原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2014年
2期
271-276
,共6页
谭效时%李晓伟%李笑天%何树延
譚效時%李曉偉%李笑天%何樹延
담효시%리효위%리소천%하수연
非能动%热工水力%预应力混凝土安全壳
非能動%熱工水力%預應力混凝土安全殼
비능동%열공수력%예응력혼응토안전각
passive%thermal-hydraulic%prestressed concrete containment
本文以C A P1700核电厂为例，提出了一种新的核电厂预应力混凝土安全壳及其非能动冷却方案，介绍了新式非能动安全壳冷却系统热工水力计算方法，并给出事故工况下新非能动安全壳冷却系统的运行参数。结果表明，C A P1700非能动安全壳冷却系统的设计是可行的，能满足事故工况下的冷却需求。贮水箱水量有很大的裕量，可通过计算进一步优化贮水量。
本文以C A P1700覈電廠為例，提齣瞭一種新的覈電廠預應力混凝土安全殼及其非能動冷卻方案，介紹瞭新式非能動安全殼冷卻繫統熱工水力計算方法，併給齣事故工況下新非能動安全殼冷卻繫統的運行參數。結果錶明，C A P1700非能動安全殼冷卻繫統的設計是可行的，能滿足事故工況下的冷卻需求。貯水箱水量有很大的裕量，可通過計算進一步優化貯水量。
본문이C A P1700핵전엄위례，제출료일충신적핵전엄예응력혼응토안전각급기비능동냉각방안，개소료신식비능동안전각냉각계통열공수력계산방법，병급출사고공황하신비능동안전각냉각계통적운행삼수。결과표명，C A P1700비능동안전각냉각계통적설계시가행적，능만족사고공황하적냉각수구。저수상수량유흔대적유량，가통과계산진일보우화저수량。
A new nuclear power plant prestressed concrete containment and its passive cooling system design were proposed for CAP1700 nuclear power plant as an example . T he thermal-hydraulic calculation method for the new passive containment cooling sys-tem of CAP1700 was introduced and the operating parameters in accident condition were obtained .The result shows that the design of passive containment cooling system for CAP1700 is feasible and can meet the cooling demand in accident condition .Reservoir capacity of tank has a big margin and can be further optimized by calculation .
