tailieunhanh - Material Science_ Vol 2 of 2 - US DOE (1993) Episode 11

Tham khảo tài liệu 'material science_ vol 2 of 2 - us doe (1993) episode 11', kỹ thuật - công nghệ, cơ khí - chế tạo máy phục vụ nhu cầu học tập, nghiên cứu và làm việc hiệu quả | Plant Materials DOE-HDBK-1017 2-93 EFFECT DUE TO NEUTRON CAPTURE TABLE 2 Effect of Fast-Neutron Irradiation on the Mechanical Properties of Metals Integrated Radiation Tensile Yield Fast Flux Temperature Strength Strength Elongation Material NVT C MPa MPa Austenitic SS 0 576 235 65 Type 304 x 1021 100 720 663 42 Low Carbon 0 517 276 25 steel x 1019 80 676 634 6 A-212 .2 C x 1020 80 800 752 4 x 1019 293 703 524 9 x 1019 404 579 293 14 Aluminum 0 124 65 6061-0 x 1020 66 257 177 Aluminum 0 310 265 6061-T6 x 1020 66 349 306 Zircaloy-2 0 276 155 13 x 1020 138 310 279 4 One of the areas of the reactor vessel that is of most concern is the beltline region. The Nuclear Regulatory Commission requires that a reactor vessel material surveillance program be conducted in accordance with ASTM standards in water-cooled power reactors. Specimens of steel used in the pressure vessel must be placed inside the vessel located near the inside vessel wall in the beltline region so that the neutron flux received by the specimens approximates that received by the vessel inner surface and the thermal environment is as close as possible to that of the vessel inner surface. The specimens are withdrawn at prescribed intervals during the reactor lifetime and are subjected to impact tests to determine new NDT temperatures. Figure 5 shows the increase in NDT temperature for a representative group of low carbon steel alloys irradiated at temperatures below 232 C. Many current reactors have core pressure vessel wall temperatures in the range of 200 C to 290 C so that an increase in NDT is of very real concern. Irradiation frequently decreases the density of a metal over a certain temperature range so that a specimen exhibits an increase in volume or swelling. The swelling of stainless steel structural components and fuel rod cladding resulting from fast neutron irradiation at the temperatures existing in fast reactors is a matter of great concern

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