SOARCA Uncertainty Analysis of a Short-Term Station Blackout Accident at the Sequoyah Nuclear Power Plant.
Abstract not provided.
Engineering topics
Publications and source records attributed to Dennis, Matthew L..
Abstract not provided.
Energy policy can often be narrow and take a short-term view as well as beholden to public opinion as demonstrated by the early decommissioning of nuclear power plants (NPPs) in Germany and Belgium after the Fukushima Daiichi event. The subsequent pursuit of renewable electric power generating capacity should not lose sight of the value of technological diversity in an energy portfolio. Domestic market incentives have failed to maintain the U.S.'s technological diversity as demonstrated by the dwindling state of the nuclear power industry. The nuclear power industry faces many challenges, such as aging infrastructure, policy driven production disincentives, and licensing delays, which leave the nuclear power industry at a cross roads. However, there is an opportunity to identify both a socially beneficial technology mix which includes NPPs and corresponding strategies for retaining NPPs in the U.S. energy portfolio. This paper proposes three technical approach options to identify strategies to assist NPPs that will hopefully prove publicly unobtrusive, economically affordable, and potentially profitable.
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This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.
This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.
Abstract not provided.