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key technical requirements passive safety system design case general design requirements passive safety systems introduction analysis standard design passive system rudder angle control accuracy construction surfaces electrohydraulic block brake pusher scopethis standard
GB/T 35730-2017 in English

GB/T 35730-2017 in English

VALID

General design requirements of pressurized water reactor nuclear power plantswith passive safety systems

  • Issued on:2017-12-29
  • Implemented on:2018-07-01
  • File Format:PDF
  • Delivery:Via email within 5 business days
Price(USD): $810.00
$786.00
Standard No: GB/T 35730-2017
Document status: VALID
Title in English: General design requirements of pressurized water reactor nuclear power plantswith passive safety systems
Title in Chinese: 非能动安全系统压水堆核电厂总设计要求
Language: English
File Format: Electronic (PDF)
Delivery: Via email within 5 business days
Issued on: 2017-12-29
Implemented on: 2018-07-01
ICS Classification: 27.120.20-Nuclear power plants. Safety
Chinese Classification: F65-Nuclear island of nuclear power plant
Professional Classification: GB-National Standard
Related Keywords: key technical requirements passive safety system design case
general design requirements
passive safety systems introduction analysis
standard design
passive system
Related Topics: PWR
PWR nuclear power plant loose parts and
passive pressurized water reactor
Requirements for non-aqueous assays
Design of foundations for nuclear safety-related workshops in pressurized water reactor nuclear power plants
Design criteria for equipment cooling water system of passive pressurized water reactor nuclear power plant
Thirteenth Five-Year Nuclear Power Plant Safety Requirements
system pressure
unconventional security climate
GBT35730
GB/T 35730-2017
Safety requirements for new nuclear power plants

《GB/T 35730-2017非能动安全系统压水堆核电厂总设计要求》由TC58(全国核能标准化技术委员会)归口,TC58SC3(全国核能标准化技术委员会反应堆技术分会)执行,主管部门为国家标准化管理委员会。


Introduction

Analysis of the core content of the standard

Design elementsGB/T 35730-2017 requirementsComparison with traditional nuclear power standards
Safety objectivesCore damage frequency <10^-5/reactor year, radioactive release frequency <10^-6/reactor yearGenerally required to be 10^-4~10^-5/reactor year
Seismic designSingle SSE benchmark (PGA=0.3g), OBE requirement cancelledUsually SSE+OBE dual benchmark is adopted
Passive systemNo intervention required for 72 hours, driven by natural forcesReliant on active equipment + emergency power supply

Detailed explanation of key technical requirements

Passive safety system design case (AP1000)

Appendix A/B of the standard uses AP1000 as an example to demonstrate the typical configuration of the passive system:

  • Core makeup water tank: Emergency cooling by gravity injection
  • Containment cooling system: Natural air circulation to remove heat
  • Passive residual heat removal: High-level water tank + density difference drive

Implementation suggestions

  1. Modular construction: Refer to Chapter 7.8, the maximum lifting weight of the structural module is controlled within 800 tons
  2. Seismic verification: The time history analysis method is used to verify the structural integrity of the containment under SSE
  3. Fire partitioning: Set up a 3-hour fire resistance limit barrier according to HAD102/11 requirements

Standard evolution analysis

The significantly improved requirements of this standard are reflected in:

  • The concept of Design Extended Conditions (DEC) is added, and it is required to consider beyond the design basis accident
  • The requirements for hydrogen concentration control under severe accidents are clarified (<10% volume fraction)
  • The platform diversity requirements of the digital instrumentation and control system are specified

Sample only — not a preview of GB/T 35730-2017
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