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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 392-406
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32648
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on the mechanical properties, structure, and peculiarities of void formation in the Mo-Zr-B alloy within the temperature range from 400 to 1080° C and fluences (1.3 to 11.5) · 1025 n/m2 (>0.1 MeV) has been investigated. The results from radiation studies of poly- and monocrystalline molybdenum, Mo—0.12 Zr—0.16 Ti alloy and of the Mo-Zr-B alloys with different initial thermal treatment have been analyzed. At temperatures of 950 and 1080°C, the voids of nonequiaxial shape are formed, and at 1010°C only planar defects, supposedly thin precipitates, are observed. These results show a minimum swelling of the Mo-Zr-B alloy at 1010°C. It is expected that the peculiarities of void evolution in the Mo-Zr-B alloy are due to the impurity precipitation on void faces. A good correlation of the calculated and experimental values for radiation strengthening of the alloy as a result of voids and dislocation loops within a wide range of their sizes and concentrations was observed. A connection was found between the reduction of the uniform elongation within the temperature range from 400 to 900° C and voidage parameters. A maximum strengthening of the alloy takes place after irradiation at 635°C, which results from a high density of both 1.5-nm-diam voids and the dislocation loops.