A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydrau...
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A 3rd generation reactor called HuaLong is developed by China National Nuclear Corporation (CNNC). S econdary passive system (PRS) is designed to remove the residual heat during 72 hours after the reactor trips. To ve...
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ISBN:
(纸本)9781510811843
A 3rd generation reactor called HuaLong is developed by China National Nuclear Corporation (CNNC). S econdary passive system (PRS) is designed to remove the residual heat during 72 hours after the reactor trips. To verify the ability of PRS system, the test facility ESPRIT is built in Chengdu which is 1:1 in heigh t and 1/62.5 in power. Tests are consisted by three Steady-states and one transient. One model of RELAP5 mod3.2 is developed and used to simulate the steady and transient tests. The results of RJELAP5 show con sistent with facility results, but the early phenomenon during transients is different between RELAP5 and tests as RELAP5 underestimates the direct-contact condensation power.
The small modular reactor (SMR), which is coded ACP100 and developed by China National Nuclear Corporation(CNNC), is an innovative PWR based on existing PWR technology, adapting "passive" safety system and &...
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ISBN:
(纸本)9781510808096
The small modular reactor (SMR), which is coded ACP100 and developed by China National Nuclear Corporation(CNNC), is an innovative PWR based on existing PWR technology, adapting "passive" safety system and "integrated" reactordesigntechnology. It can reach large power by several modular combinations and can be used in different places and different condition. This paper introduces the main technical characteristic of ACPI00 firstly, for example, integrated layout of primary system and equipment, larger primary coolant inventory, once-through steam generator (OTSG), complete passive safety systems, multi-unit layout, and so on. Based on the description of the main technical characteristic of the ACPI00, the basic design rules and requirements for the ACPI00 instrumentation and control (I&C) system are introduced in this paper. The overall I&C system architecture is also introduced. Especially, the design scheme and features of the NSSS I&C systems, including reactor power control system, OTSG feedwater control system, reactor protection system, in-core instrumentation system, ex-core neutron flux monitoring system, are discussed in this paper. Furthermore, the simulation studies for the main control systems are introduced in the paper, including simulation method, simulation models and simulation results. The control scheme of these control systems are validated by the simulation study.
C-ring, whose sealing behavior is the key to the sealing structure, is one of the main seal-rings for reactor Pressure Vessel. A finite element model with less simplification has been established using ANSYS APDL to s...
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Hydrogen security is an important problem of the severe accident analysis in NPP, and the security of hydrogen detonation is more important. The hydrogen risk mainly focused on the risk of flame acceleration (FA) and ...
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Water-lubricated thrust bearing is one of the key parts in canned motor pump, for example, the RCP in AP1000, and it functions to balance axial loads. A calculation model which can handle all flow state lubrication pe...
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The direct contact condensation (DCC) is a significant phenomenon in nuclear reactor and its balance facilities, together with other chemical engineering systems. DCC occurs when the vapor is injected into the subcool...
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作者：
XUE YangXIONG Fu-ruiSUN Jian-qiaoDepartment of Mechanics
Tianjin UniversityTianjin300350China Science and Technology on Reactor System Design Technology LaboratoryNuclear Power Institute of ChinaChengdu 610041China School of EngineeringUniversity of CaliforniaMercedCA 95343USA
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