最新刊期
      卷 43 ， 期 3 ， 2020

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “中国绵阳研究堆采用引束导管偏转技术，为自旋回波谱仪提供中子束。通过蒙特卡罗模拟，验证了引束导管设计方案的可行性。”
        WANG Baihua,HUANG Chaoqiang,WANG Tingting,SUN Guang'ai,WANG Yan
        Vol. 43, Issue 3, Article number: 030201(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030201
        摘要：BackgroundNeutron beam is provided for the spin-echo spectrometer at China Mianyang Research Reactor (CMRR) by neutron deflection at the upper part of the C32 exit of the C3 cold neutron guide. The deflected neutron guide consists of curved guide pipe and straight guide pipe with cross-section 30 mm (W)×30 mm (H).PurposeThis study aims to validate the design scheme of the deflected neutron guide by simulation. The parameters including the number of the channels of the curved guide, the radius of the curved guide and the supermirror factor of the deflected neutron guide.MethodsNeutron ray-tracing package McStas version 2.5 was employed to perform Monte Carlo simulation to investigate the effects of the parameters of the deflected neutron guide on the neutron flux, energy spectrum and beam divergence at the exit and sample position of the deflected neutron guide. The parameters of the curved guide pipe such as the number of the channels, the radius, and the supermirror factor of the deflected neutron guide were studied as well.ResultsThe results show that: 1) it is reasonable to divide the curved guide into 6 channels vertically; 2) the radius of the curved guide should be as large as possible when the space meet the requirements to the installation of the spectrometer; 3) the neutron flux is close to the maximum flux while the supermirror is 2.5.ConclusionsAccording to simulation results, the design scheme for deflected neutron guide is achievable by using 6 channels with the radius 0f 40.0 m and the supermirror factor of 2.5.  
        关键词：China Mianyang research reactor;Monte Carlo simulation;Deflected neutron guide;Curved guide;McStas   
        316
        |
        20
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523469 false
        发布时间：2024-10-25
      • “在射频四极场加速器热稳定性研究领域，专家提出了结合CFD热流耦合的三维多物理场数值分析方法，为加速器结构优化提供有效数值模拟平台。”
        ZHAO Bo,ZHANG Bin,CHEN Shuping,WANG Fengfeng,ZHU Tieming,JIN Xiaofeng
        Vol. 43, Issue 3, Article number: 030202(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030202
        摘要：BackgroundRadio frequency quadrupole (RFQ) field accelerator causes temperature rise and thermal deformation during high power operation. Among many multi-physical analysis methods for RFQ cavity, these models are limited to 2D RFQ section or 3D RFQ local structures whilst the fluid flow motion was ignored.PurposeThis study aims to propose a noval three-dimensional multi physical field numerical method for coupling analysis of RFQ cavity.MethodsCombined with computational fluid dynamics (CFD) and heat flow coupling, electromagnetic, fluid, thermal, structure were integrated into electromagnetic multi physical field coupling analysis. A 81.25 MHz RFQ cavity was taken as sample for verification and the heat transfer effects of three (Standard, RNG, Realizable)k-ε turbulence models under the same experimental conditions were analyzed.Results & ConclusionsThe results show that the CFD numerical simulation method can better simulate the steady-state heat transfer of RFQ accelerator. The feasibility and reliability of the method were verified by comparison with the experimental results. The variation of cavity temperature, structure and frequency under different parameters were analyzed using a suitable turbulence model. Hence this study provides an effective numerical simulation platform for the structural optimization and performance improvement of the accelerators in future.  
        关键词：Computational fluid dynamics;Accelerator;Coupled;Numerical simulation   
        332
        |
        23
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523394 false
        发布时间：2024-10-25
      • “在医疗成像领域，新型X射线管采用碳纳米管阴极，实现快速启动、低功耗和灵活焦斑调整，适用于移动DR设备。”
        TANG Huaping,CHEN Zhiqiang,LIU Ang,QIN Zhanfeng,HE Wu,ZHANG Qinghui
        Vol. 43, Issue 3, Article number: 030203(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030203
        摘要：BackgroundMobile digital radiography (DR) is a hot research direction in the field of modern medical imaging.PurposeThis study aims to develop a new-type X-ray tube for mobile DR devices.MethodsFirstly, in order to solve the problems of slow start-up and high dose of ineffective radiation of hot cathode ray tube, carbon nanotube (CNT) was employed to replace traditional filament as the cathode of the X-ray tube. Then flexible adjustment of focal spot size was realized through active focusing mechanism, so as to meet various clinical application needs. Finally, experimental tests were carried out to compare with the simulation results.ResultsBoth the simulation and experimental results show that the maximum anode voltage of the finally built X-ray tube is 110 kV, the maximum anode current is 70 mA, and the focal spot size varies between 0.9 and 1.9 (IEC 60336 nominal focal spot value). The different working parameters of the corresponding X-ray tube in four different clinical application scenarios are given.ConclusionThe X-ray tube has many advantages, such as fast startup, low power consumption, and wide application scenarios, which makes it very suitable for mobile DR devices.  
        关键词：Carbon nanotube cathode;Cold-cathode X-ray tube;Variable focal spots;Mobile digital radiography   
        334
        |
        26
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523723 false
        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “在闪烁探测器领域，研究人员利用22Na放射源，研究了掺钇BaF2探测器的性能，发现其能量分辨率和时间分辨率均优于BaF2探测器，为高强度γ射线探测提供新方案。”
        WANG Hongfeng,LIU Fuyan,WANG Yingjie,CHEN Junfeng,KUANG Peng,ZHANG Peng,YU Runsheng,CAO Xingzhong,LI Yuxiao,WANG Baoyi
        Vol. 43, Issue 3, Article number: 030401(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030401
        摘要：BackgroundBaF2 scintillation detector is commonly used in low intensity γ-ray detection experiments, and it is easy to pileup during high intensity γ-ray detection.PurposeThis study aims to investigate the performance of Yttrium doped BaF2 (Yttrium doped with 1 at%， atomic percentage) scintillation detector with main concern of pileup and time resolution for high intensity γ-ray detection.MethodsThe energy resolution and time properties of Yttrium doped BaF2 (Yttrium doped with 1 at%) scintillation detector were experimentally tested by using 0.511 MeV γ-ray generated after positron annihilation from 22Na source. As a comparison, the normal BaF2 detector was also tested.ResultsThe experimental results show that the ratio of fast and slow components of Yttrium doped BaF2 crystal (1:1.1) is much higher than that of BaF2 crystal (1:5), but the energy resolution of Yttrium doped BaF2 detector (38%) is worse than that of BaF2 detector (19%). For high intensity γ-ray detection, the Yttrium doped BaF2 detector have better time resolution than the BaF2 detector.ConclusionsThe decrease of the slow component in Yttrium doped BaF2 crystal can shorten the time width of the detector output signal, hence reduce the signals' pileup and improve the time resolution of the detector in high count rate environment.  
        关键词：Scintillation detector;Yttrium doped BaF2 crystal;Energy/time resolution;High intensity γ-ray;Pileup   
        384
        |
        24
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523567 false
        发布时间：2024-10-25
      • “兰州重离子加速器冷却储存环外靶实验子触发判选系统设计完成，可高效筛选γ球探测器信号，满足实验需求。”
        SONG Haisheng,SU Fengjiao,LI Xianqin,ZHANG Qi,CHEN Yong,YAN Duo,YANG Haibo,KONG Jie,SU Hong
        Vol. 43, Issue 3, Article number: 030402(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030402
        摘要：BackgroundThe gamma detection array is an important device in the heavy ion research facility at Lanzhou - cooling storage ring (HIRFL-CSR). In order to eliminate invalid information such as background noise in the experiment, to ensure that subsequent physical analysis can be performed efficiently, a sub-trigger selection system needs to be designed for CSR external target γ detection array.PurposeThis study aims to design aforementioned sub-trigger system for selectable interesting signal in the events recorded by the gamma detector.MethodsBased on flash-based field programmable gate array (FPGA), this sub-trigger system mainly consisted of the optical fiber interface and the Ethernet interface. The former was used for signal transmission with global trigger and system, and the latter was used to communicate with host computer. Experimental tests were carried out to evaluate the performance of the sub-trigger system.Results & ConclusionsThe test results show that this sub-trigger system is suitable for external target experiment.  
        关键词：External target experiment;Sub-trigger selection system;Flash-type FPGA;Optical port;Ethernet;Performance test   
        351
        |
        22
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523436 false
        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “在材料计算模拟领域，VaspCZ程序大幅提高VASP计算效率，为材料理论研究提供便利。”
        ZHANG Zhengde,TAN Menglu,REN Cuilan,HUAI Ping
        Vol. 43, Issue 3, Article number: 030501(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030501
        摘要：BackgroundWith the improvement of computing power and the rise of high-throughput computing, researchers usually need to perform a large number of repeated instructions to submit scientific tasks and further check their computational results during material theoretical calculations. Generally, these instructions are simple, cumbersome and time consuming.PurposeThis study aims to improve the efficiency of scientific calculations by using VASP code.MethodsThe material theory calculation assistant program, VaspCZ, developed by using Python languages, is summarized to form a general github open source project, which provides detailed user documents, examples and application programming interfaces (API).ResultsVaspCZ, an efficient VASP computation assistant program includes two parts: the software part and API part. The software part provides the command line user interface, which enabled the researchers to complete the VASP calculations with the basic Linux command. The API part provides the bottom layer library to realize the custom calculation (such as high-throughput calculation, writing advanced application, etc.) for the researchers with python experiences.ConclusionsIt is proved by practice that the efficiency of theoretical calculation of materials using VASP can be significantly improved by aid of this assistant program.  
        关键词：First-principles;VASP;assistant program;electronic structure calculation;transient state calculation   
        357
        |
        27
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523340 false
        发布时间：2024-10-25
      • “在乏燃料组件运输容器临界安全研究领域，中国核工业集团有限公司专家建立了保守临界计算模型，验证了其设计满足法规标准，为乏燃料运输安全提供了解决方案。”
        ZHANG Min,WANG Jing,HONG Zhe,LI Xiaolong,ZHANG Liang,PAN Yuting
        Vol. 43, Issue 3, Article number: 030502(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030502
        摘要：BackgroundCritical safety index, as an important safety indicator for the transport container of spent fuel assembly, needs to be calculated and analyzed to determine whether it meets regulatory standards.PurposeThis study aims to analyze whether the critical safety design of the spent fuel assembly transport container of China national nuclear corporation (CNSC) meets the requirements of the “Regulations for the Safe Transport of Radioactive Material”.MethodsThe conservative critical calculation model was constructed by using Monte Carlo programs. The critical calculation of the spent fuel assembly transport container of the CNSC under normal and accident conditions was carried out, Both the overall effective multiplication coefficient, i.e.,keff, and the critical safety index were analyzed.ResultsThe analysis results show that the maximumkeff of a single package and package array is 0.804 25 under normal conditions, which is less than the subcritical limit and the critical safety index is 0; the maximumkeff of a single package and package array under the accident conditions is 0.813 17, which is also less than the subcritical limit and the critical safety index is 0.ConclusionUnder normal and accident conditions, the maximumkeff of the CNSC spent fuel assembly transport container is less than the subcritical limit of 0.94, and the critical safety index is 0, which meets the requirements of regulatory standards.  
        关键词：CNSC transport container;Critical safety analysis;Critical safety index   
        332
        |
        22
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523359 false
        发布时间：2024-10-25
      • “在液态铅铋合金冷却剂领域，专家利用fluent软件模拟氧化锂颗粒物运动，为铅铋合金系统净化提供参考。”
        LIU Peng,DU Xiaochao,HONG Feng,YUAN Xianbao
        Vol. 43, Issue 3, Article number: 030503(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030503
        摘要：BackgroundLiquid lead-bismuth alloy (LBE) is the preferred coolant material for the 4th generation liquid metal cooled fast reactor, but it is difficult to reduce the oxygen concentration. Theoretically, the oxygen concentration can be reduced by the reaction of hydride with oxygen. However, the reaction product insoluble microparticles will threaten the safe operation of the reactor.PurposeThis study aims at the floating law of particles in liquid lead-bismuth alloy that has significant reference for the collection of impurities and the purification of lead-bismuth alloy.MethodsThe fluent software was used to analyze and simulate the movement of solid particles in a cylindrical box. The standard k-ε model was adopted for continuous phase whilst the discrete phase model (DPM) was used for solid phase particulate matter to study the movement of particles in lead-bismuth alloy.Results & ConclusionThe distribution of the large diameter particles is close to the axial center of the cylinder, and the distribution of the small diameter particles is farther from the axial position than that of the larger particles. The particles with large diameter have a short floating time, the particles with small diameters have a long floating time, and the temperature has little influence on the floating time and can be ignored. With a radius of about 90 mm around the central axis, the concentration of the particles is 2~3 times higher than that of other positions. Therefore, the attention should be paid to this range when purifying the lead-bismuth alloy, and the efficiency and effect of purification are good.  
        关键词：Lead-bismuth alloy;Particulate matter;Floating motion   
        319
        |
        20
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523688 false
        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在核能领域，研究人员基于FLiBe载体盐，通过在线添加反应堆级钚，实现了熔盐堆233U的自持和焚烧反应堆级钚的能力。研究发现，在熔盐体积占比为10%~85%的较大范围内都可以实现233U自持，其中约43%熔盐体积比下233U增殖效果最佳。同时，43%熔盐占比下对钚的依赖最大，在熔盐体积比较小和较大时对钚的依赖较小；在熔盐体积比较小时更有利于钚的利用，其中在熔盐体积比为10%~15%时钚的焚烧率最大，约为75%。此外，中子损失率与钚的依赖近似呈正比关系，对233U自持性能影响较小。”
        YU Changqing,ZHU Guifeng,XIA Shaopeng,ZOU Yang,YU Xiaohan
        Vol. 43, Issue 3, Article number: 030601(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030601
        摘要：BackgroundThorium-uranium sustainability of molten salt reactor usually relies heavily on online reprocessing technology, which is still immature at the present.PurposeThe study aims to use reactor-grade plutonium online to achieve233U self-sustaining and burn reactor-grade plutonium based on the FLiBe carrier salt and Th/233U starter reactor.MethodsBased on Scale6.1, the program of molten salt reactor feeding and reprocessing sequence (MSR-RRS) was developed. The database ENDF /B-VII Library of group 238 was adopted for simulation.Single cell models were used to analyze the performance of233U self-sustaining and plutonium utilization at different molten salt volume fraction (VF) and neutron loss ratio.Results & ConclusionsIt is found that233U self-sustaining could be achieved in a large range from 10%VF to 85%VF, and233U have the best breeding ability at about 43%VF, of which the utilization of plutonium is worst. When the VF becomes smaller or larger, the utilization of plutonium always becomes smaller. It is more beneficial to burn plutonium in the low VF region. When VF is 10%~15%, the burning ratio of plutonium is the highest, corresponding to 75%. In addition, the neutron loss ratio is positively proportional to the burnup of plutonium, and has little influence on the self-sustaining performance of233U.  
        关键词：Thorium molten salt reactor;Thorium-uranium sustainability;Reactor-grade plutonium;Fuel utilization   
        319
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523598 false
        发布时间：2024-10-25
      • “在自然循环铅基快堆热工水力设计领域，研究了一回路腔室几何结构对堆芯流量分配特性的影响，为堆芯流量分配特性优化提供了参考。”
        WANG Tianshi,ZHAO Pengcheng,LIU Zijing,XIE Jinsen
        Vol. 43, Issue 3, Article number: 030602(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030602
        摘要：BackgroundThe flow distribution characteristic of core is an important consideration in the design of natural circulation lead-based fast reactor. The primary chamber geometry is one of the important factors affecting the flow distribution characteristic of core.PurposeThis study aims to investigate the effects of the height of the chamber riser, the radius and length of the central measuring column, the depth of the lower chamber, the aspect ratio and the height of the diversion structure on the flow distribution characteristics of the core.MethodsComputational fluid dynamics (CFD) method was employed to simulate the primary flow field of the natural circulation lead-based fast reactor SNCLFR-10, and the influence of the primary chamber geometry on the flow distribution characteristics was studied by changing the primary chamber geometry and observing the flow distribution characteristics of the core.Results & ConclusionsVarying the height of the rising chamber, the radius of the central measuring column and the length of the measuring column in the geometric structure of the upper chamber results in a significant influence of core flow while changing the depth and aspect ratio of the lower chamber has no noteworth effect on the total flow and flow distribution of the core. The flow field in the lower chamber can be improved obviously by adding the angular convex diversion structure in the lower chamber, but its influence on the total flow and flow distribution of the core is not significant.  
        关键词：Primary circuit plenum;Flow distribution characteristics;Lead-based fast reactor;Natural circulation   
        324
        |
        20
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523509 false
        发布时间：2024-10-25
      • “在核反应堆严重事故研究领域，通过可视化实验方法，采用铅锡合金模拟材料，研究了堆芯熔融物与冷却剂相互作用现象，揭示了热细粒化过程的关键影响因素，为核安全研究提供了新思路。”
        LI Ge TONG Lili
        Vol. 43, Issue 3, Article number: 030603(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030603
        摘要：BackgroundFuel coolant interaction (FCI) is one of the possible serious problems in severe accidents of nuclear power plants.PurposeThis study aims to further understand FCI phenomenon and key factors affecting the process of thermal fine fragmentation.MethodsVisualized experiments were performed using Pb-Sn alloy. Images of the reaction process were acquired through a high-speed video system, the area of pixels occupied by the molten materials was calculated to obtain the cross-sectional area of interaction zone. Melt debris was collected to investigate, the effects of initial melt temperature, melt mass and coolant temperature from three aspects: the morphology of experimental products, the state of interaction process and the gas distribution around molten materials.Results & ConclusionsThe comparative analysis results show that with the increase of melt temperature, thermal fine fragmentation is enhanced first and then reduced. With fixed water volume, improving the quality of the molten materials may lead to insufficient thermal fragmentation. High sub-cooling temperature is beneficial to thermal fine fragmentation of molten materials in FCI process.  
        关键词：FCI;Thermal fragmentation;Severe accident   
        320
        |
        19
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523527 false
        发布时间：2024-10-25
      • “在聚变堆中子学分析领域，中国专家利用GEANT4程序，建立了CFETR模型，验证了其在聚变中子学分析中的适用性，为聚变堆设计和安全运行提供重要参考。”
        REN Jincai,XU Kun,YE Minyou,MAO Shifeng,LU Yudong
        Vol. 43, Issue 3, Article number: 030604(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030604
        摘要：BackgroundNeutronics analyses plays a pivotal role in the design and safe operation of fusion reactors, especially the tritium breeding blanket. Simulation based on Monte Carlo methods is commonly used in fusion neutronics analyses.PurposeThis paper aims to study the application of GEANT4 Monte Carlo simulation toolkit for fusion neutronics analyses of CFETR (China Fusion Engineering Test Reactor).MethodsVerification calculations of G4NDL libraries were carried out to validate the applicability of libraries. Both the 1D model and the 3D model of CFETR were constructed successfully in GEANT4 by means of hard-coded programming and the McCAD conversion method, respectively. Neutron source and scoring methods were set up. A new process was implemented in GEANT4 to achieve the reflective surface function.ResultsNeutron wall loading results show that the deviations between results of GEANT4 and results of MCNP are less than 1%, which validates the effectiveness of this process. The CFETR neutronics analyses model was constructed successfully in GEANT4.ConclusionsThis work validates the application feasibility of GEANT4 for fusion neutronics analyses.  
        关键词：Fusion neutronics;GEANT4;CFETR   
        366
        |
        22
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523625 false
        发布时间：2024-10-25
      • “在EAST装置上，通过在线辐射剂量监测系统，研究了不同加热模式下中子、γ辐射剂量的变化规律。发现在中性束注入加热时，中子与γ剂量当量存在线性关系，为辐射防护提供了重要参考。”
        ZHOU Mengjie,HU Liqun,ZHONG Guoqiang,HUANG Liangsheng,LI Kai,ZHOU Ruijie,HONG Bing,XIAO Min,ZHANG Ruixue
        Vol. 43, Issue 3, Article number: 030605(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030605
        摘要：BackgroundA pulsed hybrid radiation field will be generated by Experimental Advanced Superconducting Tokamak (EAST) during deuterium plasma discharge.PurposeThis study aims to explore the radiation doses of EAST under different heating modes to ensure the radiation safety.MethodsThe on-line radiation dose monitoring system of EAST was used to measure the neutrons and γ-rays radiation in the main hall of the device under various heating modes during the deuterium plasma experiment. Evolution of neutron and γ radiation intensity with time under ohmic heating, lower hybrid waves heating, neutral beam injection heating, and neutral beam and radio frequency waves collaborative heating were compared and analyzed.ResultsThe results showed that the main sources of radiation dose were high-energy γ(X)-rays and photoneutrons produced by runaway electrons bremsstrahlung radiation in the pure ohmic heating mode. The drop of the loop voltage effectively inhibited the generation of runaway electrons, and the radiation dose level under lower hybrid waves heating mode was lower than that of ohmic heating mode. The beam target reaction increased the neutron yield by 2-3 orders of magnitude. The approximate linear relationship between neutron and γ ambient dose equivalent was found by statistical induction under neutral beam injection heating mode, but it was not completely applicable to the situation that the neutrons and γ-rays came from various ways when the neutral beam and radio frequency waves were heated together.ConclusionThe study can lay a good foundation for the establishment of fusion radiation dose database.  
        关键词：EAST;Radiation dose;Heating mode;Neutron;γ-ray   
        331
        |
        21
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523664 false
        发布时间：2024-10-25
      • “在高温核一级管道领域，专家利用PepS软件对钍基熔盐堆回路管道进行蠕变-疲劳损伤分析，满足蠕变疲劳极限要求。”
        GONG Wei,ZHANG Xiaochun,WANG Xiaoyan,XUE Jingyi,FU Yuan
        Vol. 43, Issue 3, Article number: 030606(2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.030606
        摘要：BackgroundThe pipe of thorium molten salt reactor-liquid fuel (TMSR-LF1) has been designed to operate at 650 ℃ for a long time, therefore, it is extremely important to analyze its creep-fatigue damage. At present, the provisional creep-fatigue damage evaluation is only stipulated in ASME-BPVC-III-5-HBB, and the evaluation is too cumbersome to realize for complex piping systems.PurposeThis study aims to apply PepS to analysis and evaluate class 1 nuclear piping at elevated temperature.MethodsThe analytical predictions of stress components and associated linearization of stress results through wall thickness of the pipe paths were successfully benchmarked with those given by finite element analysis (FEA), and good matching results was obtained. Finally, the structural analysis and structural integrity assessment procedures for the design structure of TMSR-LF1 on PepS are performed.ConclusionsThe study establishes effective connection between the ASME evaluate method and the pipe analysis software and clarifies the evaluation method. Hence, the creep-fatigue evaluation of class 1 nuclear complex piping system at elevated temperature is realized.  
        关键词：TMSR-LF1;Pipe;PepS;Creep-fatigue;High temperature   
        340
        |
        25
        |
        0
        <HTML>
        <L-PDF><Meta-XML>
        <引用本文> <批量引用> 1523759 false
        发布时间：2024-10-25
      0