Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel Assembly (Unknown)
- New search for: Liu, W.
- New search for: Bai, N.
- New search for: Shan, J.-q.
- New search for: Liu, W.
- New search for: Bai, N.
- New search for: Shan, J.-q.
In:
NUCLEAR POWER ENGINEERING
;
34
;
005-009
;
2013
-
ISSN:
- Article (Journal) / Print
-
Title:Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel Assembly
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Contributors:
-
Published in:NUCLEAR POWER ENGINEERING ; 34 ; 005-009
-
Publisher:
- New search for: HIDONGLI GONGCHENG
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Publication date:2013-01-01
-
Size:5 pages
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ISSN:
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Type of media:Article (Journal)
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Type of material:Print
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Language:Unknown
- New search for: 621.48
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Classification:
DDC: 621.48 -
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© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents – Volume 34
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 001
-
Study on Breeding of Fast Zone Assembly in SCWR-MShan, D.-y. / Yu, T. / Xie, J.-s. et al. | 2013
- 001
-
Two-Dimensional Matrix Characteristics Method Based on Krylov Subspace and Domain Decomposition TheoriesZhang, H.-b. / Wu, H.-c. / Cao, L.-z. et al. | 2013
- 001
-
Study on Fuel Loading Pattern Optimization for A Pressurized Water Reactor (PWR) Using Particles Warm MethodLiu, S.-c. / Cai, J.-j. et al. | 2013
- 001
-
Production of Pseudo Fission-Product for Transmutation of Fast ReactorHu, W.-c. / Liu, B. / Ouyang, X.-p. et al. | 2013
- 001
-
Overview of Research and Development (Phase I) on Key Technologies for Supercritical Water-Cooled ReactorXiao, Z.-j. / Li, X. / Huang, Y.-p. et al. | 2013
- 001
-
Method to Study Water Hammer with Fluid-Structure Interaction in Spatial PipeXi, Z.-d. / Ma, J.-z. / Sun, L. et al. | 2013
- 005
-
Study on Life Extension of AP1000 Nuclear Power Plant CORELiu, Z. et al. | 2013
- 005
-
Overview on Overall Design of CSR1000Li, X. / Li, Q. / Xia, B.-y. et al. | 2013
- 005
-
Coupled Neutronics/Thermal-Hydraulics Analysis of PT-SCWR Fuel AssemblyLiu, W. / Bai, N. / Shan, J.-q. et al. | 2013
- 005
-
Experimental Investigation of Hot Block Rewetting Process during Nuclear Reactor Emergency CoolingLiu, B. / Chen, D.-q. / Pan, L.-m. et al. | 2013
- 006
-
Two-Point Reactor Core Model for Pressurized Water Reactor and Its ApplicationWu, Y.-z. / Chen, s.-h. / Liu, Y. et al. | 2013
- 007
-
Study on Acceleration of Three Dimensional Characteristics MethodZhang, Z.-z. / Li, Q. / Wang, K. et al. | 2013
- 008
-
Study on Mismatch Phenomenon of Power Change and ReactivityXin, F. / You, G.-s. / Zhang, C.-m. et al. | 2013
- 009
-
Core Preliminary Conceptual Design of Supercritical Water-Cooled Reactor CSR1000Xia, B.-y. / Yang, P. / Wang, L.-j. et al. | 2013
- 009
-
Experimental Study on Flow Characteristics and Parameters Influences of Geysering Phenomena in HeatingQi, Z.-f. / Chen, J.-b. / Tong, L.-l. et al. | 2013
- 010
-
Deep Subcritical Levels Measurements Dependents upon Kinetic Distortion FactorsPan, S.-b. / Li, X. / Fu, G.-e. et al. | 2013
- 011
-
Study on Super Equivalence MethodLi, M.-c. / Wang, K. / Yao, D. et al. | 2013
- 012
-
Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP CodeHu, W.-c. / Ouyang, X.-p. / Liu, B. et al. | 2013
- 012
-
Neutronics Analysis Code System for Hybrid ReactorZu, T.-j. / Wu, H.-c. / Zheng, Y.-q. et al. | 2013
- 013
-
Analysis on CEA93 LibraryGuo, F.-c. / Wang, J.-c. / Lu, W. et al. | 2013
- 015
-
Preliminary Conceptual Design Study on Supercritical Water-Cooled Reactor CSR1000A with Annular FuelXia, B.-y. / Zhao, C.-q. / Cao, L.-z. et al. | 2013
- 016
-
CATHARE Simulation on Coupled Neutronics/Thermal-Hydraulics of Molten Salt Reactor (MSR)Peng, C.-x. / Yan, X. / Peng, J.-f. et al. | 2013
- 016
-
Model Development on Cooling of Debris Formed of Molten Material in Lower HeadYu, H.-x. / Lu, Q. / He, X.-q. et al. | 2013
- 016
-
Research on Calculation of PWR Coolant ^1^6N and ^1^7N Activity Source Terms Based on Transport Calculation MethodHu, J.-j. / Tang, B. / Yang, B. et al. | 2013
- 017
-
Application of Runge-Kutta Method in 3-D Coupled Netronics and Thermal-Hydraulics Transient AnalysisZhao, W.-b. / Yao, D. / Wang, K. et al. | 2013
- 018
-
Study on Development of ASCFR1.0/MC and Initial Calculation of Moderator Temperature Effect for ASCFRLi, Z.-f. / Yu, T. / Xie, J.-s. et al. | 2013
- 019
-
Primary Design and Calculation of a Breeder Supercritical Water Cooled Fast ReactorYu, T. / Liu, Z.-j. / Xie, J.-s. et al. | 2013
- 020
-
Real Time Thermal Hydraulic Model for High Temperature Gas-cooled Reactor CoreSui, Z. / Zhang, R.-p. / Sun, J. et al. | 2013
- 020
-
ERVC Effectiveness Analysis for Three-Layer Configuration Molten PoolCao, K.-m. / Xu, Y.-q. / Shi, G.-b. et al. | 2013
- 020
-
Neutronics Analysis for Core Assembly in Inverted Hydride-Fueled Pressurized Water ReactorZeng, Z.-k. / Yu, T. / Xie, J.-s. et al. | 2013
- 023
-
Effect of Variable Viscosity on Flow Resistance Characteristics of Porous Channel with Internal Heat SourceZhang, X.-n. / Sun, Z.-n. / Meng, X.-k. et al. | 2013
- 024
-
Study on 3D Nonlinear Seismic Analysis of Reactor StructureLiu, W.-j. / Wu, W.-j. / Lan, B. et al. | 2013
- 024
-
Study on Direct Extraction of Uranium from Uranium Oxides Powder Using Supercritical CO~2Li, J. / Zhu, C.-g. / Liu, X.-l. et al. | 2013
- 025
-
Effect of Fuel Assembly When Changing from AFA 2G to AFA 3G on Seismic Loads of Reactor InternalLiu, W.-j. / Zeng, Z.-x. / Ye, X.-h. et al. | 2013
- 025
-
Scaling Effect on Flow Characteristics of a Structured Packed Bed Using CFD MethodLi, J. / Song, X.-m. / Lu, J.-c. et al. | 2013
- 026
-
Study on Reactivity Control Method for Supercritical Water-Cooled Reactor CSR1000Xia, B.-y. / Yang, P. / Wang, L.-j. et al. | 2013
- 027
-
Study on Second-Order Scheme for One-Dimensional Two-Fluid Model of ReactorZhang, X.-y. / Ding, F. / Chen, J.-y. et al. | 2013
- 027
-
Optimized Design for TWR Assembly by CFD CalculationsLu, J.-c. / Lu, C. / Yan, M.-y. et al. | 2013
- 028
-
Study on Preparation of B~4C-Zircaloy Annular Burnable AbsorberLi, Y.-y. / Dai, S.-p. / Yang, J. et al. | 2013
- 030
-
Analysis of Fast Fracture of Core Region of RPVZhang, L.-p. / Zheng, L.-g. / Lu, Y.-c. et al. | 2013
- 030
-
Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRsZhang, K. / Wang, D.-z. / Ma, Y.-w. et al. | 2013
- 031
-
Research on 90^oElbow Structure Optimization for Main Coolant Piping of CPR1000 Nuclear Power PlantLi, Q.-b. / Zhang, X.-h. / Ren, H.-b. et al. | 2013
- 031
-
Performance Analysis on Two-Row Hexagonal Fuel Assembly for Super Critical Water-Cooled ReactorAn, P. / Wang, L.-j. / Pan, J.-J. et al. | 2013
- 032
-
Study on Cladding Oxidation Model Improvement in SCDAP/RELAP5Yu, H.-x. / He, X.-q. / Su, G.-h. et al. | 2013
- 033
-
Development of a New Model to Predict Heat Release in Vicinity of Quench Front in Tight LatticeWu, D. / Yu, H.-x. / Yu, J.-c. et al. | 2013
- 033
-
Comparison and Validation of Dynamic Characteristic Analytical Method for Tubular Heat ExchangerHuang, Q. / Xu, D.-g. / Chen, M. et al. | 2013
- 034
-
CFD Analysis of Effect of Helix Rib on Flow and Heat Transfer of Supercritical Water in Square Annular ChannelZhu, H.-y. / Yan, X. / Zeng, X.-k. et al. | 2013
- 035
-
Supercritical Fuel Assembly Design Applicable for Cruciform Control RodZhu, F.-w. / Lei, T. / Cheng, H.-y. et al. | 2013
- 036
-
Effect of Dynamic Structure Stiffness on Rotor Characteristics of Vertical PumpOu, M.-x. / Wang, Y. / Yan, J.-h. et al. | 2013
- 037
-
Effect of T1G Welding on Corrosion Resistance of Zirconium R60702Ling, K. / Wang, Z.-d. et al. | 2013
- 037
-
Analysis of Probabilistic Fracture Mechanics for PTS of Reactor Pressure VesselLiu, Z.-w. / Qiao, H.-w. / Zhang, Y. et al. | 2013
- 038
-
LES Calculations for Pressure and Velocity Transient Characteristics on Spacer Grids Outer RibbonsLu, C. / Lu, Q. / Zhang, H. et al. | 2013
- 040
-
Nuclear Auxiliary Pipe Whip and Whip Restraint Stress AnalysisYuan, F. / Lu, Y.-b. / Al, H.-l. et al. | 2013
- 040
-
Thermal-Hydraulic Analysis and Design Improvement for Coolant Channel of ITER Shield BlockZhao, L. / Li, H.-q. / Zheng, J.-t. et al. | 2013
- 040
-
Subchannel Analysis of SCWR CSR1000 AssemblyDu, D.-q. / Xiao, Z.-j. / Yan, X. et al. | 2013
- 041
-
Comparative Research of Finite Element Methods for Perforated Structures of Nuclear Power Plant Primary EquipmentsXiong, G.-m. / Deng, X.-y. / Jin, T. et al. | 2013
- 042
-
Effect of Hydrogen on Irradiation Stability of Dispersed Oxide Particles (Y~2O~3) in 12Cr-ODS SteelGuo, L.-n. / Hu, B.-f. / Jia, C.-c. et al. | 2013
- 043
-
Numerical Study on Single Phase Flow Resistance Characteristics in Randomly Packed Channel with SpheresZhang, N. / Sun, Z.-n. et al. | 2013
- 043
-
Analysis of Nonlinear Response of Cracked BeamsCai, F.-c. / Zhang, Y.-x. / Wang, M.-l. et al. | 2013
- 044
-
Fully Developed Laminar Flow in a Rolling Narrow Retangular DuctMa, J. / Huang, Y.-p. / Liu, X.-z. et al. | 2013
- 045
-
Flow Instability Analysis of Supercritical Water-Cooled Reactor CSR1000 based on Frequency DomainTian, W.-x. / Tian, X.-y. / Feng, J. et al. | 2013
- 045
-
Study on Application of Green's Function Method in Thermal Stress Rapid CalculationZhang, G.-h. / Duan, Y.-g. / Xu, X. et al. | 2013
- 046
-
Effect of Burn-off on Oxidation Rate of Nuclear GraphiteWang, P. / Yu, S.-y. et al. | 2013
- 047
-
Pressure Fluctuation Characteristics of Flow Field of Mixed Flow Nuclear Primary PumpWang, C.-l. / Yang, X.-y. / Li, C.-j. et al. | 2013
- 048
-
Modeling Research on PWR Fuel Assembly Lateral Non-linear CharacteristicsRu, J. / Xiao, Z. / Pu, Z.-p. et al. | 2013
- 048
-
Stationary Stochastic Seismic Response Analysis of Coupled Structures Interconnected by Hysteretic Dampers Subjected to Non-uniform Random Seismic Excitations with Pseudo Excitation PrincipleHuang, Q. / Zhang, F.-g. / Zhang, Y.-x. et al. | 2013
- 050
-
Research on Reflood Model of Narrow Channel Based on RELAP5Zeng, W. / Yu, H.-x. / Sun, Y.-f. et al. | 2013
- 051
-
Effect of Rolling Motion on Forced Circular Boiling Flow CharacteristicsWang, C. / Gao, P.-z. / Tan, S.-c. et al. | 2013
- 052
-
Evaluation of Influence of Diffuse Earthquakes Based on Near-Source Ground Motion Acceleration RecordingsWu, J. / Yu, Y.-x. / Pan, H. et al. | 2013
- 052
-
Research on Overall Structure Design of CSR1000Zhang, H.-l. / Luo, Y. / Li, X. et al. | 2013
- 052
-
Numerical Research on Hydraulic Performance of ACPR1000^+ ReactorZhang, M.-q. / Duan, Y.-g. / Yu, X.-l. et al. | 2013
- 053
-
Turbulent Heat Transfer Characteristics of Liquid Sodium Flow in an Annular TubeWang, M. / Wu, Y.-w. / Tian, W.-x. et al. | 2013
- 055
-
Development and Abecedarian Verification of Reactor Core Physic and Thermal-Hydraulic Analysis Software Package DCNMCZhou, X.-h. / Cai, Q. / Wang, D.-y. et al. | 2013
- 056
-
Development of Digital Centralized Data Acquisition System for ReactorsDai, H.-y. / Deng, S. / Cui, C. et al. | 2013
- 057
-
Analysis of Effect of Damping on Seismic Loads of Primary EquipmentYe, X.-h. / Qi, H.-h. / Zhang, Y.-x. et al. | 2013
- 057
-
Research on Reactor Internals Sealing Structure of Supercritical Water Cooled ReactorLiu, X. / Fang, C.-s. / Wang, L.-b. et al. | 2013
- 058
-
Critical Heat Flux Prediction Model for Low Quality Flow BoilingPan, J. / Yang, D. / Xiao, R.-g. et al. | 2013
- 058
-
Experimental Investigation of Subcooled Flow Boiling Incipience in Volumetrically Heated Packed BedZhang, X.-n. / Sun, Z.-n. / Meng, X.-k. et al. | 2013
- 060
-
Theoretical Calculation and Analysis of Emergency Ventilation to Reduce Nuclear Accident ConsequenceLin, X.-l. / Yang, Y.-x. et al. | 2013
- 060
-
Study on Materials Selection for SCWR Reactor Vessel InternalsZhou, Y. / Zhang, H.-l. / Li, M.-c. et al. | 2013
- 061
-
Thermodynamic Analysis of Chemical Vapor Depositing Nb Coating on Fuel ParticlesPan, X.-q. / Yang, J. / Zhang, L. et al. | 2013
- 061
-
Hydraulic Performance Analysis of Nuclear Axial Pump Based on CFD MethodJiang, H. / Huang, W. et al. | 2013
- 062
-
Application of Wavelet Analysis inSignal Singularity DetectionChen, Z.-h. / Xia, H. / Wu, Z.-s. et al. | 2013
- 063
-
Numerical Simulation of Fluid Flow and Heat Transfer in Pebble Bed ReactorXu, G.-z. / Sun, Z.-n. / Meng, X.-k. et al. | 2013
- 064
-
Heat Transfer Characteristics of Supercritical Pressure Water in Vertical Upward Annular ChannelsWang, H. / Bi, Q.-c. / Yang, Z.-d. et al. | 2013
- 065
-
Simulation Study on Flow Uniformity in Casting Nozzle during Preparation of UO~2 KernelLiu, M.-l. / Hao, S.-c. / Liu, B. et al. | 2013
- 065
-
Analysis on Heat Transfer of Outlet Nozzle and Steam Cavity for SCWR RPV Using CFDLi, Y.-G. / Wang, X.-b. / Luo, Y. et al. | 2013
- 066
-
Research on Effect of Two-Phase Interfacial Friction Characteristics on Quench Front Velocity in Narrow ChannelZeng, W. / Zhu, L. / Liu, S.-t. et al. | 2013
- 067
-
Research on Void Fraction Models for Vertically upward Two-Phase Cross-Flow in Horizontal Tube BundleJiang, N.-b. / Zang, F.-g. / Zhang, Y.-x. et al. | 2013
- 068
-
Effects of Loading Reactivity at Dynamic State on Wave of Neutrons in Burst ReactorGao, H. / Liu, X.-b. / Fan, X.-q. et al. | 2013
- 068
-
Study on Transition Criterion from Bubble Flow to Slug Flow in Rectangular ChannelsWang, Y. / Yan, C.-q. / Sun, L.-c. et al. | 2013
- 070
-
Study on Model of Onset of Nucleate Boiling under Natural Circulation in Narrow Rectangular Channel by Using Unascertained MathematicsDuan, J. / Zhou, T. / Li, J.-j. et al. | 2013
- 071
-
Transient Flow Characteristics of Nuclear Reactor Coolant Pump in Recessive Cavitation Transition ProcessWang, X.-l. / Yuan, S.-q. / Zhu, R.-s. et al. | 2013
- 071
-
Design Scheme of Special Safety System for Supercritical-Water-Cooled ReactorSui, H.-m. / Shan, J.-q. / Huang, X.-k. et al. | 2013
- 071
-
Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGRLu, Z.-m. / Zhang, J. / Zhou, X.-w. et al. | 2013
- 072
-
Optimization of Data Processing for ORIGEN-S CalculationsXin, F. / Liu, Y.-y. / Zheng, P. et al. | 2013
- 073
-
Visualized Experimental Study on Sliding and Lift-Off of Bubbles in Narrow Rectangular ChannelXu, J.-j. / Zhuo, W.-b. / Xie, T.-z. et al. | 2013
- 075
-
Analysis of Rolling Induced Additional Effect on Two-phase FlowTian, D.-g. / Sun, L.-c. / Yan, C.-q. et al. | 2013
- 075
-
Research on SCWR Turbine and Thermal SystemHuang, X.-K. / Ma, A.-p. / Sun, q. et al. | 2013
- 075
-
Study on ^6LiD Convertor as 14MeV Neutron Source in HFETRSun, S.-h. / Peng, F. / Xu, T.-z. et al. | 2013
- 076
-
Study on High-Cycle Fatigue Behavior of 6XN Stainless Steel and Alloy 825Xiong, R. / Qiao, Y.-j. / Zhao, Y.-x. et al. | 2013
- 077
-
Study on Flow Characteristics of Integral Reactor Test Facility under Rolling Motion without HeatingGong, H.-j. / Yang, X.-t. / Huang, Y.-p. et al. | 2013
- 078
-
Large-Break Accident Analysis of Supercritical Water-Cooled Reactor CSR1000Dang, G.-j. / Hua, D.-s. / Lu, J.-c. et al. | 2013
- 079
-
Numerical Simulations on Flow Field Structure and Free Surface Behavior of ADS Windowless TargetHu, C. / Su, G.-Y. / Gu, H.-Y. et al. | 2013
- 079
-
Analysis of Effects on Radioactive Fission Product Release from Fuel Pellet to CoolantJing, F.-t. / Chen, B.-d. / Yang, H.-r. et al. | 2013
- 079
-
Visualized Study on Interface Shape and Growth of Sliding Bubble in Narrow Rectangular ChannelXu, J.-j. / Zhuo, W.-b. / Xie, T.-z. et al. | 2013
- 080
-
Study on Feasibility of Replacing 321 with 316LN Stainless Steel for Main Reactor Coolant Pipe MaterialLuo, Y.-j. et al. | 2013
- 082
-
Study on Homogeneous Flow Model for Air-Water Two-Phase Flow in Mini-Rectangular ChannelXing, D.-c. / Yan, C.-q. / Sun, L.-c. et al. | 2013
- 083
-
High Temperature Performance of Cobalt-Free Nickel-Based Cladder on Nuclear Valve Sealing SurfaceYu, J.-l. / Fu, G.-y. / Liu, S. et al. | 2013
- 083
-
Analysis of Complete Loss of Forced Flow Accident in China Super-Critical Water ReactorZhang, D. / Lu, J.-c. / Liu, S.-t. et al. | 2013
- 083
-
An Assessment Methodology of Thee-Layers Melt Configuration during IVR for AP1000Xiang, Q.-a. / Guan, Z.-h. / Deng, C.-r. et al. | 2013
- 084
-
Numerical Simulation on Fluid Flow and Heat Transfer Characteristics of Narrow Rectangular Channel in Rolling MotionLi, L.-j. / Dong, X.-l. / Ma, J. et al. | 2013
- 084
-
Study on Performance of Novel Overlaying Welding Materials on the Sealing Face of RPVDang, Y. / Wen, Y.-z. / Qiu, S.-y. et al. | 2013
- 086
-
Study on Creep Damage Behaviors of Ni-Based Alloy C276Mao, X.-p. / Guo, Q. / Zhang, S.-y. et al. | 2013
- 087
-
Development of Coupled Neutronics/Thermal-Hydraulics CASIR Code System for SCWR Core Steady StateMa, Y.-q. / Chai, X.-m. / Wang, Y.-w. et al. | 2013
- 087
-
Study on Density Wave Oscillation in Parallel Channels by Section FormHuang, J. / Huang, Y.-p. / Wang, Y.-l. et al. | 2013
- 088
-
Characteristics and Application Study of AP1000 NPPs Equipment Reliability Classification MethodGuan, G. et al. | 2013
- 089
-
Limitations and Shortcomings of Duplex Stainless Steel Choice in RCC-MShen, Y.-s. / Xiao, J. et al. | 2013
- 090
-
Dimensionless Analysis of Single-Phase Natural Circulation Characteristics for PWR under Ocean ConditionHao, Y.-l. / Yan, B.-h. / Yang, X.-t. et al. | 2013
- 090
-
Numerical Investigation of Residual Heat Removal Heat Exchange Capacity in Pressurized Water Reactor PlantsQiu, J. / Li, J. / Wang, X.-j. et al. | 2013
- 091
-
Numerical Simulation of Steam Condensation Inside Vertical Tube in Presence of Noncondensable GasesHuang, Z. et al. | 2013
- 092
-
Development of Safety Analysis Code for SCWRWu, P. / Dang, G.-j. / Gou, J.-l. et al. | 2013
- 092
-
Degradation of Zirconium Alloy Pressure Tube in Qinshan CANDU-6 Heavy Water Reactor and Its MitigationZhao, W.-d. / Shi, X.-q. et al. | 2013
- 092
-
Research on Transfer Rule of the Monitoring of Operator in Digital Main Control Room of Nuclear Power PlantZhang, L. / Li, L.-f. / Lu, C.-s. et al. | 2013
- 094
-
Scaling Study for Experimental Test of Advanced Reactor Analysis of Passive Feature of Containment and Its Simulation HierarchyLi, S.-q. / Li, W.-h. / Jiang, S.-y. et al. | 2013
- 095
-
Experimental Investigation on Local Parameter Measurement Using Optical Probes in Two-phase Flow under Rolling ConditionTian, D.-g. / Sun, L.-c. / Yan, C.-q. et al. | 2013
- 096
-
Numerical Simulation of Multiphase Flow and Boiling using Lattice Boltzmann MethodLi, L.-j. / Hu, A.-j. / Zeng, J.-b. et al. | 2013
- 096
-
Reliability Residual-Life Prediction Method for Thermal Aging Based on Performance DegradationRen, S.-h. / Xue, F. / Yu, W.-w. et al. | 2013
- 097
-
Preliminary Study on SCWR Fuel Rod Performance Analysis CodeXing, S. / Yao, D. / Yin, C.-y. et al. | 2013
- 097
-
Preliminary Analysis of Power Control Characteristics for ADS Equipment in ChinaSun, C.-y. / Zhao, F.-y. et al. | 2013
- 099
-
Dynamic Detection System for Deuterium Pellet Row LengthGuo, Y.-c. / Zhou, S. / Gao, C. et al. | 2013
- 100
-
Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWRLuo, F. / Zhou, T. / Cheng, W.-x. et al. | 2013
- 100
-
Efficiency Contrast Test for Initial and One Refueling Cycle Used Catalytic Plates of Passive Autocatalytic RecombinerGuo, X.-l. / Yu, T. / Xu, R.-y. et al. | 2013
- 101
-
Experimental Study on Heat Transfer of Supercritical Water in Simple ChannelsLi, Y.-l. / Zeng, X.-k. / Huang, Z.-g. et al. | 2013
- 101
-
Parameter Analysis for Pebble Dynamics of Two-Dimensional Two-Region Pebble-Bed Reactor using Phenomenological MethodWang, W.-j. / Yang, X.-t. / Jiang, S.-y. et al. | 2013
- 102
-
Simulation Experimental Research on Passive Residual Heat Removal Performance for Nuclear Seawater Desalination ReactorNie, C.-h. / Xu, S.-j. / Liu, X. et al. | 2013
- 104
-
PWR Core Power Control and Simulation Based on Multi-Model StrategyWu, Y.-z. / Chen, S.-h. / Li, G. et al. | 2013
- 104
-
Design of Automatic Welding Device for Nuclear Vessel HeadKong, J.-s. / Meng, K. et al. | 2013
- 105
-
Experiment of Pebble Flow in Two-Region Pebble-Bed Reactor Core VesselTang, Z.-w. / Yang, X.-t. / Sun, Y.-l. et al. | 2013
- 106
-
Transient Safety Analysis of Subcritical Energy ReactorMa, J.-m. / Liu, Y.-k. / Li, M.-s. et al. | 2013
- 107
-
Conceptual Design of Passive Residual Heat Removal System for 10 MW Molten Salt ReactorSun, L. / Sun, L.-c. / Yan, C.-q. et al. | 2013
- 107
-
Operation Research on Steam Generator Tube Rupture Accident in PWR NPPsGuo, C. et al. | 2013
- 108
-
Method of Defining Pseudocritical Region Based on Secondary Phase Transition TheoryYan, X. / Zang, J.-g. / Zeng, X.-k. et al. | 2013
- 108
-
Analysis and Research of PWR Instrument Commissioning Based on SimulinkLuan, Z.-h. / Liu, D.-g. / Qiu, S.-s. et al. | 2013
- 109
-
Study on Nuclear Reactor Power Control Based on T-S Neuro-Fuzzy NetworkLiao, L.-t. / Chen, Z. et al. | 2013
- 111
-
Analysis of Loss of Offsite Power and Loss-of-flow Accident of HFETRSun, S.-h. / Xu, T.-z. / Li, Z.-y. et al. | 2013
- 111
-
Analysis of Origin for Thermal Power Fluctuation in Lose of Coolant Accident Monitoring SystemHu, R.-p. / Li, Z.-j. / Zhou, X.-l. et al. | 2013
- 111
-
Effect of Guide Vane Outlet Position on Nuclear Reactor Coolant Pump under Gas-liquid Two-phase ConditionFu, Q. / Wang, X.-l. / Yuan, S.-q. et al. | 2013
- 112
-
Process Management during Construction of Digital I&C System in Tianwan Nuclear Power PlantDuan, P. / Xu, J. / Shi, Q.-w. et al. | 2013
- 113
-
Application of Ethernet-Based Distributed Measurement and Control System in Thermal Hydraulic TestsKuang, S.-q. / Wang, H.-y. / Zhong, Y.-m. et al. | 2013
- 114
-
Application of RCM in Ensuring Reliability of ARMS in Tianwan Nuclear Power StationBai, X.-b. et al. | 2013
- 114
-
Application of CFD Methods in Research of SCWR Thermo-HydraulicsZeng, X.-k. / Li, Y.-l. / Yan, X. et al. | 2013
- 114
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Effect of Steam Distribution Modes on Performance of Last Stage in Steam TurbineGao, Y.-q. / Li, Y.-x. / Zhou, Z.-d. et al. | 2013
- 115
-
Cavitation Characteristics for Impeller of Centrifugal Charging Pump of M310 Nuclear Power PlantsFu, Q. / Yuan, S.-q. / Zhu, R.-s. et al. | 2013
- 115
-
Application of AFAL Methodology in Substantiation of Instrument Calibration Intervals Extension in Nuclear Power PlantZhou, P. / Qiu, C.-H. / Chu, Q.-B. et al. | 2013
- 116
-
Reconstruction of Water Level of Steam Generator Based on Elman Neural NetworkDuan, M.-q. / Zheng, Y.-f. / Chen, Y.-q. et al. | 2013
- 117
-
Nuclear Safety Review for Qualification of Class 1E Motor inside Containment for Nuclear Power StationsLi, S.-x. / Wu, Q. / Zhang, Y.-b. et al. | 2013
- 118
-
Research on Heat and Mass Transfer Model for Passive Containment Cooling SystemJiang, X.-w. / Yu, H.-x. / Sun, Y.-f. et al. | 2013
- 118
-
Wall Thinning Analysis of Carbon Steel Pipes in Nuclear Power PlantsMa, N. / Yin, C.-g. / Qin, J.-g. et al. | 2013
- 120
-
Best Estimate Plus Uncertainty Method and Its ApplicationRan, X. / Wu, D. / Chen, B.-d. et al. | 2013
- 121
-
Online pH Monitoring and Control of Radioactive Waste Liquid in Evaporation Treatment SystemYu, R. / Kong, J.-s. / Guo, W.-q. et al. | 2013
- 121
-
Precise Prefabrication of Primary Pipes Automatic Welding in CPR1000 Nuclear Island InstallationZhang, K. / Li, J.-b. / Wang, D. et al. | 2013
- 121
-
Numerical Analysis of Effect Factors on Heat Transfer and Flow Characteristics of Supercritical WaterLiu, L. / Xiao, Z.-j. / Yan, X. et al. | 2013
- 123
-
A Scheme for Establishing of Criterions for Reactor Safe Operation in Condition of Fuel Clad FailureLin, X.-l. et al. | 2013
- 124
-
Natural Circulation Characteristics in a Symmetrical Two-Circuit Loop under Inclined ConditionYang, X.-t. / Zhu, H.-y. / Gong, H.-j. et al. | 2013
- 124
-
Experimental Study on Emergency Ventilation to Reduce Nuclear Accident ConsequenceLin, X.-l. / Niu, W.-l. / Chen, Y.-f. et al. | 2013
- 125
-
Position Design for Instrumentation Penetration of Reactor Vessel Based on None-Alignment AnalysisXia, X. / Du, H. / Li, N. et al. | 2013
- 126
-
Numerical Simulation of Heat Transfer Characteristics of Supercritical Water in Annular Channel with Helical RibsLiu, L. / Xiao, Z.-j. / Xiao, Y. et al. | 2013
- 126
-
Development of Non-destruction Test Device by gamma -Ray ScanningZhang, J.-b. et al. | 2013
- 126
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Design and Analysis of Throttle Orifice Applying to Small Space with Large Pressure DropLi, Y. / Lu, D.-g. / Zeng, X.-k. et al. | 2013
- 126
-
Analysis and Management of Accelerated Aging of Relay in NPPsZhang, S. / Ma, Y.-j. / Jiang, H. et al. | 2013
- 128
-
Experimental Study on Over Reading Coefficient in Wet Steam Flow MeasurementPeng, X.-j. / He, C.-y. / Yuan, D.-w. et al. | 2013
- 128
-
Design Improvement and Open Item Analysis of Containment Sump Strainer in QINSHAN Phase II Extension ProjectZhang, W. / Gong, Z. / Zhu, J.-m. et al. | 2013
- 129
-
Heavy Water Reactor Pressure Tube Elongation Measurement and Data AnalysisShang, J.-m. / Zou, L.-l. / Yuan, J.-z. et al. | 2013
- 129
-
Application and Modification of On-Line Monitoring System for Containment Leakage in Qinshan Second Nuclear Power PlantWang, H.-w. / Shi, C.-j. / Yang, G. et al. | 2013
- 130
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Dynamic Load Protection Technology for Nuclear Upender and Its ApplicationZhao, A.-p. / Zhang, Q. / Zhang, M.-l. et al. | 2013
- 132
-
Numerical Study on Over Reading Coefficient in Wet Steam Flow MeasurementBai, X.-s. / Yuan, D.-w. / Yan, X. et al. | 2013
- 132
-
Design and Application of Concrete Floor Modular Hoisting in Nuclear Power PlantsYu, X.-n. / Yang, Y.-y. / Jian-guo, W. et al. | 2013
- 133
-
Numerical Simulation of Heat Transfer Characteristics of Supercritical Water in 2x2 BundlesZang, J.-g. / Yan, X. / Huang, S.-f. et al. | 2013
- 133
-
Study on Solutions to Sensor Support Setting Resonance of Nuclear Power Half-Speed Turbo-GeneratorGao, P. et al. | 2013
- 133
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Seismic Response Analysis of Circulation Pump in AP1000 Nuclear Power PlantOu, M.-x. / Zhao, L. / Shi, W.-d. et al. | 2013
- 133
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Study on the Application of Ethanolamine in PWR Secondary Water TreatmentWang, L. / Xie, Y. / Cui, H.-m. et al. | 2013
- 135
-
Discussion on Operation Occasion of Pre-Service Inspection and Main Primary System Hydrostatic Test of PWRSun, H.-t. / Zhang, Y. / Wang, C. et al. | 2013
- 136
-
Design and Verification of Detective Device of Boron MeterWang, H.-b. / Deng, S. / Wang, C.-h. et al. | 2013
- 136
-
Analysis of High On-Line Vibration Measurement of Nuclear Power Half-Speed Turbo-GeneratorGao, P. / Wang, W. / Chen, Y. et al. | 2013
- 137
-
Study on Creep Property of Candidate Stainless Steels for SCWRLiang, B. / Chen, L. / Tang, R. et al. | 2013
- 137
-
Study of Venturi Geometry Parameter Design for the Better Wet Steam MeasurementWang, H.-p. / Yuan, D.-w. / He, C.-y. et al. | 2013
- 137
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A General Model Based on Graph Theory for Quantitative Analysis of PWR Thermodynamic SystemRan, P. / Wang, Y.-s. et al. | 2013
- 138
-
Effect of Thermal Aging on Failure Probability of a Nuclear Primary PipeLi, S.-X. / Li, S.-L. / Wang, X.-T. et al. | 2013
- 139
-
Research on pH Automatic Adjustment System in Radioactive Decontamination Waste Liquid Evaporation Treatment SystemYu, R. / Kong, J.-s. / Xiang, X.-m. et al. | 2013
- 140
-
Thermal Research of CITP-II Tritium Production Irradiation DeviceZhang, Z.-h. / Mi, X.-m. / Duan, S.-l. et al. | 2013
- 140
-
Study on Chain Relationship between Condenser and Vacuum Isolation ValveShang, X.-y. / Shi, J.-z. / Wang, X.-h. et al. | 2013
- 140
-
Experimental Study on Creep/Fatigue Interaction CorrelationTan, X.-h. / Ma, J.-z. / Liu, Y.-j. et al. | 2013
- 141
-
Effects of Seismic Wave Inputting Interface on Designed Surface Ground Motion in AP1000 Nuclear Island StructureHou, C.-l. / Li, X.-j. et al. | 2013
- 142
-
Design of Maintenance Pattern for Valves in Radioactive Waste Processing FacilitiesKong, J.-s. / Yu, R. / Meng, K. et al. | 2013
- 143
-
Analysis on NDE Problem of Weld Joint between AP1000 Steam Generator and Reactor Coolant Pump CasingMao, C.-s. / Chen, F.-b. et al. | 2013
- 143
-
Study on Ultrasonic Inspection Technology for Reactor Pressure Vessel StudZhang, G.-f. / Zhang, B.-j. / Yan, Z. et al. | 2013
- 144
-
Dropping Accident Analysis of Liquid Storage Container using Finite Element MethodNie, J.-f. / Zhang, H.-q. / Li, H.-k. et al. | 2013
- 145
-
Research on Monitoring and Management Information Integration Technique in Waste Treatment and ManagementKong, J.-s. / Yu, R. / Mao, W. et al. | 2013
- 146
-
Study on Low-Cycle Fatigue Property of Candidate Stainless Steels for SCWRChen, L. / Tang, R. / Liang, B. et al. | 2013
- 147
-
Cause Analysis and Countermeasures for Valve Failure of Radioactive Liquid Waste Treatment FacilitiesJin-song, K. / Yu, R. / Meng, K. et al. | 2013
- 147
-
Auto Type-Selection of Constant Supportingin Nuclear Power StationsLiu, H. / Wang, F.-j. / Liu, W. et al. | 2013
- 148
-
Screening and Management of Dead-End Pipe in Qinshan NPPCao, X.-m. / Li, S.-w. / Xue, F. et al. | 2013
- 148
-
Stress and Fatigue Analysis for Lower Joint of Control Rod Drive Mechanisms Seal HouseShao, X.-j. / Zhang, L.-p. / Du, J. et al. | 2013
- 149
-
Analysis of Radwaste Treatment Localization Scheme at Nuclear Power PlantsLiu, P. / Liu, Y. / Yao, B. et al. | 2013
- 149
-
Conception Design of Shielding Collimator System for High Energy Neutron Radiography with Minitype Neutron SourceWu, Y. / Dou, H.-f. / Tang, B. et al. | 2013
- 150
-
Study on High-Cycle Fatigue Behavior of Candidate Stainless Steels for SCWRXiong, R. / Zhao, Y.-x. / Qiao, Y.-j. et al. | 2013
- 152
-
Transient Analysis for CPR1000 Reactor Main Pump and ElectromotorXiao, S.-p. et al. | 2013
- 153
-
Ansys CFX Thermal Analysis of Modular Tube-Type Irradiation RigYang, W.-h. / Tong, M.-y. / Sun, S. et al. | 2013
- 153
-
Analysis and Improvement on Broken Coupling BoltsYou, L. / Deng, X.-y. / Chen, R. et al. | 2013
- 153
-
Feasibility Study on Development of Small Nuclear Power Reactors in ChinaChen, W.-j. / Jiang, S.-y. et al. | 2013
- 154
-
Analysis of Falling Characteristics of Small Absorber Ball in HTR Shutdown DeviceChen, F. / He, X.-d. / Li, T.-j. et al. | 2013
- 156
-
Study on Chemical Cleaning Formula for Steam Generator Secondary Side during Tianwan NPP Cooling DownXia, X.-j. / Wen, J.-h. / Ma, W.-g. et al. | 2013
- 156
-
Research on Abnormal Operation Status Detection Method for Nuclear Power Plants Based on Operation Data AnalysisYu, R. / Kong, J.-s. / Luo, D.-s. et al. | 2013
- 157
-
Design of Test Device for RPN Neutron Source ComponentWang, H.-b. / Zhuo, W.-b. / Wan, H.-s. et al. | 2013
- 157
-
Research on Rejection Performance of Reverse Osmosis to Nickel in Simulated Radioactive WastewaterKong, J.-s. / Wang, X.-w. et al. | 2013
- 157
-
Research and Development of A New Speediness Disassembly Tie-In for Advanced Fuel AssemblyHuang, X.-d. / Huang, H. / Hong, L. et al. | 2013
- 157
-
Study on Corrosion Behaviors of Stainless Steels and Refractory Alloys in Pseudo-Critical ZoneZhang, Q. / Qiu, S.-y. / Tang, R. et al. | 2013
- 159
-
Root Cause Analysis of Ventilation System Motor Shaft Fracture in Nuclear Power PlantsYang, L.-f. / Che, Y.-h. / Lu, Q.-x. et al. | 2013
- 160
-
Removal of U(VI) from Aqueous Solution by Nanoscale Zero-Valent IronLi, X.-y. / Liu, Y.-b. / Hua, M. et al. | 2013
- 160
-
Research of Electrochemistry Behavior of Corrosion Inhibitor for KAA of Tianwan NPPLiu, J.-h. / Gong, B. / Jiang, E. et al. | 2013
- 161
-
Development of Long Shank Repair Tool for Defect of Pressure Vessel Bolt Hole in Pressure Vessel of Nuclear Power PlantHuang, X.-d. / Huang, H. / Hong, L. et al. | 2013
- 161
-
Study on Treating of Low-Level Radioactive Reactor Wastewater by Combined Membrane Process (UF-RO)Lu, Y.-y. / Cao, Q.-r. / Chen, Y.-m. et al. | 2013
- 162
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Design and Application of Numeric Hardware Platform of Reactor Numeric Instrument and Control SystemWu, Z.-q. / Gao, H. / Zeng, S.-l. et al. | 2013
- 164
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Study on Fretting Characteristics of Si~3N~4/NS315 Alloy at High TemperatureLi, G. / Liu, H.-w. / Ren, P.-d. et al. | 2013
- 164
-
Analysis of Interfaces in AP1000 EOP ProceduresYe, C. / Zheng, M.-g. / Wang, Y. et al. | 2013
- 164
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Experimental Research of Cutting Stainless Steel by High Pressure Abrasive Water Jet under WaterLu, X.-j. / Si, D.-d. / Tong, M.-y. et al. | 2013
- 165
-
Preparation of SBR Rubber Based Flexible Shield MaterialFu, M. / Wang, Y. / Li, F. et al. | 2013
- 168
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Study Scheme of Reactor Decommissioning Simulation TechnologyDai, B. / Zhang, Y.-l. / Zhou, B. et al. | 2013
- 168
-
Building of a CAD System for I&C System of Nuclear Power PlantMa, Z.-c. / Zhang, D.-s. et al. | 2013
- 169
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Venturi Purification Device and Its Application in Purification of Gaseous Waste of Nuclear FacilitiesKong, J.-s. / Yu, R. / Yang, H.-l. et al. | 2013
- 172
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Feasible Research on VLLW Disposal in Control Area of Nuclear InstallationKong, J.-s. / Guo, W.-q. et al. | 2013
- 175
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Design of Detection Platform for Radioactive Waste PackageKong, J.-s. / Meng, K. et al. | 2013
- 176
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Simulation Research on Path Planning of Nuclear Emergency Decision with ConstraintsWei, Q. / Zhu, B. / Xie, C.-j. et al. | 2013
- 180
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Research and Practice of Informatization Construction in Waste Treatment and ManagementKong, J.-s. / Yu, R. / Guo, W.-q. et al. | 2013
- 185
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PRA Quality in Risk-Informed Application of Nuclear Power PlantLi, C. / Yi, Y. et al. | 2013