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Xu H.,State Nuclear Power Technology R and nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2013

Scientific and reasonable operator management is the basis of nuclear safety. It is paid more attention after the three-mile island accident. The prediction of operators' basic behavior parameters is the premise and foundation of scientific and reasonable operator management. Grey theory happened to solve the dilemma encountered in prediction and decision-making of operator behavior in operator management of nuclear power plant. The procedure was divided into two steps:1) According to the historical record of operators' behavior parameters, a differential equation model using grey theory was set up to predict the future behavior of operators; 2) operator management decision-making was made based on grey theory. The calculation result is not only helpful for operator management but also useful for operators to find their shortcomings. Grey theory used in the study provides a new idea and method for future operator management in nuclear power plant. Source


Gang Z.,State Nuclear Power Technology R and nter | Ke G.-T.,China Institute of Atomic Energy
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2014

Traveling wave reactor (TWR) is an innovative conceptual fast reactor, which takes with once through breeding-burning mode and includes ignition and propagation regions. TWR's operation comprises stages of ignition start-up, wave forming, stable propagation of wave and lifetime extinguishing etc. TWR response to perturbation of reactor fuel component change in ignition and propagation stages was investigated in the paper. The results indicate that TWR has a good self-stabilizing performance under small perturbation. Source


Liu Z.,Harbin Institute of Technology | Yu D.,Harbin Institute of Technology | Duan Y.,State Nuclear Power Technology R and nter
Journal of Engineering for Gas Turbines and Power | Year: 2012

A nonlinear dynamic model is developed for a rotor-bearing system with radial steam force due to partial admission, taking into account the prediction of subsynchronous instability of a steam turbine. The optimum schemes are obtained by comparing the rotor responses subjected to maximal radial steam forces in different partial admission schemes. It is found through comparison that the instability of a rotor-bearing system is directly related to the direction of the radial steam force in the partial admission scheme. © 2012 American Society of Mechanical Engineers. Source


Yin Z.,CAS Institute of Mechanics | Chang L.,CAS Institute of Mechanics | Chang L.,State Nuclear Power Technology R and nter | Hu W.,CAS Institute of Mechanics | And 2 more authors.
Physics of Fluids | Year: 2012

In this paper, the study on isolated spherical drops in thermocapillary migrations in zero gravity is carried out with a novel numerical scheme to accomplish long-tank simulations in a very short computing domain, and the full migrating phenomena with fairly large Marangoni numbers (up to 400) are discussed in detail. Larger Marangoni numbers lead to more complicated migrating processes, and longer distances for the drops to reach their final stable migrating velocities (UF). There is nontrivial difference between the UF values in theoretical analysis, numerical simulations, and space experiments, and the most possible reason is the assumed different migrating distances to reach steady states in different investigations. © 2012 American Institute of Physics. Source


Wang H.,State Nuclear Power Technology R and nter | Chen P.,State Nuclear Power Technology Corporation Ltd
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 | Year: 2015

The AP1000 nuclear power plant safety system is characterized by its unique passive Emergency Core Cooling System (ECCS), including Core Makeup Tanks (CMTs), Automatic Depressurization System (ADS), and In-containment Refueling Water Tank (IRWST), to mitigate SBLOCA accident. The most challenging period of AP1000 SBLOCA transient is the transition from CMT injection to IRWST injection after the actuation of the fourth stage ADS (ADS4). This paper is to report a transient evaluation model for AP1000 SBLOCA analysis during CMT to IRWST transition. The model simulates ADS4, CMT injection, IRWST injection, reactor core mixture level and upper plenum entrainment to hotlegs. Both critical and non-critical flow models are used to calculate mass flow loss through ADS 1-4 vents. The most important feature of this model is that it constantly traces core/upper plenum two-phase mixture level, which demonstrates cooling capability of ECCS during the transient. A baseline case is analyzed to study ADS-IRWST transient using AP1000 prototypic information. In addition, a sensitivity analysis is performed to further study the robustness of AP1000 ECCS during SBLOCA transient. Source

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