原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2014年
2期
291-297
,共7页
APEX-1000%非能动堆芯冷却系统%RELAP5/MOD3.3%小破口失水事故
APEX-1000%非能動堆芯冷卻繫統%RELAP5/MOD3.3%小破口失水事故
APEX-1000%비능동퇴심냉각계통%RELAP5/MOD3.3%소파구실수사고
APEX-1000%passive core cooling system%RELAP5/MOD3.3%small break loss of coolant accident
AP1000核电厂采用非能动堆芯冷却系统来缓解小破口失水事故（SBLOCA），缓解事故的理念是流动冷却。RELAP5/MOD3.3程序适用于传统核电厂SBLOCA 研究，对于非能动电厂SBLOCA研究的适用性需重新研究与评估。本工作基于非能动电厂小破口失水事故的分析，结合RELAP5/MOD3.3的结构与模型，对其进行评估和改进。为验证改进后的REL A P5/M OD3.3的适用性，以A P1000小破口失水事故的验证试验台架APEX-1000为模拟对象，分析模拟DBA-02、NRC-05事故工况。分析结果表明，改进后的REL A P5/M OD3.3的计算结果与试验数据符合较好。
AP1000覈電廠採用非能動堆芯冷卻繫統來緩解小破口失水事故（SBLOCA），緩解事故的理唸是流動冷卻。RELAP5/MOD3.3程序適用于傳統覈電廠SBLOCA 研究，對于非能動電廠SBLOCA研究的適用性需重新研究與評估。本工作基于非能動電廠小破口失水事故的分析，結閤RELAP5/MOD3.3的結構與模型，對其進行評估和改進。為驗證改進後的REL A P5/M OD3.3的適用性，以A P1000小破口失水事故的驗證試驗檯架APEX-1000為模擬對象，分析模擬DBA-02、NRC-05事故工況。分析結果錶明，改進後的REL A P5/M OD3.3的計算結果與試驗數據符閤較好。
AP1000핵전엄채용비능동퇴심냉각계통래완해소파구실수사고（SBLOCA），완해사고적이념시류동냉각。RELAP5/MOD3.3정서괄용우전통핵전엄SBLOCA 연구，대우비능동전엄SBLOCA연구적괄용성수중신연구여평고。본공작기우비능동전엄소파구실수사고적분석，결합RELAP5/MOD3.3적결구여모형，대기진행평고화개진。위험증개진후적REL A P5/M OD3.3적괄용성，이A P1000소파구실수사고적험증시험태가APEX-1000위모의대상，분석모의DBA-02、NRC-05사고공황。분석결과표명，개진후적REL A P5/M OD3.3적계산결과여시험수거부합교호。
The passive core cooling system is used in AP 1000 to mitigate the small break loss of coolant accident (SBLOCA) .The RELAP5/MOD3.3 code is generally applicable to the traditional NPP SBLOCA research , but for the passive NPP SBLOCA , its applicability will need further study and evaluation . Based on the analysis of the important phenomenon of the SBLOCA of the passive NPP , the RELAP5/MOD3.3 code was assessed and modified . In order to verify the applicability of the modified RELAP5/MOD3.3 code ,the DBA-02 and NRC-05 cases of APEX-1000 which was the test facility for verifying AP1000 small break loss of coolant accident ,were simulated . It shows good agreement between the results of the modified RELAP5/MOD3.3 code and experiment data .
