38 Result(s)
within
English
Physics
Nuclear Energy
**hu Zhu
Chapter
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Chapter and Conference Paper
On the Creep Collapse of the Cladding Considering the Irradiation Growth Effect
Creep collapse of the cladding is one of the most important performance to be verified at the fuel rod’s design stage to guarantee safe operation. The irradiation growth effect should be considered to improve ...
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Chapter and Conference Paper
Modeling of the Gadolinium Fuel Tests with the Jasmine Fuel Performance Code
JASMINE is an advanced fuel rod performance code under development by China General Nuclear Power Cooperation (CGNPC). Basing on JASMINE1.0, JASMINE2.0 incorporates some state-of-the-art models or model featur...
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Chapter and Conference Paper
Analysis and Assessment of BEO-Doped Fuel with Fuel Rod Performance Code Jasmine
UO2-BeO fuel, a quite potential accident tolerant fuel, is used to increase the temperature margin of UO2 fuel and improve the safety performance of reactor operation. With the advantage of higher thermal conduct...
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Chapter and Conference Paper
Study on Capiliary Characteristics of Stainless Steel Wire Mesh Wick of Alkali Metal Heat Pipe
The capillary characteristics of the wicks are of great significance to the normal operation of the heat pipe,and this study carried out the wick experiment of vertical reel stainless steel wire mesh in liquid...
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Chapter and Conference Paper
Study on Aggregation Forming of Cathode Liquid Cerium Metal in Molten Salt Electrorefining Process
The research on the electrorefining purification of metallic cerium is a useful way to lay the foundation for dry reprocessing technology of spent nuclear fuel in molten salt. This paper investigated the aggre...
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Chapter and Conference Paper
Wetting Behavior of LBE on 316L and T91 Surfaces with Different Roughness
In this paper, two typical candidate structural materials of 316L and T91 with different surface roughnesses were studied at temperatures from 200–500 ℃. The surface with different roughness was prepared by me...
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Chapter and Conference Paper
Disorder Induced by Gamma Irradiation in Borosilicate Glasses
Vitrification is the mainstream method for the immobilization of high-level radioactive waste (HLW). As the common matrix of vitrification, the borosilicate glass and its irradiation tolerance have been widely...
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Chapter and Conference Paper
Research on Public Communication of Small Reactor
Based on the conclusions of small reactor environmental impact assessment and social stability risk assessment of small reactors, this paper conducts a special study on the public communication of small reacto...
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Chapter and Conference Paper
Optimization on Design of Logic Degradation for Safety I&C System of Nuclear Power Plant
As a conservative strategy to deal with instrument and control signal failure, logic degradation design has been often used in the safety instrument and control (I&C) system of nuclear power plants. For exampl...
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Chapter and Conference Paper
Failure Analysis of Valve Seat Cracking of Pneumatic Control Valve in Nuclear Power Plant
Cracks were found on the alloy layer of the valve seat when a pneumatic control valve was disassembled during the overhaul of the nuclear power plant, and the erosion corrosion traces were found on the surface...
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Chapter and Conference Paper
Influence of Zirconia Addition on the Leaching Stability of Borosilicate Glass
Immobilization of high-level radioactive wastes (HLW) in borosilicate glass for deep geological disposal has been widely used in the treatment of HLW around the world. The chemical durability of borosilicate g...
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Chapter and Conference Paper
Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular Reactor
On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized water reactor nuclear power plants, the principle of setting f...
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Chapter and Conference Paper
Study on Composition Design of Enamel Coating and Its Resistance to Active Metal Vapor Corrosion
After evaporation of cerium metal (simulated radioactive substance) in a stainless steel plate in a production process, Ce and Fe elements are interdiffused at the bonding interface and Ce-Fe solid solution is...
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Chapter and Conference Paper
Research on Aging Behavior and Life Prediction of Fluorine Rubber Seals in Nuclear Power Plants Under Silicone Oil Condition
The comprehensive aging experiments of fluororubber sealing materials in the nuclear power plant were carried out in the condition of pressure load, silicone oil and temperature from 135 ℃ to 165 ℃. Then, comp...
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Chapter and Conference Paper
Study on the Crystallization Rate of Uranium Peroxide Based on Ultrasound and Microchannel Technology
With the application and development of process intensification technologies such as ultrasonic crystallization and microchannel technology in the field of crystallization, it is of great practical significanc...
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Chapter and Conference Paper
Optimization of Sintering Parameters of Lead Oxide Particles for Solid Oxygen Control in Lead Cooled Fast Reactor
Lead oxide ceramic is a kind of material used for the solid phase oxygen control in lead-cooled fast reactor (LFR) and accelerator driven sub-critical system (ADS). In this work, Lead oxide ceramics were prepa...
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Chapter and Conference Paper
Solid-Liquid Equilibria of Ternary Systems UO2(NO3)2 + HNO3 + H2O and UF4 + HF + H2O at 298 K
UO2(NO3)2 and UF4 are significant intermediates that connect different chemical unit operations (such as dissolution, evaporation, concentration, extraction and etc.) in uranium chemical industry. Commonly, there...
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Chapter and Conference Paper
Study on Welding Process Between the Hexagonal Tube and the Grid Frame Component of MOX Fuel Assembly in CEFR
A series of welding process tests were carried out for the pressure resistance spot welding (RSW) of the hexagonal tube and the grid frame component of MOX fuel assembly in CEFR. With the help of visual inspec...
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Chapter and Conference Paper
Experimental Study on Thermal-Hydraulic Characteristics of Air Heat Exchanger for Sodium Cooled Fast Reactor
The sodium-air heat exchanger is one of the important equipment of the decay heat removal system of sodium-cooled fast reactor. The liquid sodium in the heat transfer tube exchange heat with the air flowed in ...
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Chapter and Conference Paper
Study on Social Stability Risk Assessment of Nuclear Facilities
This paper studies the social stability risk assessment of nuclear facilities, formulates the assessment procedure, determines the assessment content and scope, and establishes the assessment risk index databa...
