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Investigating thermal and mechanical behavior for two thorium fuel types in a PWR

ANNALS OF NUCLEAR ENERGY 2025年 219卷

作者： Refaey, Ahmed M. Wasfy, Samaa A. Hassan, Mohga I. Egyptian Atom Energy Author EAEA Cairo Egypt

Thorium, as a nuclear fuel, has been the subject of intensive research for many years. One of the options is the adoption of thorium in currently operated nuclear PWRs. In this work two combinations of thorium fuel are investigated. The first contains thorium with uranium, while the second contains thorium with plutonium. The present research aims at studying the thermal and mechanical behavior of the fuel rod and clad under the steady state conditions. Coupling is applied between MCNP6 and ansys-17.2 (FLUENT and Static Structure) codes to obtain temperature and power distribution. An iterative process is associated with the exchange of data between codes to meet the convergence criteria, starting by the thermal-hydraulic ansys-FLUENT model to calculate actual temperature distributions of fuel, clad and coolant;these results are used in the MCNP code to determine the axial power distribution in the fuel rod. The value and the location of the maximum thermal stress of the fuel and clad are demonstrated. The results showed that thorium Uranium fuel has a better behavior and thus reducing stress on clad.

关键词： Thorium fuel Steady stat conditions Mechanical analysis Thermal stress ansys code MCNP6

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Probabilistic analysis of micro-machined fixed-fixed beam for reliability

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MICRO & NANO LETTERS 2008年第3期3卷 95-100页

作者： Islam, Md. Fokhrul Ali, M. A. Mohd. Majlis, B. Y. Univ Kebangsaan Malaysia Fac Engn & Built Environm Dept Elect Elect & Syst Engn Bangi 43600 Selangor Malaysia Univ Kebangsaan Malaysia IMEN Bangi 43600 Selangor Malaysia Univ Kebangsaan Malaysia Inst Space Sci ANGKASA Bangi 43600 Selangor Malaysia

A realistic approach for modelling a fixed-fixed beam is presented. The use of probabilistic methods to assess the electromechanical behaviour of the beam under the presence of micro-machine manufacturing and process uncertainties is demonstrated. A finite-element model of the beam is constructed using the commercial code ansys (10.0). In the standard approach of modelling, existing literature assumes deterministic values for design parameters, however, fabrication of the device introduces some amount of variation in the design parameters. Here, the probabilistic approach is discussed to account for the variability in fabrication. Probabilistic analysis guides the design of the fixed-fixed beam to achieve a robust and reliable design in the most efficient way. The results of the probabilistic design approach on the performance characteristics such as maximum deflection and maximum stress will be discussed.

关键词： reliability probabilistic analysis Reliability Design and modelling of MEMS and NEMS devices Probability theory, stochastic processes, and statistics Micromechanical and nanomechanical devices and systems Finite element analysis Probability and statistics Numerical approximation and analysis micromachined fixed-fixed beam probability finite-element model micromechanical devices design parameters beams (structures) micromachining ansys code microelectromechanical systems finite element analysis

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Implementation of a low-activation Au-In-Cd decoupler into the J-PARC 1 MW short pulsed spallation neutron source

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NUCLEAR MATERIALS AND ENERGY 2018年 14卷 14-21页

作者： Teshigawara, M. Ikeda, Y. Ooi, M. Harada, M. Takada, H. Kakishiro, M. Noguchi, G. Shimada, T. Seita, K. Murashima, D. Fukatani, K. Kanomata, K. Teraoku, T. Japan Atom Energy Agcy J PARC Ctr 2-4 Shirakata Tokai Ibaraki 3191195 Japan Met Technol Co Ltd 713 Syaka Ebina Kanagawa 2430424 Japan

A silver-indium-cadmium (Ag-In-Cd, or AIC) alloy with a 1 eV high neutron cut-off energy was originaly developed as a decoupler to provide a narrow neutron pulse width with a short tail for the J-PARC 1-MW short-pulsed spallation neutron source. As a result of later studies, gold (Au) was chosen as a substitute for Ag for the production of spare decoupled moderators and reflector in order to reduce residual radioactivity thus easing handling and disposal of the spent moderator and reflector. The decoupler material Au-In-Cd (AuIC) was therefore investigated and developed. To implement it into an actual moderator-reflector assembly many critical engineering issues needed to be resolved with regard to large-sized bonding between AuIC and aluminum alloy A5083 by the hot isostatic pressing process (HIP). The HIP process for AuIC and aluminum was investigated in terms of surface condition, size, and heat capacity. Implementation of an AuIC decoupler into a spare reflector assembly was successfuly achieved and will result in a remarkable reduction of radioactivity compared to AIC without sacrificing neutronic performance.

关键词： 1 MW short pulsed spallation neutron source Decoupler Neutron absorber Gold-indium-cadmium (Au-In-Cd) alloy Silver-indium-cadmium (Ag-In-Cd) alloy Hot isostatic pressing (HIP) Moderator-reflector assembly Ultrasonic transmission Aluminum alloy (A5083) ansys code

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Thermal analysis of DTL in the SSC-LINAC

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Chinese Physics C 2011年第10期35卷 952-954页

作者：吴锡袁平何源马力祯张小奇吴巍杨雅青 Institute of Modern Physics Chinese Academy of Sciences Graduate University of Chinese Academy of Sciences

A linear accelerator as a new injector for the Separated Sector Cyclotron at the Heavy Ion Research Facility of LAN Zhou is being designed. The Drift-Tube-Linac （DTL） has been designed to accelerate ^238U^34＋ from 0.140 MeV/u to 0.97 MeV/u [1]. The 3D finite element analysis of thermal behavior is presented in this paper. During operation, the cavity will produce Joule heat. The cavity will not work normally due to the high temperature and thermal deformation will lead to frequency drift, So it is necessary to perform thermal analysis to ensure the correct working temperature is used. The result of the analysis shows that after the water cooling system is put into the cavity the temperature rise is about 20 degrees and the frequency drift is about 0.15%.

关键词： finite element method coupling field frequency drift ansys code

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Multi-physics analysis of the RFQ for Injector Scheme Ⅱ of C-ADS driver linac

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Chinese Physics C 2014年第10期38卷 97-101页

作者：王静黄建龙何源张小奇张周礼石爱民 Lanzhou University of Technology Institute of Modern Physics Chinese Academy of Sciences

A 162.5 MHz, 2.1 MeV radio frequency quadruples （RFQ） structure is being designed for the Injector Scheme Ⅱ of the China Accelerator Driven Sub-critical System （C-ADS） linac. The RFQ will operate in continuous wave （CW） mode as required. For the CW normal conducting machine, the heat management will be one of the most important issues, since the temperature fluctuation may cause cavity deformation and lead to the resonant frequency shift. Therefore a detailed multi-physics analysis is necessary to ensure that the cavity can stably work at the required power level. The multi-physics analysis process includes RF electromagnetic analysis, thermal analysis, mechanical analysis, and this process will be iterated for several cycles until a satisfactory solution can be found. As one of the widely accepted measures, the cooling water system is used for frequency fine tunning, so the tunning capability of the cooling water system is also studied under different conditions. The results indicate that with the cooling water system, both the temperature rise and the frequency shift can be controlled at an acceptable level.

关键词： frequency shift multi-physics analysis finite element method ansys code

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Flow Field and Thermal Analysis of the Divertor Target Plate for HL-2A Tokamak

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Plasma Science and Technology 2005年第5期7卷 2989-2993页

作者：施乐 Southwestern Institute of Physics

In the initial phase of the physics experiment, the double-null divertor plates used consist of graphite armor tiles, Mo-alloy intermediate layers and Cu-alloy coolant tubes. In the later operating phase, tungsten will be used as armor tiles. A multi-physical field numerical analysis method is used in this paper. Its analysis model reflects more realistically the real divertor structure than other models. Two-dimensional （2D） and three-dimensional （3D） fluid flow field, temperature distribution and thermal stress analyses of the divertor plates are carried out by the ansys code. During the physics experimental phase with a heat flux of 1 MW/m2, a coolant velocity of 5.48 m/s, and a thermal stress of 750 kg/cm2, the graphite armor tiles successfully meet the requirements of temperature, thermal stress and sputtering erosion. The tungsten armor will be considered as a second candidate. The result of simulation can be used for upgrading the design parameters of the HL-2A poloidal divertor.

关键词： fluid flow field thermal stress computer simulation divertor target plate fluid calculation ansys code

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Impact of the monoblock thickness in an ITER-like configuration of DEMO divertor

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FUSION ENGINEERING AND DESIGN 2018年第PartB期136卷 1322-1326页

作者： Maviglia, Fabio Roccella, Selanna Crescenzi, Fabio Visca, Eliseo Carlini, Maurizio Univ Tuscia DEIM Via Paradiso 47 I-01100 Viterbo Italy ENEA Dept Fus & Technol Nucl Safety & Secur Rome Italy

The thermal-mechanical analyses carried out on the DEMO Divertor tungsten monoblocks have shown that the fatigue lifetime of the CuCrZr tube and copper interlayer, under cyclic thermal loads, depends on the axial thickness of the W. One of the monoblocks thickness currently considered for plasma facing component of the DEMO divertor is 4 mm. This configuration is compared with ITER design, where the W thickness is 12 mm. Both configurations have been simulated in ansys Workbench environment. In this paper, not the single monoblock, but an entire plasma facing unit (PFU) is analyzed with its constraints to the cassette. The FEM model consists of a CuCrZr tube 60 mm long, corresponding to the distance between two successive support attachment to the cassette as well in the current ITER divertor design. Between the W monoblocks and the tube 1 mm of pure copper interlayer is present. Appropriate symmetry conditions allow to simulate the entire PFU. The pipe and interlayer materials have elasto-plastic behavior, while the monoblock Tungsten is considered to have linear elastic properties. In this study the plastic fatigue lifetime of the CuCrZr tube and the copper interlayer has been estimated by applying a cyclic heat flux (20 MW/m(2)) to the surface of the tungsten armor.

关键词： Demo divertor Critical heat flux (CHF) High heat flux (HHF) ansys code ITER SDC-IC criteria

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Design study of ITER-like divertor target for DEMO

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FUSION ENGINEERING AND DESIGN 2015年 98-99卷 1263-1266页

作者： Crescenzi, Fabio Bachmann, C. Richou, M. Roccella, S. Visca, E. You, J. -H. ENEA CR Frascati Unita Tecn Fus ENEA I-00044 Frascati Roma Italy EFDA Power Plant Phys & Technol D-85748 Garching Germany CM IRFM F-13108 St Paul Les Durance France Max Planck Inst Plasma Phys D-85748 Garching Germany

A near-term water-cooled target solution has to be evaluated together with the required technologies and its power exhaust limit under 'DEMO' conditions. The ITER-like design concept based on the mono-block technology using Was armour material and the CuCrZr-IG as structural material with an interlayer of pure copper represents a promising solution also for DEMO. This work reports the design study of an "optimized" ITER-like Water Cooled Divertor able to withstand a heat flux of 10 MW m(-2), as requested for DEMO operating conditions. The optimization of plasma facing unit (PFU) aims to enhance the thermo-mechanical behaviour of the component by varying some geometrical parameters (monoblock size, interlayer thickness and, tube diameter and thickness). The optimization was performed by means of the multi-variable optimization algorithms using the FEM code ansys. The coolant hydraulic conditions (inlet pressure, temperature and velocity) were fixed for simplicity. This study is based on elastic analysis and 3 dimensional modelling. The resulting optimized geometry was evaluated on the basis of the ITER SDC-IC criteria and in terms of low cycle fatigue (LCF). The margin to the critical heat flux (CHF) was also estimated. Further design study (taking into account the effect of neutron radiation on the material properties) together with mock-up fabrication and high-heat-flux (HHF) tests are foreseen in next work programmes. (C) 2015 Elsevier B.V. All rights reserved.

关键词： Demo divertor Critical heat flux (CHF) High heat flux (HHF) ansys code ITER SDC-IC criteria

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Thermal Deformation Analysis and Electron Beam Optics Simulation for a Thermionic Electron Gun Design

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JOURNAL OF THE KOREAN PHYSICAL SOCIETY 2018年第8期73卷 1042-1048页

作者： Jang, Seungsoo Hwang, Jihyun Park, Sung-Ju Namkung, Won Cho, Moohyun Seo, Hyeong-Seok Pohang Univ Sci & Technol Dept Phys Pohang 37673 South Korea Pohang Accelerator Lab Pohang 37874 South Korea Pohang Univ Sci & Technol Dept Adv Nucl Engn Pohang 37673 South Korea Vitzrotech Co Ansan 15603 South Korea

When the thermionic electron gun of the klystron operates, the structure around the cathode is subjected to thermal deformation due to the high operating temperature of the cathode. A thermal deformation analysis of the existing electron gun with cold' dimensions (dimension on fabrication) was done using the ansys code to get the hot' dimensions of the electron gun on operation. After that, the optics of the emitted electron beam were simulated using two codes (EGUN and CST-PS) for the two cases of the cold' dimension and the hot' dimension. We compared the beam trajectories of the above two cases to investigate the change in the physical quantities, which would have a strong effect on the klystron performance due to the thermal deformation. The thermal deformation was found to cause a perveance change as large as 15%. The scalloping behavior was also investigated with an applied magnetic field for the two cases of cold and hot dimensions.

关键词： Klystron Electron gun Thermal deformation ansys code EGUN code CST code

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Comparison between FEM and high heat flux thermal fatigue testing results of ITER divertor plasma facing mock-ups

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FUSION ENGINEERING AND DESIGN 2014年第7-8期89卷 985-990页

作者： Crescenzi, F. Roccella, S. Visca, E. Moriani, A. Assoc EURATOM ENEA Fus CR Frascati IT-00044 Frascati Italy

The divertor is one of the most challenging components of "DEMO" the next step ITER machine, so many tasks regarding modeling and experiments have been made in the past years to assess manufacturing processes, materials and thus the life-time of the components. In this context the finite element analysis (FEA) allows designers to explore multiple design options, to reduce physical prototypes and to optimize design performance. The comparison between the hydraulic thermal-mechanical analysis performed by ansys WORKBENCH 14.5 and the test results [1] on small-scale mock-ups manufactured with the Hot Radial Pressing (HRP) [2] technology is presented in this paper. During the thermal fatigue testing in the Efremov TSEFEY facility to assess the heat flux load-carrying capability of the mock-ups, only the surface temperature was measured, so the FEA was important because it allowed to know any other information (temperature inside the materials, local water temperature, local stress, etc.). FEA was performed coupling the thermal-hydraulic analysis, that calculated the temperature distributions on the components and the heat transfer coefficient (HTC) between water and heat sink tube, with the mechanical analysis. The comparison between analysis and testing results was based on the temperature maps of the loaded surface and on number of the cycles supported during the testing and those predicted by the mechanical analysis using the experimental fatigue curves for CuCrZr-IG, that is the structural material in the component. Also the behavior for Cu-OFHC interlayer material based on the experimental fatigue curves was considered and the ultimate tensile strength for W, because their failure affects the heat removal capability of the component. The good correlation found between PEA result S and testing campaign validated again the use of PEA itself for future design improved concepts. (c) 2014 EURATOM-ENEA Association. Published by Elsevier B.V. All rights reserved.

关键词： PFC Non-destructive testing (NDT) High heat flux testing (HHF) Computational fluid dynamic (CFD) ansys code

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