By Ernest J. Henley, Jeffery Lewins
Advances in Nuclear technology and expertise, quantity 7 offers details pertinent to the elemental points of nuclear technological know-how and know-how. This ebook discusses the secure and priceless improvement of land-based nuclear strength plants.
Organized into 5 chapters, this quantity starts with an summary of irradiation-induced void swelling in austenitic stainless steels. this article then examines the significance of varied delivery strategies for fission product redistribution, which relies on the diffusion information, the vaporization houses, and the solubility within the gas matrix. different chapters think about the integro-differential type of the linear shipping equation, which kinds the root for the learn of neutron distributions. This publication discusses in addition the W–H method and its relevance in shipping thought. the ultimate bankruptcy bargains with nuclear reactor defense and describes the method in combating thermal explosions.
This e-book is a worthy source for thermal reactor physicists, commercial engineers, theoreticians, scientists, and study employees.
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Additional resources for Advances in Nuclear Science and Technology: v. 7
4 x 1 0 n / c m . Over this range of temperatures a peak in swelling at 460 °-480 °C was ob served for both 304 stainless steel and Incoloy 800, whereas types 316, 316L, and 347 exhibited a peak in swelling at 500°-520°C. After irradiation at 520550°C peak swelling increased in the following order: types 347, 316, 316L, 304, and Incoloy 800. After irradiation at 600 °C Incoloy 800 again showed the largest volume increase and the stabilized alloys 321 and 347 showed the smallest (37). T E M examinations of types 304, 316, and 347 stainless steel irradiated at 2 2 2 520°-550°C and at fluences to 7 x 1 0 n / c m in the above investigations (37) showed that intragranular precipitates provided favorable sites for void formation.
88) also revealed the unfaulting of loops and the development of dislocation networks above about 2 0 d p a ; however, a de crease in dislocation density at high doses was observed only for nickel. From 10 2 a maximum of 5 x 1 0 lines/cm at 40 dpa, the dislocation density decreased by nearly an order of magnitude at a dose of 350 dpa. Observations during H V E M bombardment have provided direct evidence for the influence of dislocations on void growth. Buswell et al. (60) found that maximum void growth occurred for an intermediate dislocation density.
In some cases the amount of dissolved hydrogen is sufficiently large that loops are prismatically punched from the voids due to high internal pressures (62). Again, internally trapped H 2 0 is probably responsible, as is indicated from electrodiffusion studies (86). Hydrogen effects on void formation are also evident from ion-bombard ment studies. Nelson and Mazey (67) bombarded 316 stainless steel with pro tons and observed a definite change in the size and density of voids when the hydrogen content was exceeded by 100% of normal.