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Processing of a comprehensive windowed multipole library via vector fitting

Processing of a comprehensive windowed multipole library via...

2018 International Conference on Physics of reactors: reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018

作者： Liang, Jingang Peng, Xingjie Liu, Shichang Josey, Colin Forget, Benoit Smith, Kord Department of Nuclear Science and Engineering Massachusetts Institute of Technology CambridgeMA02139 United States Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China ChengduSichuan610000 China Department of Engineering Physics Tsinghua University Beijing100084 China

ISBN: (纸本)9781713808510

The windowed multipole method is a promising technique to efficiently perform Doppler broadening of nuclear cross section data and has so far been based on the conversion of resolved resonance parameters to the pole representation. However, 40% of ENDF/B-VII. 1 nuclides cannot be directly converted in windowed multipole format because some nuclides are provided directly as point-wise data in the evaluation or the presence of non-smooth point-wise data that prevents the transformation. A new approach based on Vector Fitting technique was recently investigated to convert point-wise cross section data to poles and residues. This paper presents a generalized Vector Fitting algorithm which is able to generate optimized multipole parameters from ENDF point-wise data and applicable to a wide range of nuclides. Using this algorithm, a comprehensive windowed multipole library which contains all ENDF/B-VII.l nuclides was produced for the first time. Accuracy of the library was demonstrated by microscopic cross section comparisons at different temperatures, and calculation results of the BEAVRS benchmark were performed to demonstrate its applicability to realistic problems. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient Systems. All rights reserved.

关键词： Doppler effect

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Current nuclear data needs for applications

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Physical Review Research 2022年第2期4卷 021001-021001页

作者： Karolina Kolos Vladimir Sobes Ramona Vogt Catherine E. Romano Michael S. Smith Lee A. Bernstein David A. Brown Mary T. Burkey Yaron Danon Mohamed A. Elsawi Bethany L. Goldblum Lawrence H. Heilbronn Susan L. Hogle Jesson Hutchinson Ben Loer Elizabeth A. McCutchan Matthew R. Mumpower Ellen M. O'Brien Catherine Percher Patrick N. Peplowski Jennifer J. Ressler Nicolas Schunck Nicholas W. Thompson Andrew S. Voyles William Wieselquist Michael Zerkle Nuclear and Chemical Sciences Division Lawrence Livermore National Laboratory Livermore California 94550 USA Department of Nuclear Engineering University of Tennessee Knoxville Tennessee 37996 USA Department of Physics and Astronomy University of California Davis California 95516 USA IB3 Global Solutions Oak Ridge Tennessee 37830 USA Physics Division Oak Ridge National Laboratory Oak Ridge Tennessee 37831 USA University of California Department of Nuclear Engineering Berkeley California 94720 USA Nuclear Science Division Lawrence Berkeley National Laboratory Berkeley California 94720 USA National Nuclear Data Center Brookhaven National Laboratory Upton New York 11973 USA Design Physics Division Lawrence Livermore National Laboratory Livermore California 94550 USA Rensselaer Polytechnic Institute Department of Mechanical Aerospace and Nuclear Engineering 110 8th Street Troy New York 12180 USA Signature Science and Technology Division Pacific Northwest National Laboratory Richland Washington 99352 USA Xe-Mobile Division X-Energy LLC Rockville Maryland 20852 USA Radioisotope Science and Technology Division Oak Ridge National Laboratory Oak Ridge Tennessee 37831 USA NEN-2 Advanced Nuclear Technology Los Alamos National Laboratory Los Alamos New Mexico 87545 USA Theoretical Division Los Alamos National Laboratory Los Alamos New Mexico 87545 USA Chemistry Division Los Alamos National Laboratory Los Alamos New Mexico 87545 USA Nuclear Criticality Safety Division Lawrence Livermore National Laboratory Livermore California 94550 USA Johns Hopkins University Applied Physics Laboratory Laurel Maryland 20723 USA Nuclear Energy and Fuel Cycle Division Oak Ridge National Laboratory Oak Ridge Tennessee 37831 USA Reactor Technology Department Naval Nuclear Laboratory West Mifflin Pennsylvania 15122 USA

Accurate nuclear data provide an essential foundation for advances in a wide range of fields, including nuclear energy, nuclear safety and security, safeguards, nuclear medicine, and planetary and space exploration. In these and other critical domains, outdated, imprecise, and incomplete nuclear data can hinder progress, limit precision, and compromise safety. Similar nuclear data needs are shared by many applications, thus prioritizing these needs is especially important and urgently needed. Many levels of analysis are required to prepare nuclear measurements for employment in end-user applications. Because research expertise is typically limited to one level, collaboration across organizations and international borders is essential. This perspective piece provides the latest advances in nuclear data for applications and describes an outlook for both near- and long-term progress in the field.

关键词： Nuclear engineering Nuclear reactors Quantum computation Monte Carlo methods Nuclear data analysis & compilation

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Subcooled boiling natural convective two-phase CFD simulation and application

Subcooled boiling natural convective two-phase CFD simulatio...

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International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting

作者： Li, Songwei Puragliesi, Riccardo Adamsson, Carl Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Box 436 Chengdu China Paul Scherrer Institut Villigen5232 Switzerland Vattenfall Nuclear Fuel AB Stockholm Sweden

This Paper presents sub-cooled boiling two-phase natural convective using computational fluid dynamics(CFD) model for the application to the passive residual heat removal system of boiling water reactor. Sensitivity studies on meshing scheme, grid size, as well as time step are also performed in previous study to minimize the influence of numerical discretization. Comparison between single/ two-phase CFD model proved the necessity of two-phase CFD model as it can reasonably predict the temperature jump observed in the experiment which could not be reproduced by single phase CFD model. Discrepancy between numerical simulation and experiment data due to the choice of different turbulent models and CFD software’s simulation results are also discussed in order to verify the best practice for this simulation.. The calculation shows that the the temperature distribution, bubble appearance time and locus predicted by the two-phase CFD simulation for sub-cooled boiling natural convective is well consistent with experiment data, which confirms the numerical calculation creditability and accuracy and the possibility for developing new heat transfer model using such methodology is reasonably suggested.. Base on the built two-phase CFD simulation method, transient characteristics of passive residual heat removal system for ESBWR（Economic Simplified Boiling Water reactor）is simulated and a promising tank temperature distribution is obtained compared with experiment data, which further strengthen the confidence of engineering application of two-phase CFD model on prediction of natural circulation heat transfer characteristic of passive residual heat removal system. © 2018 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting. All rights reserved.

关键词： Computational fluid dynamics

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A pinacol boronate caged NIAD-4 derivative as a near-infrared fluorescent probe for fast and selective detection of hypochlorous acid

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Chinese Chemical Letters 2018年第1期29卷 139-142页

作者： Hongjuan Tong Yajun Zhang ShengnanMa Minghao Zhang Na Wang Rui Wang Kaiyan Lou Wei Wang Shanghai Key Laboratory of New Drug Design Shanghai Key Laboratory of Chemical Biology School of Pharmacy State Key Laboratory of Bioengineering Reactor East China University of Science & Technology Shanghai 200237 China Department of Chemistry and Chemical Biology University of New Mexico Albuquerque NM 87131-0001 USA

Hypochlorous acid （HOCI） is one of highly reactive oxygen species （ROS）. It is involved in both immune defense against invading microbes and the progression of many diseases including cardiovascular disease and neurodegeneration disorders. It is generated from hydrogen peroxide （H2O2） and chloride ions in the presence of myeloperoxidase in activated neutrophils. To illustrate HOCI＇s biological functions, fluorescent probes, particularly those fluorescence emissions are in the near-infrared range, are highly needed for in vivo applications. Herein, we reported the design of a pinacol boronate caged near-infrared （NIR） fluorescent probe I derived from an Aft binding fluorophore NIAD-4 for fast and selective detection of HOC1/C10 over other ROS. Upon exposure to HOCI/CIO-, the pinacol boronate caging group of the probe 1 was quickly converted to electron-donating hydroxyl group, which increased intramolecular charge transfer OCT） in the excited state and resulted in the red-shift and intensity enhancement of fluorescence emission. The probe bears several unique features：（1） It could be used as either a ratiomatic or turn-on fluorescent probe; （2） Reaction of the caging group boronate with HOCI is very fast and finishes within seconds, which provides the selectivity over H2O2; （3） The NIAD-4 fluorophore provides additional selectivity for detection of HOCl over peroxynitrite. Moreover, the utility of the probe in imaging HOCllClO- was demonstrated in in vitro phantom imaging studies using mouse brain homogenate as biological relevant media.

关键词： Fluorescent probeHypochlorous acidBoronateReactive oxygen species （ROS）Near-infrared （NIR） imaging

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Ratcheting Behavior of SA508-3 Steel at Elevated Temperature:Experimental Observation and Simulation

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Acta Metallurgica Sinica(English Letters) 2017年第9期30卷 822-828页

作者： Jun Tian Yu Yang Li-Ping Zhang Xue-Jiao Shao Juan Du Qian-Hua Kan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Applied Mechanics and Structure Safety Key Laboratory of Sichuan Province School of Mechanics and EngineeringSouthwest Jiaotong University

A series of monotonic uniaxial tensile tests, strain-controlled and stress-controlled cyclic tests of SA508-3 steel were conducted from 25 to 350℃. Results showed that the steel exhibited temperature-dependent cyclic softening characteristic and obvious ratcheting behavior, and dynamic strain aging was observed in the range of 250-350℃. Based on experimental observations, a temperature-dependent cyclic plastic constitutive model was proposed by introducing the nonlinear cyclic softening and kinematic hardening rules, and the dynamic strain aging was also considered into the constitutive model. Comparisons between experiments and simulations were carded out to validate the proposed model at elevated temperature.

关键词： Ratcheting Constitutive model Dynamic strain aging Cyclic loading Elevated temperature

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Multi-objective Optimization of Non-uniform Beam for Minimum Weight and Sound Radiation

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Transactions of Tianjin University 2017年第4期23卷 380-393页

作者： Furui Xiong Mengxin He Yousef Naranjani Qian Ding Jianqiao Sun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China School of Mechanical Engineering Tianjin University School of Engineering University of California Merced

A multi-objective optimization of non-uniform beams is presented for minimum radiated sound power and weight. The transfer matrix method is used to compute the structural and acoustic responses of a non-uniform beam accurately and efficiently. The multi-objective particle swarm optimization technique is applied to search the Pareto optimal solutions that represent various compromises between weight and sound radiation. Several constraints are imposed, which substantially reduce the volume fraction of feasible solutions in the design space. Two non-uniform beams with different boundary conditions are studied to demonstrate the multi-objective optimal designs of the structure. © 2017, Tianjin University and Springer-Verlag Berlin Heidelberg.

关键词： Acoustic generators Acoustic properties Acoustic wave propagation Acoustic wave scattering Optimal systems Pareto principle Particle swarm optimization (PSO) Transfer matrix method

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Preliminary evaluation of U 3 Si 2 -FeCrAl fuel performance in light water reactors through a multi-physics coupled way

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Nuclear Engineering and design 2018年 328卷 27-35页

作者： Yanan He Ping Chen Yingwei Wu G.H. Su Wenxi Tian Suizheng Qiu Shaanxi Engineering Research Center of Advanced Nuclear Energy School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an City 710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China

U 3 Si 2 -FeCrAl fuel system is a potential choice for Accident Tolerant Fuel (ATF) for its higher uranium density, improved fuel thermal conductivity and stronger oxidation resistance. In this work, a new multi-physic fuel performance code called BEEs for LWR fuels has been developed based on Multiphysics Object-Oriented Simulation Environment (MOOSE) using the Object-Oriented Programming (OOP) method. As a first step to verify the capability of BEEs, one problem has been conducted using BEEs and compared with the results from BISON and ABAQUS. Then, the most recently available U 3 Si 2 -FeCrAl behavior models have been coded in BEEs. Fuel performance analysis was conducted for U 3 Si 2 -FeCrAl fuel system using BEEs and comparisons with UO 2 -Zr4 and U 3 Si 2 -Zr4 were made in this work. The results show that U 3 Si 2 -FeCrAl fuel system can lower the fuel peaking temperature about 300 K and have flat radial temperature distribution which can mitigate or eliminate the fuel cracking during power up. Further, the pellet-cladding mechanic interaction can be delayed or fully eliminated employing U 3 Si 2 -FeCrAl fuel system in light water reactors (LWRs).

关键词： U 3 Si 2 Multiphysics Fuel performance MOOSE BEEs

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Fatigue crack growth model for edge sliding mode 14

Fatigue crack growth model for edge sliding mode

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14th International Conference on Fracture, ICF 2017

作者： Shi, K.K. Zheng, B. Bai, X.M. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

The inherent law between fatigue behaviours of shear-type representative volume element and mode-II fatigue crack growth is found in the range of cycle plastic zone near the crack tip. Prediction models for mode-II fatigue crack growth rate are then proposed by utilizing shear-type low cycle fatigue properties, fatigue failure criterions (plastic strain energy and linear damage accumulation), and effective cycle stress-strain field ahead of the crack tip. Experimental data of two aluminium alloys, 2024-T351 and 7075-T6, are used for models verification. Good agreement between experimental and theoretical results is obtained. © 2017 ICF 2017 - 14th International Conference on Fracture. All rights reserved.

关键词： Fatigue crack propagation

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Stress intensity factors for penetrate radial cracks in reactor coolant pump flywheel by weight function method 14

Stress intensity factors for penetrate radial cracks in reac...

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14th International Conference on Fracture, ICF 2017

作者： Shi, K.K. Zheng, B. Gao, S.Q. Chen, J.G. Lv, X. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Stress intensity factors for penetrate radial crack at center of keyway and at keyway corner under the plane stress, the plane strain and the three dimensional, based on weight function method, is determined by finite element analysis. Two load cases of pin loading and uniform loading are considered in the present study. About stress intensity factors, finally, an approximate solution and results from weight function method are compared. Several loading are considered that lead to exact solutions which agree with the literature. The accuracy of the analysis has been examined using the finite element method results and were compared to existing solutions for uniform loading in the literature for special geometries, indicating an excellent agreement. © 2017 ICF 2017 - 14th International Conference on Fracture. All rights reserved.

关键词： Stress intensity factors

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Improved core design of the supercritical water-cooled reactor CSR1000

Improved core design of the supercritical water-cooled react...

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2017 Transactions of the American Nuclear Society, ANS 2017

作者： Wang, Lianjie Lu, Di Yang, Ping Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

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