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NRC proposed rule for licensing reactors authorized by DOE, DOD
Nuclear reactor designs approved by the Department of Energy or Department of Defense could get streamlined pathways through the Nuclear Regulatory Commission’s commercial licensing process should applicants wish to push the technology into the civilian sector.
A proposed rule introduced April 2 by the NRC would “improve NRC licensing review efficiency, where applicable, by explicitly establishing by regulation an additional means for reactor applicants to demonstrate the safety functions of their reactor designs, and thus, would contribute to the safe and secure use and deployment of civilian nuclear energy technologies.”
I. L. W. Wilson, F. W. Pement, R. G. Aspden, R. T. Begley
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 70-84
Technical Paper | Material | doi.org/10.13182/NT76-A31700
Articles are hosted by Taylor and Francis Online.
Stress-corrosion behavior of Type 304 stainless steel, Incoloy 800, Inconel 600, and Inconel 690 has been measured in both 10 and 50% NaOH environments. Both U-bend and C-ring samples were utilized, and test temperatures were in the range of 600 to 630°F. Differences in behavior between the two specimen configurations are attributed primarily to differences in stress level and distribution between the two types of specimens. Stress dependency of cracking of Inconel 600 and Incoloy 800 obtained on pressurized tubing samples was also measured. The total data indicate marked superiority of Inconel 600 at high stresses and high caustic concentrations. The C-ring samples of commercially prepared tubing were also exposed at 110% of the room temperature yield strength to strong (50%) mixtures of potassium and sodium hydroxides with and without admixtures of typical sludge species for prolonged periods. The general resistance to caustic cracking increased with the nickel content of the alloy; Type 304 stainless steel was the least resistant in all cases. Inconel Alloy 600 and the high-chromium-modification Inconel Alloy 690 were superior, with Incoloy 800 showing intermediate behavior. In uncontaminated caustic, only the stainless steels and Incoloy cracked in a three-month exposure, and a six-month exposure was required to produce attack in the Inconel 600. The additions of silica or silica-containing mixtures promoted attack. Low-level additions of halides or lead oxide did not enhance the caustic cracking.