CAJ | 학술논문

国外核电站的运行经验表明，核电站乏燃料水池冷却（PTR）系统的虹吸破坏管性能存在安全隐患，在某些工况下不能有效阻断虹吸流。本文采用RELAP5软件对国内某典型核电站的虹吸破坏管性能进行安全分析。结果表明，在现有的设计条件下，虹吸破坏管无法及时、有效阻断管道断裂后产生的虹吸流动，乏燃料水池冷却水持续从断裂处泄漏，并导致冷却水管道入口露出水面，从而引起乏燃料水池冷却能力丧失，为核电站安全带来极大风险。进一步分析表明，虹吸流引起的乏燃料水池水位下降幅度受断裂点处距水面的高度差、管道流动阻力和 PT R系统的管道结构3个因素的共同影响；管道流动阻力可有效缓解和降低由管道断裂引发的虹吸流动的危害性。
국외핵전참적운행경험표명，핵전참핍연료수지냉각（PTR）계통적홍흡파배관성능존재안전은환，재모사공황하불능유효조단홍흡류。본문채용RELAP5연건대국내모전형핵전참적홍흡파배관성능진행안전분석。결과표명，재현유적설계조건하，홍흡파배관무법급시、유효조단관도단렬후산생적홍흡류동，핍연료수지냉각수지속종단렬처설루，병도치냉각수관도입구로출수면，종이인기핍연료수지냉각능력상실，위핵전참안전대래겁대풍험。진일보분석표명，홍흡류인기적핍연료수지수위하강폭도수단렬점처거수면적고도차、관도류동조력화 PT R계통적관도결구3개인소적공동영향；관도류동조력가유효완해화강저유관도단렬인발적홍흡류동적위해성。
The feedback from foreign countries shows that the performance of siphon-breaker pipe in some nuclear power plants is insufficient and potential safety risk .In the present study ,numerical simulation was carried out with RELAP5 code to verify the performance of siphon-breaker pipe of PTR system for a typical nuclear power plant . The results show that under the present design siphon-breaker pipe can’ t break the siphon flow in time ,as the results ,the coolant in the spent fuel storage pool will be continuously drained out and can yield the exposure of the coolant pipe inlet ,and the cooling function of the used fuel storage pool is lost ,so that huge safety risk of nuclear power plant is created .The coolant level decreased in spent fuel pool is affected by the height difference between rupture location and free level in pool ,flow resistance and pipe configuration of PTR system .The flow resistance of PTR pipe can alleviate the consequence of siphon flow by pipe rupture .