Evaluation of Reactor Pressure Vessel radiation damage in a VVER-1000 nuclear reactor

سال انتشار: 1395
نوع سند: مقاله کنفرانسی
زبان: انگلیسی
مشاهده: 484

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شناسه ملی سند علمی:

IMES10_137

تاریخ نمایه سازی: 6 اردیبهشت 1396

چکیده مقاله:

Radiation damage in materials results from nuclear collisions and reactions which produce energetic recoil atoms of the host material or reaction products. An important limiting factor of nuclear power plants (NPP) lifetime is the status of the reactor pressure vessel (RPV). Structural materials, such as the RPV, in a nuclear reactor are continuously irradiated and damaged by energetic neutrons, gammas and other particles resulting from the fission reactions. Accordingly, neutron irradiation affects the RPV mechanical properties by increasing the strength (neutron hardening) and decreasing the fracture toughness (neutron embrittlement). The most sensitive region in the RPV is an area adjacent to the reactor core, so-called the beltline region. Weld lines and their related heat affected zones (HAZs) in the beltline region are significantly important since these areas have a higher potential to various flaws. The microscopic defects produced in materials due to irradiation are referred to as radiation damage and Displacements Per Atom (DPA) is routinely used to characterize irradiation damage. In this research, for a typical VVER-1000 Russian type RPV, the areas of the highest neutron radiation flux (beltline) was identified and then by using the Monte Carlo neutron transport code MCNPX, neutron flux and fluence at the beltline were calculated. The results are compared with those values presented in the Final Safety Analysis Report (FSAR) of the VVER-1000 nuclear reactor. Afterward the SRIM computer program was used to simulate Reactor Radiation Damage in RPV. Radiation damage estimation was accomplished through the evaluation of the DPA. ASTM E693 displacement cross section dataset was used to calculate the DPA .

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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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