STUDY ON SAFETY RELIEF VALVE TESTING LOOP OF HTR-10PRIMARY LOOP PRESSURE RELIEF SYSTEM

摘要

10MW High Temperature Gas Cooled Reactor(HTR-10) reached its first full power operation inJanuary of 2003 in Tsinghua University. In HTR-10,Steam Generator (SG) heat transfer tubes areprotective screens between the primary loop ofhelium and the secondary loop of water and steam.Water and steam will enter into the primary loopfrom the secondary loop if the SG heat transfer tubesrupture, which is one of the reasons to lead toincrease of the primary loop pressure. Function ofthe primary loop pressure relief system (PLPRS) isto reduce the pressure of the primary loop bydischarging part of helium of the primary loop whenthe SG heat transfer tubes rupture so that thepressure will not exceed the designed maximumpressure value of the primary loop.The PLPRS has two helium safety relief valves.In order to guarantee the function of the PLPRS, theset point pressures and the discharge capacity of thesafety relief valves must be tested periodically, sayevery 30 months. Because the safety relief valvesare the pressure boundaries of the primary loop, thesafety relief valves will be contaminated after thereactor operates for a period of time. So the testshould be done on site. In order to do so, a test loopwas designed and constructed in the reactor.This paper presents the design and constructionof the helium safety relief valve test loop in HTR-10.The test results have shown that the test loop can beused to check the set point and the dischargecapacity of the helium safety relief valves.