mIn reaction rates, and considered useful in examining the neutron spectrum information on ADS with spallation neutrons.     

Optimal ion beam,target type and size for accelerator driven systems: Implications to the associated accelerator power

In interactions of different energetic ions with extended targets hydrogen isotopes are the most effective projectiles for the production of spallation neutrons. It is shown that for every target material and incident ion type and energy there is an optimal target size which results in the escape of a maximum number of spallation neutrons from the target. Calculations show that in an ADS, combination of a beam of 1.5 GeV deuteron projectiles and a uranium target results in the highest neutron production rate and therefore highest energy gain. For fast 1.5 GeV d + ²³⁸U ADS with lead or lead–bismuth eutectic moderator, the required ion beam current is only 38% of that for 1 GeV proton projectiles on lead target. It is shown that for a modular ADS with uranium target and output power of 550 MW_th a 1.5 GeV deuteron beam of current 1.8 mA is required, which is easily achievable with today’s technology. For an ADS with k_eff = 0.98 and output power of 2.2 GW_th, the required beam currents for (a) 1 GeV p + Pb and (b) 1.5 GeV d + U systems are 18.5 and 7.1 mA, respectively.     

Material selection for spallation neutron source windows: Application to PDS-XADS and XT-ADS prototypes

High performance neutron sources are being proposed for many scientific and industrial applications, ranging from material studies, hybrid reactors and transmutation of nuclear wastes. In the case of transmutation of nuclear wastes, accelerator driven systems (ADS) are considered as one of the main technical options for such purpose. In ADS a high performance spallation neutron source becomes an essential element for its operation and control. This spallation source must fulfil very challenging nuclear and thermo-mechanical requirements, because of the high neutron rates needed in ADS. The material selection for this key component becomes of paramount importance, particularly the source window that separates the vacuum accelerator tube from the spallation material where the accelerated protons impinge. In this paper, an integral analysis of spallation sources is done, taking as a reference the projects in this field proposal in the framework of European projects. Our analysis and calculations show that titanium and vanadium alloys are more suitable than steel as structural material for an industrial ADS beam window, mostly due to its irradiation damage resistance.     

Feasibility of uranium spallation target in accelerator-driven system

A feasibility study on natural uranium spallation target in accelerator-driven system (ADS) for minor actinide (MA) transmutation was performed. As a result of comparative study of uranium and lead-bismuth (PbBi) targets in the bare case without blanket surrounding, it was found that uranium target had better neutron generation performance, but limited by the geometrical size due to high neutron absorption in ²³⁸U. In ADS for MA transmutation, uranium used as target instead of PbBi also absorbs neutrons passing the target area.More realistic concept of pin type uranium spallation target cooled by liquid PbBi was considered aiming at enhancing spallation target performance in terms of neutron generation efficiency and operation temperature. The uranium pin target design had nothing better effects on neutron balance of such system than a conventional PbBi target in ADS and it was concluded that uranium target was not suitable for the full-scale ADS.