Abstract: The present invention concerns improved corrosion resistant zirconium alloys consisting of 0.25 to 1.50% by weight of niobium, 0.025 to 0.20% by weight of tin, 0.02 to 1.00% by weight of combined chromium and molybdenum, and the remainder zirconium except for unavoidable impurities.Corrosion tests show that the above alloys have a corrosion rate comparable to Zircaloy 2 at low temperatures and a much better performance at high temperatures. Further the hydrogen uptake of the present alloys are considerably lower than for Zircaloy 2 over the whole temperature range 290.degree.-500.degree. C., and reactor tests have revealed that the good corrosion behavior is maintained under neutron irradiation. The new alloys exhibit smaller grain growth than Zircaloy 2 at annealing temperatures.
Type:
Grant
Filed:
March 3, 1978
Date of Patent:
July 15, 1980
Assignees:
AB Atomenergi, Atomenergikommissionen, Institutt for Atomenergi, United Kingdom Atomic Energy Authority, Valtion Teknillinen Tutkimuskeskus
Inventors:
Liv Lunde, Raymond C. Asher, Gerard Slattery, Frank W. Trowse, Christopher Tyzack, Gustaf C. stberg, Erich Tolksdorf
Abstract: In a method for determining the radiation received in the past by a TSC dosimeter, the dosimeter is connected to a voltage source providing a polarizing voltage across the dosimeter and to an external closed electric circuit. The initial current pulse then flowing through the dosimeter due to its capacitive properties is detected and measured and if its peak value lies within a predetermined range the actual reading-off of the radiation dose received by the dosimeter is started in that a heating of the dosimeter is initiated and the thermally stimulated currents then produced by the dosimeter in the external closed electric circuit are measured and recorded.