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: A measuring device to be conveyed through an oil or gas pipeline at the bottom of the sea is provided for measuring the radioactivity of the surroundings along the pipeline. Thus, the support and/or the covering of the pipeline may be tested, the sea bottom sediments having an appreciably higher gamma radiation source strength than the sea water and the oil or gas which flow through the pipeline.
Type:
Grant
Filed:
May 19, 1977
Date of Patent:
March 27, 1979
Assignee:
Institutt for Atomenergi
Inventors:
John B. Dahl, Johnny Schatvet, Kristian Skarsvag
Abstract: A process for the extraction of alumina from aluminum-containing silicates is disclosed. The process comprises acid leaching of the raw material, iron extraction, precipitation of the aluminum fraction as the aluminum chloride hexahydrate, removal of sodium chloride and calcination to alumina. The process can be made continuous with substantial regeneration and recycling of process components.
Abstract: A fuel rod for nuclear reactors normally comprises an internal fuel core surrounded by an external cladding, a radial spacing being advantageously arranged between said core and cladding in order to avoid hard interaction between said parts. According to the present invention said spacing is gauged by elastically squeezing the cladding at least until contact with the internal fuel core is obtained. During the squeezing process the change of elastic behavior of the squeezed cladding at the instance of said contact formation is detected by repeatedly or continuously sensing the applied squeezing force and resulting cladding deformation, the elastic deformation at said instance being measured as an expression of the spacing to be gauged.