Safety-class digital instrumentation and control system for nuclear power plant
By adopting a multi-node and point-to-point communication network in the nuclear power safety-grade digital instrumentation and control system, the communication between the reactor shutdown protection system, the dedicated safety facility drive system, and the safety control display system has been simplified. This has solved the problem of overly complex configuration of safety-grade DCS equipment qualification prototypes and reduced the qualification cycle and cost.
WO2026123632A1PCT designated stage Publication Date: 2026-06-18YANGJIANG NUCLEAR POWER
Patent Information
- Authority / Receiving Office
- WO · WO
- Patent Type
- Applications
- Current Assignee / Owner
- YANGJIANG NUCLEAR POWER
- Filing Date
- 2025-06-18
- Publication Date
- 2026-06-18
AI Technical Summary
Technical Problem
In existing technologies, the configuration scale of security-grade DCS equipment qualification prototypes is too complex, resulting in long qualification cycles and increased costs.
Method used
By employing multi-node and point-to-point communication networks, communication between the reactor shutdown protection system, the dedicated safety facility drive system, and the safety control display system is simplified. Through functional typification and minimum hardware configuration, the prototype of the safety-grade DCS equipment is simplified.
Benefits of technology
This effectively reduced the configuration size of security-grade DCS equipment qualification prototypes, shortened the qualification cycle, and lowered costs.
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Smart Images
Figure CN2025101847_18062026_PF_FP_ABST
Abstract
A safety-class digital instrumentation and control system (DCS) for a nuclear power plant (10), comprising a multi-node communication network (11) and a point-to-point communication network (12). A reactor trip protection system (13), an engineered safety features actuation system (14), and a safety control display system (15) are connected to the multi-node communication network (11). The reactor trip protection system (13) is connected to the engineered safety features actuation system (14) by means of the point-to-point communication network (12). The reactor trip protection system (13) is connected to a nuclear power simulation platform (18) and a signal preprocessing system (16) by means of a first communication interface. The safety-class DCS for the nuclear power plant (10) is simplified by selecting typical functions as basic applications, and using design principles of functional typification and minimal hardware configuration, and by means of the multi-node communication network (11) and the point-to-point communication network (12), the communication among the reactor trip protection system (13), the engineered safety features actuation system (14), a safety-related system, and the safety control display system (15) is realized, thereby simplifying the configuration scale for verifying the safety of a safety-class DCS device qualification prototype.
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