The verification test of the flow coefficient of the specialized pressure relief valve for serious accidents has been successfully witnessed
Recently, the Nuclear and Radiation Safety Center of the Ministry of Ecology and Environment (hereinafter referred to as the Nuclear Safety Center) organized a verification test of the flow coefficient of a special pressure relief valve for serious accidents at the National Nuclear and Radiation Safety Supervision Technology Research and Development Base. The relevant responsible comrades, chief engineers, chief experts of the Nuclear Safety Center, representatives of Harbin Engineering University, CGN Huizhou Nuclear Power Co., Ltd., CGN Engineering Co., Ltd., Dalian Dagao Valve Co., Ltd., and relevant comrades jointly witnessed the event.
The verification test of the flow coefficient of the special relief valve for serious accidents is mainly based on the low-pressure thermal hydraulic basic research test bench of the Nuclear Safety Thermal Hydraulic Laboratory. The joint test team composed of relevant departments of the Nuclear Safety Center and Harbin Engineering University designed a detachable globe valve and gate valve test section according to the requirements of GB/T 30832-2014, and determined representative test boundary conditions. The experiment aims to obtain the flow coefficient of the specialized pressure relief valve for serious accidents, verify the reliability of its calculation and analysis methods, and support the nuclear safety review of the final safety analysis report for Units 1 and 2 of Guangdong Taipingling Nuclear Power Plant. On site witness shows that the test bench is operating normally, the test boundary conditions and control parameters meet the requirements of the test outline, the test process is stable and controllable, and the obtained test data is true, reliable, and effective. Conducting verification tests on the flow coefficient of specialized pressure relief valves for serious accidents will further enhance the testing and verification capabilities of the Nuclear Safety Center, providing technical support for the design and development, safety analysis, and standard setting of important nuclear safety equipment. This verification test is an important measure taken by the Nuclear Safety Center to continuously deepen the "665" development strategy and enhance its nuclear safety review capabilities. The Nuclear Safety Center will continue to work with relevant units to carry out experimental verification work. Firstly, we will improve our positioning and deeply understand the importance of independent verification in ensuring nuclear safety; Secondly, we must adhere to the system concept, create benchmark projects for experimental verification, further solidify experience, improve standards, and forge teams, and form a replicable and promotable equipment testing and verification system; The third is to strengthen collaboration and sharing, gather the joint force of high-quality development of nuclear safety, closely cooperate with major universities, enterprises, and scientific research institutions, and jointly build a national level nuclear safety testing and verification platform. After the witnessing event, all participating units visited other testing facilities in the Nuclear Safety Thermal Hydraulic Laboratory of the Nuclear Safety Center.
Original text translated from: https://mp.weixin.qq.com/s/H9gn8j3fzrMMnfOCUBcC2A
