Nuclear Power Engineering 2016 Issue 2 Study of the Transform Method of Multi-Group Nuclear Cross Section Covariance Matrix

Study of the Transform Method of Multi-Group Nuclear Cross Section Covariance Matrix
Wang Dongyong;Hao Chen;Zhao Qiang;Wu Zongpei;Wu Hongchun;Li Fu;Fundamental Science on Nuclear Safety and Simulation Technology Laboratory;Harbin Engineering University;School of Nuclear Science and Technology;Xi’an Jiaotong University;Institute of Nuclear and New Energy Technology;Tsinghua University;

..............page:1-6

Research on Fuel Rod Multi-Physics Numerical Modeling and Program Development
Fei Jingran;Si Shengyi;Chen Qichang;Shanghai Nuclear Engineering Research and Design Institute;

..............page:7-12

Physical Characteristics Study of Power Ramp Test Irradiation Rig with ~3He Loop
Zhang Liang;Qiu Liqing;Deng Caiyu;Tong Mingyan;Nuclear Power Institute of China;

..............page:13-18

Study on Management Strategy for In-Core Irradiated Fuel Assembly Developed by Self-Reliance
Liao Hongkuan;Li Ligang;Liao Zejun;Yu Yingrui;Deng Zhixin;Jiao Yongjun;Wu Lei;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:19-22

Experimental Study on Hydraulic Characteristics of Tube Support Plate in Steam Generator
Wen Bo;Li Yong;Xiong Ting;Zan Yuanfeng;Yan Xiao;Zhuo Wenbin;Li Pengzhou;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institute of China;

..............page:23-26

Experimental Study on Convective Heat Transfer of Supercritical R134a in Vertical Circular Tubes
Chen Jiayue;Xiong Zhenqin;Xiao Yao;Gu Hanyang;School of Nuclear Science and Engineering;Shanghai Jiao Tong University;

..............page:27-31

Study on Mechanism of Radiation Heat Exchange for High Temperature Pebble Beds
Wu Hao;Gui Nan;Yang Xingtuan;Tu Jiyuan;Jiang Shengyao;Key Laboratory of Advanced Reactor Engineering and Safety of Tsinghua University;Ministry of Education;

..............page:32-37

Scaling Analysis of the Transient from Forced Circulation to Natural Circulation
Shi Yan;Yang Fuming;Li Yuquan;State Nuclear Power Technology Research & Development Centre;

..............page:38-42

Analysis of Downcomer Channel Thermal-Hydraulic Phenomena of PCCS Outside Cooling
Li Le;Li Cheng;Zhang Yajun;Yi Xiongying;INET of Tsinghua University;State Nuclear Power Technology Research & Development Center;Unit 92609;

..............page:43-47

Experimental Study on Effect of Buoyancy and Flow Acceleration on Heat Transfer of Supercritical CO₂
Liu Guangxu;Huang Yanping;Wang Junfeng;Zan Yuanfeng;Lang Xuemei;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;NPIC;

..............page:48-51

Criticality Excursion Analysis
Yang Junyun;Xiao Gang;Ying Yangjun;Institute of Applied Physics and Computational Mathematics;

..............page:52-55

Numerical Investigation of Heat Transfer Characteristics of Supercritical Carbon Dioxide in Double D-Shape Channel
Liu Shenghui;Huang Yanping;Liu Guangxu;Wang Junfeng;Zhao Dawei;Zang Jinguang;Zan Yuanfeng;Lang Xuemei;Xu Jianjun;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institute of China;

..............page:56-59

Experimental Study on Distribution Regions of Flow instability and Boiling Crisis in Parallel Twin Rectangular Channels under High Pressure
Tang Yu;Chen Bingde;Xiong Wanyu;Huang Yanping;Xu Jianjun;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institute of China;

..............page:60-64

Investigation of TVD Scheme Applied Into One Dimensional Flow Problems
Liu Wei;Yan Xiao;Department of Nuclear Power;China National Nuclear Corporation;Nuclear Power Institute of China;

..............page:65-69

A Simulation of Hysteresis Phenomenon during Cladding Transient Oxidation
He Xiaoqiang;Yu Hongxing;Jiang Guangming;Dang Gaojian;Wu Dan;Zhang Yu;Science and Technology on Reactor System Design Technology;Nuclear Power Institute of China;

..............page:70-73

Detecting Technique for Uranium Distribution Uniformity of Dispersion Uranium-Zirconium Fuel Core Based on Dual Energy Gama-Ray Transmission
Luo Jiandong;Du Yu;Tang Yueming;Xu Guiping;Wang Xuequan;Zhang Xiaochuan;Nuclear Power Institute of China;

..............page:74-76

Effects of Statistical Variations of Geometric Parameters of Coated Fuel Particles on the Failure Fraction
Li Rong;Liu Bing;Tang Chunhe;Institute of Nuclear and New Energy Technology;Tsinghua University;

..............page:77-81

Thermal Property Analysis of Accident Tolerance Fuel Pellet
Xu Duoting;Liu Tong;Ren Qisen;Huang Heng;Wu Hailong;China Nuclear Power Technology Research Institute;

..............page:82-86

Quantitative Characterization of Micro-defect in Zircaloy Oxide Films
Long Chongsheng;Wei Tianguo;Chen Hongsheng;Xiao Hongxing;Zhao Yi;Science and Technology on Reactor Fuel and Materials Laboratory;Nuclear Power Institute of China;

..............page:87-90

Protective Control and Simulation Research on Nuclear Power Plant Coolant Average Temperature
Qian Hong;Fang Zhenlu;Jin Weixiao;Zhou Lei;Zheng Pengyuan;Automation Engineering;Shanghai University of Electric Power;Shanghai Electrical Automation R&D Institute Ltd.Inc.;

..............page:91-96

Study on Level 2 PSA Source Terms Analysis of 1000 MW PWR
Chen Qiaoyan;Yang Zhiyi;Zhou Tao;Li Hanchen;China Nuclear Power Engineering Company;Nuclear and radiation safety center;North China Electric Power University;

..............page:97-101

Study on Emergency Planning Zone for Small Modular Reactors
Chen Wenjun;Jiang Shengyao;Liang Manchun;Institute of Nuclear and New Energy Technology;Tsinghua University;Department of Engineering Physics;Tsinghua University;

..............page:102-105

Design of CRDM Digital Current Adjustment Equipment Based on Transfer Phase Trigger and Close Loop Control
Li Guoyong;Zheng Gao;Xu Mingzhou;Jin Yuan;Science and Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:106-110

Research on Time-Varying Characteristics for Nuclear Power Valve Failure Probability
Guo Haikuan;Cai Qi;Zhao Xinwen;Zhang Yongfa;Department of Nuclear Energy Science and Engineering;Naval University of Engineering;

..............page:111-115

Independent Development of a New-Style Spent Fuel Storage Rack
Mo Huaisen;Yuan Chengyu;Tan Jingyao;China Nuclear Power Design Company;Ltd.;

..............page:116-121

Study on Characteristics and Sensitive Factors of PCS Air Flow Path Resistance
Pan Xinxin;Xiang Wenjuan;Song Chunjing;Shanghai Nuclear Engineering Research and Design Institute;

..............page:122-126

Stress Calculated by Two Models of Large Storage Tank
Huang Wen;Tan Tiancai;Ma Janzhong;Qualification Laboratory of Safety Classified Equipment;Nuclear Power Institute of China;

..............page:127-128

Airtightness Test Technology for Reactor Compartment
Lin Xiaoling;Tian Yanjie;Nuclear Safety and Chemical Defense Institute;

..............page:129-131

Development and Application of Routing Verification Program in Nuclear Piping Layout
Liu Qin;Chen Xinghua;China Nuclear Power Design Company;Ltd.;

..............page:132-135

Analysis and Operation of Tuning Amount of Boron in PWR NNP’s Transient Test Condition
Liu Daoguang;Yu Hang;Luan Zhenhua;Liu Peng;Start-up Department China Nuclear Power Engineering Co.;Ltd.;

..............page:136-140

Research on Atmospheric Steam Dump System Control Commands Oscillations and Valve Failure of CPR1000 Nuclear Units
Peng Haicheng;Yang Zhong;Yang Jianhui;Ouyang Hui;Li Jin;Fujian Ningde Nuclear Power Co.;Ltd;

..............page:141-142

CFD Study on Cavitation Abrasion for Axletree of Main Pump of Tianwan NPP
Zeng Xiaokang;Zhou Huihui;Xiong Wanyu;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;Nuclear Power Institute of China;

..............page:143-146

Feasibility Study on Flow Test Procedure for AP1000 Accumulator Discharge Lines
Kong Xiangwei;Qiu Fengxiang;Na Hongwei;State Nuclear Power Engineering Company;

..............page:147-150

Typical Accident Analysis of Supercritical Water-Cooled Reactor
Liu Liang;Zhou Tao;Chen Jie;Fang Xiaolu;Chen Juan;Wei Xiaoyan;Xia Bangyang;North China Electric Power University Nuclear Thermal Safety and Standardization Research Institute;Beijing Passive Technology Key Laboratory;Science Technology on Reactor System Design Technology Laboratory;Nuclear Power Institute of China;

..............page:151-155

Mechanism Study on Passive Siphon Break of a Low-Pressure System
Zheng Yiyun;Huang Shanfang;Guo Xiaoyu;Wang Ningbo;Pang Tianfeng;Jiang Bin;Qin Xiaobin;Xia Shaopeng;Li Min;Department of Engineering Physics;Tsinghua University;Institute of Nuclear Engineering and Science;National Tsing Hua University;

..............page:156-159

Experimental Study on Flow Characteristics of Large Subcooled Water in In-Containment Refueling Water Storage Tank Based on Scaled Model of AP1000 ADS under Depressurization Condition
Wu Guanghao;Lu Daogang;Wang Zhongyi;Zhang Yuhao;Fu Xiaoliang;Yang Yanhua;North China Electric Power University;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy;State Nuclear Power Software Development Center;National Energy Key Laboratory of Nuclear Power Software;

..............page:160-164

CFD Analysis on Key Components of Mixing Vane Grids—— Vane Angle/Dimple Shape
Yang Baowen;Han Bin;Zhang Hui;Shan Jianqiang;Department of Nuclear Science and Technology;Xi’an Jiaotong University;

..............page:165-170

Experimental Study on Thermal Fragmentation of Melt
Peng Cheng;Tong Lili;Cao Xuewu;Yan Xiao;School of Mechanical Engineering;Shanghai Jiao Tong University;CNNC Key Laboratory on Nuclear Reactor Thermal-Hydraulics Technology;Nuclear Power Institute of China;

..............page:171-174

Demonstration of Simulation Analysis Program PCCSAP-3D for Passive Containment Cooling System(PCCS)
Wang Yan;Yang Yanning;Zhang Yaoli;Zhou Zhiwei;Institute of Nuclear and New Energy Technology;Tsinghua University;State Nuclear Power Technology R&D Center;

..............page:175-179

Numerical Simulation of Double-Sensor Conductivity Probe Measurement Mechanism for Two-Phase Flow
Liu Hang;Pan Liangming;Deng Jiajia;Yuan Dewen;Huang Yanping;Key Laboratory of Low-grade Energy Utilization Technologies and Systems;Chongqing University;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology;NPIC;

..............page:180-184