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Comparison and evaluation of resolved resonance region covariance representations 共振区协方差表示的比较与评价
IF 1.2 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-20 DOI: 10.1080/00223131.2023.2279303
Hunter Belanger, Amanda Lewis, Devin Barry
The covariance matrices for the evaluated resolved resonance region parameters are typically processed into a grouped covariance representation for use in uncertainty propagation studies. An altern...
评估的已分辨共振区域参数的协方差矩阵通常被处理成一个分组协方差表示,用于不确定性传播研究。一个交错的…
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引用次数: 0
Kinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applications 创新高温气冷堆低氧惰性气氛中IG-110氧化动力学建模
IF 1.2 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-15 DOI: 10.1080/00223131.2023.2274928
Yosuke Nishimura, Anna Gubarevich, Katsumi Yoshida, Avadhesh Kumar Sharma, Koji Okamoto
The oxidation behavior of IG-110, a graphite core component, was investigated at temperatures ranging from 400 to 1000°C in a 10 ppm Ar/O2 flow to simulate the oxidation process between the graphit...
研究了石墨芯材IG-110在温度为400 ~ 1000℃、Ar/O2浓度为10 ppm的条件下的氧化行为,模拟了石墨芯材与石墨芯材之间的氧化过程。
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引用次数: 0
Request for 35 Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design 从熔盐快堆设计的角度要求35cl (n,p)反应截面测量和重新评估
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-14 DOI: 10.1080/00223131.2023.2282553
Yoshihisa Tahara, Haruka Hirano, Satoshi Chiba, Hiroyasu Mochizuki, Tatsuya Katabuchi
ABSTRACTA molten chloride salt fast reactor with inherent safety features is being studied in order to utilize spent fuel discharged from light-water reactors effectively and to reduce environmental burdens. A hard neutron spectrum is required to achieve the transmutation of TRU efficiently, which can be realized by using a molten chloride salt. However, it was found that the criticality analysis shows a large difference of 2%Δk among the effective multiplication factors (keff) obtained using several evaluated nuclear data libraries. A sensitivity analysis was performed to investigate the cause of the difference in keff and it was clarified that the difference of 2%Δk/k reactivity was due to the difference in cross sections of the 35Cl(n,p)35S reaction. Such a large difference in keff makes a reliable core design difficult and strongly affects important core characteristics such as the TRU transmutation rate, conversion ratio, and so on. Therefore, this paper has been prepared to make a strong request for measurements and re-evaluations of the (n,p) cross section of 35Cl.KEYWORDS: Molten salt reactorchloridefast reactortransmutationTRU35Cl(np) reactionDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgmentsWe would like to thank Assistant Prof. Chikako Ishizuka at the Tokyo Institute of Technology for her helpful discussions, encouragement and also for computer maintenance to proceed calculations.Fig. 1 Conceptual design for 700-MWt reactor core with four heat exchangers (unit in meters).Display full sizeFig. 2 Bird’s-eye view of the reactor with four loops and a stainless steel reflector.Display full sizeFig. 3 Calculation model of the MCSFR.Display full sizeFig. 4 Average neutron spectrum in the core of the MCSFR.Display full sizeFig. 5 Sensitivities of keff to the reaction cross sections of 35Cl calculated using Serpent 2Display full sizeand ENDF/B-VIII.0.(n,p), (n,α), and (n,γ) cross sections(n,n) and (n,n’) cross sectionsFig. 6 Relative cross-section differences of 35Cl between ENDF/B-VIII.0 and JENDL-5.Display full sizeThe reference of the relative difference is ENDF/B-VIII.0.(n,p), (n,α), and (n,γ) cross sections(n,n) and (n,n’) cross sectionsFig. 7 Contribution of the relative difference in the (n,p) cross sections for 35Cl between ENDF/B-VIII.0 and JENDL-5 to reactivity.Display full sizeThe reference of the relative difference is ENDF/B-VIII.0.Fig. 8 Comparison of nuclear data libraries for the 35Cl (n,p) 35S reaction cross sections with the experimental values. There are three experimental values around 14 MeV: one of Schantl at 14.7 MeV (1970)
摘要为了有效利用轻水堆排放的乏燃料,减轻环境负担,研究具有固有安全特性的熔融氯盐快堆。为了有效地实现TRU的嬗变,需要硬中子谱,这可以通过使用熔融氯化物盐来实现。然而,在临界分析中发现,不同核数据库得到的有效乘法因子(keff)在2%Δk上存在较大差异。通过敏感性分析探讨了keff差异的原因,并明确了2%Δk/k反应活性的差异是由于35Cl(n,p)35S反应截面的差异。如此大的角差使得可靠的堆芯设计变得困难,并强烈影响堆芯的TRU嬗变率、转化率等重要特性。因此,本文强烈要求对35Cl的(n,p)截面进行测量和重新评价。关键词:熔盐反应器氯化物反应器突变tru35cl (np)反应免责声明作为对作者和研究人员的服务,我们提供此版本的已接受稿件(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。我们要感谢东京工业大学的助理教授Chikako Ishizuka,感谢她的有益讨论和鼓励,并感谢计算机维护人员继续进行计算。1 700mwt堆芯4个热交换器概念设计(单位米)。全尺寸显示2鸟瞰图,反应器有四个回路和一个不锈钢反射器。全尺寸显示3 MCSFR的计算模型。全尺寸显示4 MCSFR核心的平均中子能谱。全尺寸显示5使用Serpent 2Display full size和ENDF/B-VIII.0计算keff对35Cl反应截面的灵敏度。(n,p), (n,α)和(n,γ)截面(n,n)和(n,n ')截面。6 ENDF/B-VIII之间35Cl的相对截面差异。0和JENDL-5。相对差值的参考为ENDF/B-VIII.0 (n,p), (n,α), (n,γ)横截面(n,n)和(n,n ')横截面7 ENDF/B-VIII之间35Cl (n,p)截面相对差值的贡献。0和JENDL-5的反应性。相对差值的参考值为ENDF/ b - viii .0。8 35Cl (n,p) 35S反应截面核数据库与实验值的比较。在14mev附近有三个实验值:一个是Schantl在14.7 MeV (1970) [Citation21],另两个是Nagel在14.6 MeV (1966) [Citation22]。全尺寸显示9 JENDL-4.0、JENDL-5和ENDF/B-VIII的35Cl (n,p) 35S反应截面比较。用新的实验数据。表4使用不同核数据库计算的有效倍增因子的比较。表下载CSVDisplay表
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引用次数: 0
Mutual separation of Am and Cm using ADAAM (alkyl DiAmide AMine) and Reduction of Volumes for Liquid Waste generated via batch wise multistage extractions 利用ADAAM(烷基二胺)相互分离Am和Cm,并通过分批多级萃取减少废液的体积
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-14 DOI: 10.1080/00223131.2023.2283214
Yuji Sasaki, Masashi Kaneko, Yasutoshi Ban, Hideya Suzuki
ABSTRACTThe mutual separation of Am and Cm is conducted using an alkyl-diamide amine (ADAAM(EH)) extractant. ADAAM(EH) exhibits extremely high separation factor (SF) with respect to Am and Cm separation (SF = 5.9) in a HNO3-n-dodecane system. The batch-wise multistage extractions are performed using a system containing 0.2 M ADAAM(EH) and 1.5 M HNO3, with their distribution ratios (D) of the system for Am and Cm equal to 2.55 and 0.434, respectively. In this multistage extraction, 3 stages of feed, 9 stages involving scrubbing, and 11 stages involving the use of an organic solvent give 96.5% and 1.06% yields of Am and Cm, respectively. After the mutual separation, the aqueous and the organic phases that includes actinides increases four times in volume compared to the feed solution. Additional extraction steps are to reduce the volume of the solutions including actinides. We use tetraethyl diglycolamide (TEDGA)/water for Am concentration, tetraoctyl diglycolamide/n-dodecane for the intermediate extraction, and TEDGA/water for stripping in the Cm concentration step. Taking the additional steps, Am and Cm can be recovered in just two or three stages in the aqueous phases.KEYWORDS: Solvent extractionAmCmseparationADAAMDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgmentsThe authors gratefully acknowledge Dr. Y. Kitatsuji at JAEA for safety management with respect to actinides and Dr. M. Arisaka at JAEA for ICP-measurements.Declaration of Interest StatementNo potential conflict of interest was reported by the authors.Figure 1 Extractant, masking agents, and other reagents used in this studyDisplay full sizeFigure 2 The conditions of batch-wise multistage extraction. (a) Am and Cm separation, (b) Am concentration, (c) Cm concentrationDisplay full sizeFigure 3 Extraction behavior of metals using alkyl-diamide amine (ADAAM). (a) D(Ln, An) against HNO3 concentration, (b) D(An) against ADAAM concentration, (c) D(Ln) against ADAAM concentration, (d) D(Ln) against their atomic number, (e) D(FP) against HNO3 concentration, and (f) D(FP) against ADAAM concentrationDisplay full sizeFigure 4 Ball-and-stick description of [M(ADAAM)]3+, wherein the black, red, blue, and brown spheres show metal, oxygen, nitrogen, and carbon atoms, respectively, and hydrogen atoms are not shown to avoid confusion, with the M3+–Namine and M3+–Oamide bond lengths in the Å unit shown as Am3+/Cm3+Display full sizeFigure 5 Representatives of 5f-type α-MOs in the valence region for [M(ADAAM)]3+Display full size Figure 6 pH and masking agent dependence on D(An, Ln) in alkyl-diamide amine (ADA
摘要采用烷基二胺(ADAAM(EH))萃取剂对Am和Cm进行了相互分离。ADAAM(EH)在hno3 -n-十二烷体系中具有极高的Am和Cm分离系数(SF = 5.9)。采用含有0.2 M ADAAM(EH)和1.5 M HNO3的体系进行分批多级提取,Am和Cm的分配比(D)分别为2.55和0.434。在这个多级萃取中,3级进料,9级洗涤,11级有机溶剂的使用,分别得到96.5%和1.06%的Am和Cm收率。相互分离后,包括锕系元素在内的水相和有机相的体积比进料溶液增加了四倍。附加的萃取步骤是减少溶液的体积,包括锕系元素。在Cm浓度步骤中,采用四乙基二甘醇酰胺(TEDGA)/水萃取Am浓度,四辛基二甘醇酰胺/正十二烷萃取中间部分,TEDGA/水萃取。通过采取额外的步骤,Am和Cm可以在水相中只需要两到三个阶段就可以回收。关键词:溶剂萃取- amcm -分离- adaam免责声明作为对作者和研究人员的服务,我们提供此版本的已接受稿件(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。作者感谢日本原子能机构的Y. Kitatsuji博士对锕系元素的安全管理和日本原子能机构的M. Arisaka博士对icp测量的研究。利益声明作者未报告潜在的利益冲突。图1本研究中使用的萃取剂、掩蔽剂和其他试剂显示完整尺寸图2分批多级萃取条件(a) Am和Cm的分离,(b) Am浓度,(c) Cm浓度。图3烷基二胺(ADAAM)萃取金属的行为。(a) D(Ln, An)对HNO3浓度的影响,(b) D(An)对ADAAM浓度的影响,(c) D(Ln)对ADAAM浓度的影响,(D) D(Ln)对它们的原子序数的影响,(e) D(FP)对HNO3浓度的影响,(f) D(FP)对ADAAM浓度的影响显示完整尺寸图4 [M(ADAAM)]3+的球棒描述,其中黑色、红色、蓝色和棕色球体分别表示金属、氧、氮和碳原子,氢原子不显示,以避免混淆。图5 [M(ADAAM)]3+价区5f型α-MOs的代表图6烷基二胺(ADAAM)萃取剂中pH和掩掩剂对D(An, Ln)的依赖条件:(a) 0.5 M ADAAM−2.5 M HNO3 + 1.3 M en + 1m MAc + 0.1 M DTBA (b) 0.5 M ADAAM−1.5 M HNO3 + 0.05 M DGAc + 0.5 M en + 1m MAc (c) 0.5 M ADAAM−1.5 M HNO3 + TMDGA或NTAamide(C2)显示全尺寸图7多级提取结果(a)水相各段An的回收率(%)(b)有机相各段An的回收率(%)萃取条件:0.2 M ADAAM/n-十二烷,1.5 M HNO3多段萃取条件:有机相、进料水相、磨砂水相的段数:11、3、9。表2 (b) ADAAM萃取后丙二酸水溶液pH值*下载csv显示表
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引用次数: 0
Detailed visualization of radioactive hotspots inside the unit 1 reactor building of the Fukushima Daiichi Nuclear Power Station using an integrated radiation imaging system mounted on a mecanum wheel robot 使用安装在机械轮式机器人上的集成辐射成像系统,对福岛第一核电站1号反应堆建筑内的放射性热点进行了详细的可视化
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-14 DOI: 10.1080/00223131.2023.2282551
Yuki Sato, Yuta Terasaka, Masatoshi Oura
In the decommissioning of the Fukushima Daiichi Nuclear Power Station, understanding the distribution of radioactive substances and dose-equivalent rates is crucial to develop detailed decontamination plans and minimize worker exposure. In this study, we remotely visualized radioactive hotspots and dose-equivalent rate distribution in Unit 1 reactor building of the station using a Mecanum wheel robot equipped with a Compton camera, simultaneous localization and mapping device, and survey meter. We successfully visualized high-concentration radioactive hotspots on the U-shaped piping of the drywell humidity control system and the atmospheric control piping in the ceiling in front of the transverse in-core probe room. Furthermore, the hotspot location was identified in three dimensions using the Compton camera used to analyze the atmospheric control piping. By simultaneously analyzing the dose-equivalent rate data acquired by the survey meter and the hotspot locations visualized by the Compton camera, it was confirmed that the hotspots caused elevated dose-equivalent rates in the surrounding area. In the future, if this robotic system is used in unexplored areas, such as the upper floors of reactor buildings, it can provide information about the locations of radioactive hotspots and the distribution of dose-equivalent rates.
在福岛第一核电站的退役过程中,了解放射性物质的分布和剂量当量率对于制定详细的去污计划和最大限度地减少工人的暴露至关重要。本研究采用Mecanum轮式机器人,配备康普顿相机、同步定位与测绘装置和测量仪表,对电站1号反应堆厂房内的放射性热点和剂量当量率分布进行了远程可视化。我们成功地在干井湿度控制系统的u型管道和横向岩心探测室前天花板的大气控制管道上可视化了高浓度放射性热点。在此基础上,利用康普顿相机对大气控制管路进行了三维定位。通过同时分析测量仪获取的剂量当量率数据和康普顿摄像机显示的热点位置,确认热点引起周边区域剂量当量率升高。将来,如果这个机器人系统被用于未开发的区域,比如反应堆建筑的上层,它可以提供有关放射性热点位置和剂量当量率分布的信息。
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引用次数: 0
Application of the spectral determination method to liquid scintillation spectra 液相闪烁光谱测定方法的应用
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-13 DOI: 10.1080/00223131.2023.2282552
Masumi Oshima, Jun Goto, Takehito Hayakawa, Hirofumi Shinohara, Katsuyuki Suzuki, Yuichi Sano, Masato Asai, Tomoko Haraga
ABSTRACTPreviously we reported a simple algorithmic method of spectral determination method (SDM), which is based on the first principle that a γ-ray spectrum obtained for a sample is a linear superposition of individual spectra of the radioactive nuclides included in the sample and demonstrated that the method is valid for γ-ray determination. Here we apply it to the spectra obtained by liquid scintillation counter (LSC). In LSC measurements quenching is generally observed and we at first developed its correction method to standard spectra. The SDM code reported in the previous investigation is used to analyze the LSC spectra. Based on the analyses done by using the measured spectra, we concluded that the SDM method is valid in the LSC spectra similarly to the γ-ray spectra studied in the previous investigation.KEYWORDS: Decomposition of a liquid-scintillation-counter spectrumfull-spectrum analysisleast-squares fitquenching correctiondetermination accuracyDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementsThis work was supported by JAEA Nuclear Energy S&T and Human Resource Development Project through concentrating wisdom Grant Number JPJA20P20333366.
摘要以前我们报道了一种简单的光谱测定方法(SDM),该方法基于样品的γ射线光谱是样品中放射性核素的单个光谱的线性叠加的第一原理,并证明了该方法对γ射线的测定是有效的。本文将其应用于液体闪烁计数器(LSC)得到的光谱。在LSC测量中普遍观察到猝灭现象,我们首先提出了对标准光谱的校正方法。在前面的研究中报告的SDM代码被用来分析LSC频谱。通过对实测光谱的分析,我们得出结论,SDM方法在LSC光谱中是有效的,类似于之前研究的γ射线光谱。关键词:液体闪烁分解-计数器光谱-全谱分析-最小二乘拟合校正-测定精度免责声明作为对作者和研究人员的服务,我们提供此版本的接受稿件(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。本研究由日本原子能机构核能科技与人力资源开发项目资助,项目资助号:JPJA20P20333366。
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引用次数: 0
Spatial evolution mechanism of vortex structure in the highly-loaded helium compressor cascade 高负荷氦压缩机叶栅涡结构的空间演化机制
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-13 DOI: 10.1080/00223131.2023.2282550
Ke Sun, Zhitao Tian, Yingqi Fan, Huawei Lu, Jianchix Xin
ABSTRACTThe highly-loaded design method of helium compressors can effectively solve the difficulty in compressing helium in High Temperature Gas-cooled Reactors (HTGR). But it also causes obviously different attack angle characteristics of blade surface loads in a highly-loaded helium compressor compared to air compressors. This difference inevitably affects separation characteristics and flow loss within the compressor. In the current study, the effects of highly-loaded design methods and changes in attack angle on the separation characteristics of the compressor cascade are analyzed by applying a numerical simulation method firstly. Then the influence of Mach number on the loss characteristics of the cascade for a highly-loaded helium compressor is systematically analyzed. Finally, the effect of differences in the material properties of working fluid on the separation characteristics is discussed. The results indicate that the proportion of secondary flow loss to the total loss in highly-loaded compressor cascades is 2.46 times larger than that in conventionally-loaded ones. While properties of working fluid have an effect on the performance of the compressor cascade, their effects on the weight factor of vortex loss are highly limited.KEYWORDS: Helium compressorHigh temperature gas-cooled reactor (HTGR)HTGR type reactorhighly-loaded design methodSecondary flow lossTurbineClosed Brayton cycleSpecific heat ratioComputational fluid dynamicsDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementThe present work is financially supported by the National Natural Science Foundation of China (No. 52206042), Natural Science Foundation of Liaoning Province (No. 2022-BS-096), Basic Research Project of Liaoning Provincial Department of Education(LJKMZ20220364).NomenclatureTableDisplay TableDeclaration of interest statementNo potential conflict of interest was reported by the author(s).Figure 1 Construction of highly-loaded helium compressor velocity triangleDisplay full sizeFigure 2 Schematic diagram of the geometric parameters of cascadesDisplay full sizeFigure 3 Schematic diagram of S3 sectional positionDisplay full sizeFigure 4 Schematic diagram of the calculation meshDisplay full sizeFigure 5 Axial vorticity diagrams for different grid numbers of exit sectionsDisplay full sizeFigure 6 Validation of numerical simulation methodDisplay full sizeFigure 7 Variation of total loss coefficients and pressure ratios with attack angle for helium compressor cascades of different design methodsDisplay full sizeFigure 8 Static pressure curves of blade surface with 50% blad
摘要氦气压缩机的高负荷设计方法可以有效地解决高温气冷堆(HTGR)压缩氦气的难题。但高负荷氦气压缩机叶片表面载荷的攻角特性也与空压机明显不同。这种差异不可避免地影响分离特性和压缩机内部的流动损失。本研究首先采用数值模拟的方法,分析了高负荷设计方法和攻角变化对压气机叶栅分离特性的影响。然后系统分析了马赫数对高负荷氦气压气机叶栅损失特性的影响。最后,讨论了工质性质差异对分离特性的影响。结果表明:高负荷压气机叶栅二次流损失占总损失的比例是常规负荷的2.46倍;虽然工质性质对压气机叶栅的性能有影响,但对旋涡损失权重因子的影响非常有限。关键词:氦压缩机高温气冷堆(HTGR)HTGR型反应堆高负荷设计方法二次流损失sturbinclosed Brayton循环比热比计算流体动力学免责声明作为对作者和研究人员的服务,我们提供此版本的接受手稿(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。本研究得到国家自然科学基金(No. 52206042)、辽宁省自然科学基金(No. 2022-BS-096)、辽宁省教育厅基础研究项目(LJKMZ20220364)资助。NomenclatureTableDisplay表利益声明声明作者未报告潜在的利益冲突。图1高负荷氦气压缩机速度三角形构造显示满尺寸图2叶栅几何参数示意图显示满尺寸图3 S3截面位置示意图显示满尺寸图4计算网格示意图显示满尺寸图5不同栅格数出口截面轴向涡量图显示满尺寸图6数值模拟方法验证显示满尺寸图7总量变化图8不同设计方法50%叶高时叶面静压曲线(Ma=0.3)显示满尺寸图9不同设计方法叶栅极限流线及静压系数程序显示满尺寸图10不同设计方法氦压气机叶栅涡结构示意图S3截面不同设计方法(Ma=0.3, i= 0°)显示全尺寸图11不同设计方法的氦压缩机叶栅S3段涡损权重(Ma=0.3, i= 0°)图12高负荷氦气压气机叶栅不同攻角下吸力面极限流线及静压系数图显示满尺寸图13高负荷氦气压气机叶栅不同攻角下轴向涡量图显示满尺寸图14不同攻角下氦气压气机叶栅S3段涡损失重量图显示满尺寸图15静压图16高负荷氦压气机叶栅S3段不同来流马赫数时轴向涡量图图17不同来流马赫数下氦压气机叶栅S3段涡损失重量图18总压损失系数和压比随攻角的变化图19不同工质(0.3Ma, i=0°)下50%展向截面静压比图图20不同工质(Ma=0.3, i=0°)下叶栅S3截面轴向涡量图图21不同工质压缩机叶栅S3截面的涡损重量显示尺寸附加信息基金资助本工作得到国家自然科学基金面上[52206042]的支持。
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引用次数: 0
Study on iodine adsorption capacity and adsorption mechanism of AgY AgY对碘的吸附能力及吸附机理研究
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-12 DOI: 10.1080/00223131.2023.2276397
Cheng Zhang, Zexiang Chen, Jianrong Hou, Hongzheng Ren, Zhen Wang, Xin Li, Yongguo Li, Haixia Kong, Haifeng Yu, Jie Yu
ABSTRACTTo systematically study the methyl iodide (CH3I) adsorption performance and adsorption mechanism of Ag ion exchange NaY zeolite (AgY), AgY adsorbents with different Ag content were selected. 16.6% AgY was capable of storing 150 mg/g and 275 mg/g of CH3I when the penetrated CH3I reached 1‰ and 100% inlet concentration. TEM and EDS results presented a high relationship between Ag dispersion and CH3I adsorption capability. The formation of a stable AgI complex rationalized the CH3I adsorption mechanism on AgY. Compared to AgX, AgY was verified to possess a strong acid resistance by FT-IR, SEM and XRD. The effect of three key parameters (temperature, humidity and gas velocity) on CH3I adsorption was carefully investigated by orthogonal experiment design. The experimental results showed that AgY had better iodine removal performance at a high temperature, low humidity, and low flow rate. This work provides technical reference for further engineering applications of 16.6%AgY in spent fuel reprocessing plants.KEYWORDS: Zeolitespent fuelradioactive iodineadsorption AcknowledgementThis research was supported by the State Administration of Science, Technology and Industry for National Defence (KY20007) and the National Natural Science Foundation of China (U1967215).Disclosure statementNo potential conflict of interest was reported by the author(s).Additional informationFundingThis work was supported by the the National Natural Science Foundation of China [U1967215]; the State Administration of Science, Technology and Industry for National Defense [KY20007].
摘要为了系统研究Ag离子交换型NaY分子筛(AgY)对碘化甲酯(CH3I)的吸附性能及吸附机理,选择了不同Ag含量的AgY吸附剂。当渗透CH3I浓度达到1‰和100%时,16.6% AgY可储存150 mg/g和275 mg/g的CH3I。透射电镜和能谱分析结果表明,银的分散性与吸附CH3I的能力密切相关。稳定的AgI络合物的形成使AgY对CH3I的吸附机理合理化。与AgX相比,通过FT-IR、SEM和XRD验证了AgY具有较强的耐酸性能。采用正交试验设计,考察了温度、湿度和气速三个关键参数对CH3I吸附的影响。实验结果表明,AgY在高温、低湿、低流量条件下具有较好的除碘性能。为16.6%AgY在乏燃料后处理装置的进一步工程应用提供了技术参考。本研究得到国家国防科技工业局(ky2007)和国家自然科学基金(U1967215)的支持。披露声明作者未报告潜在的利益冲突。本研究得到国家自然科学基金资助[U1967215];国家国防科技工业局[ky2007]。
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引用次数: 0
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments 四维朗格万模型与Hauser-Feshbach理论的结合来描述裂变碎片的统计衰变
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-09 DOI: 10.1080/00223131.2023.2273470
Kazuki Fujio, Shin Okumura, Chikako Ishizuka, Satoshi Chiba, Tatsuya Katabuchi
We have developed a novel theoretical method to obtain independent fission product yields and prompt neutron observables by connecting mass and total kinetic energy (TKE) distributions calculated by a four-dimensional Langevin dynamical model to a Hauser-Feshbach statistical decay model. In the Langevin calculations, mass distributions corresponding to the standard I and II modes were obtained separately and superposed to reproduce the fission fragment yield of spontaneous fission of 238,240,242Pu and thermal neutron-induced fission of 239Pu. This was achieved by using different neck parameters for these two modes in the two-center shell model shape parametrization, and a systematics of the superposing ratio was obtained as a function of (N−Z)/A of the fissioning nuclei. The Hauser-Feshbach calculations were performed using a nuclear reaction code TALYS for 239Pu(n,f) reaction in the incident energy range from thermal up to 5MeV, and the calculated prompt fission observables were compared with experimental and evaluated data. Although further improvements are needed for the most important nuclides, it turned out that the present methodology has the capability to prepare fission-related nuclear data for nuclides for which measurements are difficult.
我们开发了一种新的理论方法,通过将四维Langevin动力学模型计算的质量和总动能(TKE)分布与Hauser-Feshbach统计衰变模型联系起来,获得独立的裂变生成量和瞬发中子观测值。在Langevin计算中,分别获得了标准I和II模式对应的质量分布,并叠加再现了238,240,242Pu自发裂变和239Pu热中子诱导裂变的裂变碎片产率。这是通过在双中心壳模型形状参数化中对这两种模式使用不同的颈参数来实现的,并得到了重叠比作为裂变核(N−Z)/ a的函数的系统分布。利用核反应代码TALYS对239Pu(n,f)在入射能量从热到5MeV范围内的反应进行了Hauser-Feshbach计算,并将计算得到的瞬发裂变观测值与实验和评估数据进行了比较。虽然对最重要的核素需要进一步改进,但事实证明,目前的方法有能力为难以测量的核素准备与裂变有关的核数据。
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引用次数: 0
Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of 74 ,76 ,78 ,80 ,82Se 74,76,78,80,82se的k -中子俘获截面和俘获伽马能谱测量
4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-11-06 DOI: 10.1080/00223131.2023.2278599
So Kamada, Masayuki IGASHIRA, Tatsuya Katabuchi, MIZUMOTO Motoharu
ABSTRACTThe neutron capture cross sections and capture γ-ray spectra of 74,76,78,80,82Se were measured in a region from 15 to 100 keV and around 550 keV. A neutron time-of-flight method was used with a ns-pulsed neutron source based on the 7Li(p,n)7Be reaction and a large anti-Compton NaI(Tl) γ-ray spectrometer. A pulse-height weighting technique was applied to the observed γ-ray pulse-height spectra to obtain capture yields. The capture cross sections of 74,76,78,80Se were derived with uncertainties from 4.0 to 5.5% and those of 82Se were derived with uncertainties of 6.5–27% by using the standard capture cross sections of 197Au. The present results of 78,82Se were the first experimental ones above the resolved resonance region. The present results were compared with previous measurements and the evaluated values in JENDL-5.0 and ENDF/B-VIII.0. The evaluations of JENDL-5.0 differ from the present results of 74,76,78,80Se and 82Se by 0.9–51% and 6.9–120%, respectively. The capture γ-ray spectra of 74,76,78,80,82Se were derived by unfolding the observed capture γ-ray pulse-height spectra. The present results were the first experimental ones in the keV region.KEYWORDS: Neutron capturecross sectionsgamma spectrakev rangeselenium 74selenium 76selenium 78selenium 80selenium 82selenium 79gold 197Anti-compton NaI(Tl) gamma-ray spectrometertime-of-flight methodpulse-height weighting techniqueDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementThe present study was supported by a Grant-in-Aid (No. 19360423) of the Japan Ministry of Education, Culture, Sports, Science and Technology. This work was also supported by KAKENHI Grant-in-Aids (21K04580) for publication.Additional informationFundingThe work was supported by the a Grant-in-Aid of the Japan Ministry of Education, Culture, Sports, Science and Technology [19360423].
摘要在15 ~ 100 keV和550 keV范围内测量了74,76,78,80,82se的中子俘获截面和俘获γ射线能谱。利用基于7Li(p,n)7Be反应的ns脉冲中子源和大型反康普顿NaI(Tl) γ射线谱仪,采用了中子飞行时间法。将脉冲高度加权技术应用于观测到的γ射线脉冲高度光谱,以获得捕获产率。采用197Au的标准俘获截面,得到了74,76,78,80se的俘获截面,其不确定度在4.0 ~ 5.5%之间,82Se的俘获截面的不确定度在6.5 ~ 27%之间。78,82se的实验结果是第一个在分辨共振区域以上的实验结果。将本研究结果与先前的测量结果以及JENDL-5.0和ENDF/B-VIII.0中的评估值进行比较。JENDL-5.0的评价结果与目前的74、76、78、80Se和82Se的结果分别相差0.9-51%和6.9-120%。通过展开观测到的捕获γ射线脉冲高度谱,得到了74,76,78,80,82se的捕获γ射线谱。这是keV区域的首次实验结果。关键词:中子捕获横截面伽马光谱范围硒74selenium 76selenium 78selenium 80selenium 82硒79gold抗康普顿NaI(Tl)伽马射线光谱仪飞行时间法脉冲高度加权技术免责声明作为对作者和研究人员的服务,我们提供此版本的接受稿件(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。本研究由日本教育、文化、体育、科学和技术部资助(No. 19360423)。这项工作也得到了KAKENHI补助金-in- aids (21K04580)的出版支持。本研究得到了日本教育、文化、体育、科学和技术部的资助[19360423]。
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