Nuclear reactor applied on ship or floating platform recommend miniaturization and optimization of PRHRs. Due to much larger volume and heat transfer area in PRHRs heat exchanger, miniaturization and design of PRHRs n...
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The compatibility and anti-interference capability of wireless sensor networks within nuclear power plants in complex electromagnetic environments are the most essential elements to ensure reliable operation and effec...
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Metal matrix microencapsulated (M3) fuel is one of the research directions on Accident Tolerant Fuel (ATF). In this article, it provides one of ATF design which consists of BISO (Bistructural ISOtropic) particles embe...
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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.
The main trend in the development of the local power plant control system is to adopt digital safety DCS system with rather strong ability of self-diagnosis. Apart from the self-diagnosis, it is also necessary to carr...
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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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The lack of fast neutron irradiation test equipment is a key practical factor that restricts the development of the new generation nuclear energy technology with fast reactor as the core in China. Scarce isotopes such...
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