1968
DOI: 10.1016/0029-5493(68)90015-0
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Critique of in-place annealing of SM-1A nuclear reactor vessel

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1969
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Cited by 14 publications
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“…This is also true for the restoration of the properties of reactor vessels. It is well known that abroad the vessel of a small-size military reactor SM-1A was annealed by nuclear heat ("wet" annealing) to extend service life [5]. The experiments performed at the Prometey Central Research Institute of Structural Materials also showed a substantial decrease of embrittlement with the irradiation temperature increased briefly from 270 to 340°C [6].…”
Section: Model Materialsmentioning
confidence: 99%
“…This is also true for the restoration of the properties of reactor vessels. It is well known that abroad the vessel of a small-size military reactor SM-1A was annealed by nuclear heat ("wet" annealing) to extend service life [5]. The experiments performed at the Prometey Central Research Institute of Structural Materials also showed a substantial decrease of embrittlement with the irradiation temperature increased briefly from 270 to 340°C [6].…”
Section: Model Materialsmentioning
confidence: 99%