论文信息 - Estimation of material degradation of VVER-1000 baffle

Estimation of material degradation of VVER-1000 baffle

The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark. Service life extension for another 10 to 30 years is now under investigation. Life extension requires the evaluation of pressure vessel internals degradation under long-term irradiation. One of the possible limiting factors for the service life of VVERs is a void swelling of the Russian type titanium stabilized stainless 08Ch18N10T steel used to construct the baffle surrounding the core. This article aims to show first steps towards deeper analysis of the baffle degradation process and to demonstrate the possibilities of precise calculation and measurements on the VVER-1000 mock-up in LR-0 reactor.

[1] R. Averback,et al. Displacement damage in irradiated metals and semiconductors , 1997 .

[2] F. Garner,et al. Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30–60 years , 2013 .

[3] R. Smither,et al. SPECTER: neutron damage calculations for materials irradiations , 1985 .

[4] Michal Košt’ál,et al. Absolute determination of power density in the VVER-1000 mock-up on the LR-0 research reactor. , 2013, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

[5] N. M. Larson,et al. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .

[6] V. Rypar,et al. Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor , 2012 .

[7] B. Margolin,et al. The Relationship of Radiation Embrittlement and Swelling for Austenitic Steels for WWER Internals , 2009 .

[8] E. Novák,et al. Applicability of LR-0 mock-up results to VVER-1000 reactor pressure vessel issues , 2016 .

[9] F. Garner,et al. Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling , 2009 .

[10] M. Robinson,et al. A proposed method of calculating displacement dose rates , 1975 .

[11] Michal Košťál,et al. The pin power distribution in theVVER-1000 mock-up on the LR-0 research reactor , 2012 .