Zobrazeno 1 - 10
of 45
pro vyhledávání: '"E. Tenckhoff"'
Autor:
E. Tenckhoff, M. Erve
Publikováno v:
Nuclear Engineering and Design. 144:139-148
The safety standard which is attained at the time of initial startup by a nuclear power plant built in accordance with state-of-the-art design and engineering principles must be assured throughout the plant's entire lifetime. Based on operating exper
Publikováno v:
Kerntechnik. 57:353-359
Tensile, burst, and creep tests have been conducted at 320 to 400°C on Zircaloy tubing. The main emphasis was placed on moderately stress-relieved tubing although tubing ranging from cold worked to fully recrystallized conditions also was investigat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4fe49470fb6baf849c31940d36a8cf7c
https://doi.org/10.1520/stp35587s
https://doi.org/10.1520/stp35587s
Autor:
E Tenckhoff
A general review of the texture characteristics in hexagonal close-packed metals is given with special reference to zircaloy tubing used in the nuclear industry. Conclusions concerning the deformation forces and their effect on the resulting deformat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1aa1ea8f925e02475bfb523cfcd64ab
https://doi.org/10.1520/stp37043s
https://doi.org/10.1520/stp37043s
The corrosion of Zircaloy in water reactors is dependent on the water chemistry of the primary coolant and the fast neutron flux. Under standard pressurized water reactor (PWR) coolant conditions with hydrogen overpressure, resulting in a low oxygen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bc65c16b187ee22e0e31fb6212137c42
https://doi.org/10.1520/stp36674s
https://doi.org/10.1520/stp36674s