核动力工程
覈動力工程
핵동력공정
NUCLEAR POWER ENGINEERING
2009年
6期
1-7
,共7页
RPV寿命%辐照脆化%RG1.99-2
RPV壽命%輻照脆化%RG1.99-2
RPV수명%복조취화%RG1.99-2
RPV lifetime%Irradiation embrittlement%RG 1.99-2
以关注轻水反应堆压力容器(LWR-RPV)寿命为焦点,着重探讨了NRC-RG1.99-2中辐照脆化预计公式应用的局限性和不保守性;并建议对目前新建造的LWR-RPV的辐照脆化预计由新的公式取代或修改NRC-RG1.99-2中的公式.
以關註輕水反應堆壓力容器(LWR-RPV)壽命為焦點,著重探討瞭NRC-RG1.99-2中輻照脆化預計公式應用的跼限性和不保守性;併建議對目前新建造的LWR-RPV的輻照脆化預計由新的公式取代或脩改NRC-RG1.99-2中的公式.
이관주경수반응퇴압력용기(LWR-RPV)수명위초점,착중탐토료NRC-RG1.99-2중복조취화예계공식응용적국한성화불보수성;병건의대목전신건조적LWR-RPV적복조취화예계유신적공식취대혹수개NRC-RG1.99-2중적공식.
This paper focuses on the LWR-RPV lifetime and discusses the application limitation and non-conservative for the irradiation embrittlement predictive formula in NRC-RG1.99-2. It is suggested that a new irradiation embrittlement predictive formula shall be used for the newly built LWR-RPV, or the formula in NRC-RG 1.99-2 shall be revised.
