Time filter

Source Type

Zhou Z.,Tsinghua University | Zhou Z.,State Nuclear Power Technology R and nter | Yang Y.,Tsinghua University | Xu H.,State Nuclear Power Technology R and nter
Nuclear Fusion | Year: 2011

This paper presents a preliminary study on neutron physics characteristics of a light water cooled fission blanket for a new type subcritical fusion-fission hybrid reactor aiming at electric power generation with low technical limits of fission fuel. The major objective is to study the fission fuel cycling performance in the blanket, which may possess significant impacts on the feasibility of the new concept of fusion-fission hybrid reactor with a high energy gain (M) and tritium breeding ratio (TBR). The COUPLE2 code developed by the Institute of Nuclear and New Energy Technology of Tsinghua University is employed to simulate the neutronic behaviour in the blanket. COUPLE2 combines the particle transport code MCNPX with the fuel depletion code ORIGEN2. The code calculation results show that soft neutron spectrum can yield M > 20 while maintaining TBR >1.15 and the conversion ratio of fissile materials CR > 1 in a reasonably long refuelling cycle (>five years). The preliminary results also indicate that it is rather promising to design a high-performance light water cooled fission blanket of fusion-fission hybrid reactor for electric power generation by directly loading natural or depleted uranium if an ITER-scale tokamak fusion neutron source is achievable. © 2011 IAEA, Vienna.

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.

Chen Y.,CAS Institute of Engineering Thermophysics | Chen Y.,University of Chinese Academy of Sciences | Han W.,CAS Institute of Engineering Thermophysics | Sun L.,State Nuclear Power Technology R and nter | Jin H.,CAS Institute of Engineering Thermophysics
Energy Procedia | Year: 2015

The use of an absorption refrigeration system is a promising way to utilize waste heat from industrial processes. Ammonia-water absorption refrigeration system is commonly used for freezing applications with temperatures lower than 0°C. When the refrigeration temperature is lower than-30°C, the performance dramatically decreases. We proposed a new absorption-compression refrigeration system to produce cooling energy at-30°C to-55°C. The proposed system comprised three subsystems, namely, a power generation subsystem using an ammonia-water mixture as the working fluid, an ammonia-water absorption refrigeration subsystem, and a CO2 compression refrigeration subsystem. The system utilized the heat source in a cascade manner. The power subsystem converted the high-temperature portion of heat into power to drive the CO2 compression refrigeration subsystem, thereby resulting in the generation of low-temperature cooling energy. The low-temperature portion of heat is converted into cooling energy to offer the heat sink of the CO2 compression refrigeration subsystem. A simulation study was conducted, and results showed that the coefficient of performance of the proposed system was 0.277, which was approximately 50% higher than that of a conventional two-stage absorption refrigeration system. This work may provide a new way to produce low-temperature cooling energy using mid-temperature heat source. © 2015 Published by Elsevier Ltd.

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.

Wang H.,State Nuclear Power Technology R and nter | Chen P.,State Nuclear Power Technology Corporation
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.

Chang L.,State Nuclear Power Technology R and nter | Zhou M.,State Nuclear Power Technology R and nter
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2015

In order to research the performance of Passive Containment Cooling System (PCS) and verify the containment safety of AP/CAP series pressurized water reactor nuclear power plants (NPPs), an integral test facility for PCS (short name CERT) is designed and constructed in China. In this paper, the CERT test facility is modeled using the T-H program GASFLOW. The steel containment shell and internals, including compartments, flow paths between compartments and heat sinks are considered. The thermal hydraulic response of the facility under scaled mass and energy release of LOCA is studied. Copyright © 2015 by JSME.

Lin Y.,State Nuclear Power Technology R and nter | Liyong H.,State Nuclear Power Technology R and nter
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2014

The advanced pressurized water reactor (APWR) uses a passive safety system relying on heat removal by condensation to maintain the containment within the design limits of pressure and temperature. The passive containment cooling system (PCCS) includes many natural phenomena mechanisms. Steam condensation is one of the most important phenomena. It is very significant for engineering designing and code developing to study the mechanism of steam condensation on cold surface. In this paper, the test pressurized vessel in the experimental test on steam condensation on the cold surface for CAP1400 is designed, and the structure pressure is calculated.. Copyright © 2014 by ASME.

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.

Xu H.,State Nuclear Power Technology R and nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2012

After Fukushima nuclear accident, much attention has been paid to the safety of the spent fuel pool (SFP). AP1000 spent fuel pool cooling system (SPS) is not a safety related system. It is not designed for design basis accident. But the safety of SFP in exterior disaster and severe accident is very important. The extensive damage mitigation guidelines (EDMG) of NEI to AP1000 SFP accident mitigation was studied, including internal strategy and external strategy. The results are useful for design AP1000 nuclear power plant and the mitigation when SFP exterior disaster happens.

Zhang P.,State Nuclear Power Technology R and nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2012

The isothermal dispersed bubbly flow in a vertical tube was simulated by Eulerian two-fluid method with two different turbulence models (RANS and LES). With proper inter-phase interaction models, the time averaged results of flow filed agree well with experiment results. The wall peak bubble distribution is captured and two-phase velocity fields are accurate. Compared with RANS SST turbulence model, the LES with WALE sub-grid model can get better agreement, and it also gives transient and detail information of the flow field.

Loading State Nuclear Power Technology R and nter collaborators
Loading State Nuclear Power Technology R and nter collaborators