Evaluation of Reactor Pressure Vessel radiation damage (DPA) in a VVER-1000 (V-446) nuclear reactor

سال انتشار: 1395
نوع سند: مقاله کنفرانسی
زبان: انگلیسی
مشاهده: 569

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شناسه ملی سند علمی:

PENPP01_102

تاریخ نمایه سازی: 19 خرداد 1396

چکیده مقاله:

The reactor pressure vessel (RPV) is one of the most critical elements with the highest priority in safety rankings. Therefore it is closely monitored and tested by surveillance programmes. Structuralmaterials in a nuclear reactor are damaged by radiation from fission reactions. Neutron irradiation influences the mechanical properties of the RPV steels by increasing the strength (neutron hardening) and decreasing the toughness (neutron embrittlement). The most sensitive location in the RPV is theregion adjacent to the reactor core (termed the beltline region). Weld lines and their heat affected zones(HAZs) in this region are particularly important since these regions have a higher probability of havingflaws. In this paper, the areas where the neutron radiation flux in the RPV is maximum and neutron spectra in those areas have been identified with MCNPX, a Monte Carlo code which is able to calculateneutron flux or fluence, and the results have been compared to the values presented by calculation inFinal Safety Analysis Report (FSAR) of the VVER-1000 NPP. Then the RPV of VVER -1000 NPP was simulated by SPECOMP code that used to calculate DPA cross sections for compounds that are not already contained in the SPECTER computer code. The SPECTER computer code used to produce neutron spectral-averaged DPAs values for the beltline region of RPV. Finally the highest sensitive zone on the inner surface of VVER-1000 RPV has been determined prior to neutron flux effect.

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نویسندگان

Kamal Hadad

Faculty of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran

Fazel Ghazi Ardekani

Ph.D. Student, Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz,Iran

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  • آدرماه 395 1 - اس‌تان بوشهو ...
  • G. S. Was, Fundamentals of Rad iationMaterias Sci ence-Metals and ...
  • V.A. Nikolaev, L.N. Ryadkov in: Irradiated Material Science and Strength ...
  • Stoller R.E. in: Journal of ASTM international, vol. 1, No ...
  • N. Soneda, K. Dohi, K. Nishida, A. Nomoto et.al Flux ...
  • A.A. Chernobaeva, A.M. Kryukov, A.D. Amaev, D.Yu. Erak, P.A. Platonov, ...
  • D.Yu. Erak, B.A. Gurovich., Y.I. Shtrombakh, D. Zhurko. Degradation and ...
  • M. Kirk Assessment of flux effect exhibited by IVAR database. ...
  • Williams T. Om the differences and commonal ities , In: ...
  • J.S. Hendricks, G.W. McKinney, L.S. W aters, T.L. Roberts, et ...
  • Wolfgang Hoffelner. Materials for Nuclear Plants From Safe Design to ...
  • L. R. Greenwood, "SPECOMP Calculations of Radiation Damage in Compounds, ...
  • L. R. Greenwood and R. K. Smither, "SPECTER: Neutron Damage ...
  • D.Yu. Erak, B.A. Gurovich., Y.I. Shtrombakh, D. Zhurko. Degradation and ...
  • M. Kirk Assessment of flux effect exhibited by IVAR database. ...
  • نمایش کامل مراجع