清华大学学报(自然科学版)
清華大學學報(自然科學版)
청화대학학보(자연과학판)
Journal of Tsinghua University
2001年
4_5期
112-115
,共4页
吴宗鑫%徐元辉%孙玉良
吳宗鑫%徐元輝%孫玉良
오종흠%서원휘%손옥량
高温气冷堆%非能动安全性%包覆颗粒燃料
高溫氣冷堆%非能動安全性%包覆顆粒燃料
고온기랭퇴%비능동안전성%포복과립연료
high temperature gas-cooled reactor (HTR)%passive safety%fuelelement formed with coated particles
10MW高温气冷实验堆(HTR-10)于2000年底在中国建成并实现临界,是一项重大的科研成果。它采用包覆颗粒燃料构成的球形燃料元件,堆芯有2.7万个燃料元件组成,四周由石墨反射层堆砌而成。氦冷却剂出口温度可达700℃。HTR-10具有非能动的安全特性。采用非能动余热载出的先进设计概念,可保证在任何事故工况下排除堆芯燃料熔化的可能性。该文介绍了10MW高温气冷实验堆的燃料元件、设计特点和安全特性。
10MW高溫氣冷實驗堆(HTR-10)于2000年底在中國建成併實現臨界,是一項重大的科研成果。它採用包覆顆粒燃料構成的毬形燃料元件,堆芯有2.7萬箇燃料元件組成,四週由石墨反射層堆砌而成。氦冷卻劑齣口溫度可達700℃。HTR-10具有非能動的安全特性。採用非能動餘熱載齣的先進設計概唸,可保證在任何事故工況下排除堆芯燃料鎔化的可能性。該文介紹瞭10MW高溫氣冷實驗堆的燃料元件、設計特點和安全特性。
10MW고온기랭실험퇴(HTR-10)우2000년저재중국건성병실현림계,시일항중대적과연성과。타채용포복과립연료구성적구형연료원건,퇴심유2.7만개연료원건조성,사주유석묵반사층퇴체이성。양냉각제출구온도가체700℃。HTR-10구유비능동적안전특성。채용비능동여열재출적선진설계개념,가보증재임하사고공황하배제퇴심연료용화적가능성。해문개소료10MW고온기랭실험퇴적연료원건、설계특점화안전특성。
The 10 MW high temperature gas-cooled reactor (HTR-10) reachedcritical in the end of 2 000 in China. The core of HTR-10 is composed of 27 000 graphite fuel elements formed with coated particles and surrounded by the blocks of graphite reflector. The outlet temperature of helium coolant could reach 700 ℃. The design of passive removal of decay heat by nature mechanism of heat radiation and conversion is adopted in HTR-10. It means that HTR-10 has the passive safety characteristics which could prevent the occurrence of core melt during any severe accidents. The paper describes the features of fuel element, reactor design and its safety.