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Research on Neutron Diffusion and Thermal Hydraulics Coupling Calculation based on FLUENT and its Application Analysis on Fast Reactors

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2020; 65 (1)

The neutron diffusion equation is defined based on the User Defined Function (UDF) and the User Defined Scalar (UDS) functions of the FLUENT. The neut......

CFD Simulation of Flow Characteristics and Thermal Performance in Circular Plate and Shell Oil Coolers

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2020; 65 (1)

Circular plate and shell heat exchangers were gradually applied as oil coolers. Hence, it was necessary to investigate their performance at low Reynol......

Analysis of Ultimate Response Guidelines for Chinshan Nuclear Power Plant in Taiwan to Cope with Postulated Compound Accident

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2020; 65 (1)

Taiwan Power Company (TPC) together with its engineering consultation, research company and institute have been working on the development of guidelin......

Research and Application of Nuclear Safety Culture Improvement Management for NPPs in China

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2020; 65 (2)

The traditional nuclear safety culture improvement work in is mainly about propagandize, training, and behavior observation to instill the concept. Th......

Experiment Research on the Insurge Transient Behavior of Gas-steam Pressurizer under Various Pressure

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2019; 64 (11-12)

For small and medium sized reactors with gas-steam pressurizer, the transient behavior of gas-steam pressurizer plays a vital role on the safety of th......

JIF:0.08

Experimental Study on Sub-cooled Boiling of Natural Circulation in Narrow Rectangular Channels

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2019; 64 (1)

Sub-cooled boiling of natural circulation has been experimentally investigated based on a natural circulation device with narrow rectangular channels.......

JIF:0.08

Design of Control System for On-line Ultrasonic Testing Device of Nuclear Power Hollow Flange Bolt Based on LabVIEW

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2019; 64 (2)

Hollow flange bolt on-line ultrasonic testing device control system and measurement and control software are researched and designed. It detects the f......

JIF:0.08

Supercritical Water Natural Circulation Flow Stability Experiment Research

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (12)

critical water natural circulation plays an important role in the safety of the Generation-IV supercritical water-cooled reactors. Hence it is crucial......

JIF:0.08

Non-Conformal Contact Mechanical Characteristic Analysis on Spherical Components

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (3)

Non-conformal spherical-contact mechanical problems is a three-dimensional coordination or similar to the coordination spherical contact. Due to the c......

JIF:0.08

Application of CATE 2.0 Code on Evaluating Activated Corrosion Products in a PWR Cooling Loop

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (3)

In PWR plants, most Occupational Radiation Exposure (ORE) for personnel results from Activated Corrosion Products (ACPs) in the cooling loop. In order......

JIF:0.08

Displacement of Cryomodule in CADS Injector II

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (6)

As Cryomodule can easily reduce higher power consumption and length of an accelerator and the accelerator can be operated more continuously. The Chine......

JIF:0.08

Reliability Analysis on Passive Residual Heat Removal of AP1000 Based on Grey Model

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (6)

It is common to base the design of passive systems on the natural laws of physics, such as gravity, heat conduction, inertia. For AP1000, a generation......

JIF:0.08

Uncertainty Analysis for Parameters of CFAST in the Main Control Room Fire Scenario

期刊: ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2017; 62 (7)

The fire accident is one of important initial events in the nuclear power plant. Moreover, the fire development process is extremely difficult and com......

JIF:0.08

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