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BWRX-300 SMR passes U.K. regulatory milestone
GE Vernova Hitachi Nuclear Energy’s BWRX-300 small modular reactor has completed the second step of the generic design assessment (GDA) process in the United Kingdom. In this step, the U.K. Office for Nuclear Regulation, the Environment Agency, and Natural Resources Wales did not identify “any fundamental safety, security safeguard or environmental protection shortfalls with the design of the BWRX-300.” Step 1 was completed in December 2024.
W. Breitung, K. O. Reil
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 205-217
Technical Paper | doi.org/10.13182/NSE90-A19186
Articles are hosted by Taylor and Francis Online.
A sample of (U,Pu)-mixed oxide was fission heated along the saturation line and into the compressed liquid regime. The density of the sample at temperatures around 7000 K was determined from the onset of the liquid-phase pressure signal. Values for the compressibility of the (U,Pu)-mixed oxide were determined from the slope of the measured pressure/time signal. Based on these results and earlier measurements, new relations are proposed for the following properties: the density/enthalpy, density/temperature, thermal expansion/temperature, and isothermal compressibility/temperature relations. The ranges of validity are 1400 to 3600 kJ/kg and 3120 to 7600 K, respectively. The property relations are recommended for both liquid UO2 and (U,Pu)O2 with yPu ≤ 0.25. The measured data strongly suggest that the critical temperature of (U,Pu)O2 is well above 8000 K.