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Nuclear Power Technologies through Year 2035
Published in D. Yogi Goswami, Frank Kreith, Energy Conversion, 2017
Kenneth D. Kok, Edwin A. Harvego
In the United States, the commercial nuclear industry in conjunction with the U.S. Department of Energy (DOE) has developed four advanced light-water reactor designs. Two of these are based on experience obtained from operating reactors in the United States, Japan, and Western Europe. These reactors will operate in the 1300 MW range. One of the designs is the advanced boiling water reactor (ABWR). It was designed in the United States and is already being constructed and operated in Asia. The NRC gave final design certification to the ABWR in 1997. It was noted that the design exceeded NRC “safety goals by several orders of magnitude.” The other type, designated System 80+, is an advanced PWR. This reactor system was ready for commercialization but the sale of this design is not being pursued.
Boiling Water Reactors
Published in Robert E. Masterson, Nuclear Engineering Fundamentals, 2017
The advanced boiling water reactor (or ABWR) is an attempt by the General Electric Company to simplify existing BWRs without having to completely redesign them. It uses new technology, new control systems, less piping, and fewer components than conventional BWRs do. The coolant pumps are also simplified by placing them directly inside the reactor vessel. Further simplification of the plant is achieved by eliminating most of the complex piping outside of the pressure vessel and many of the secondary recirculation pumps that these piping systems use.
Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor
Published in Nuclear Technology, 2020
In this study, a framework was developed to assess the output uncertainties of the MAAP5 code. The value of the 95% confidence level for 95th percentiles (95th/95%) of the output parameter is quantified. The plant analyzed is Taiwan Power Company’s Lungmen Nuclear Power Plant, which employs an advanced boiling water reactor (ABWR). The sequence selected for the analysis is a short-term station blackout. The output parameters chosen for this study are accumulated in-vessel hydrogen generation, which have also been categorized as a significant uncertainty by the MAAP Users’ Group14 (MUG) because of their direct relationship to metal oxidation and their effect on accident progression. Hydrogen is combustible and the detonation of accumulated hydrogen in the containment may threaten the integrity of the containment. In the Three Mile Island and Fukushima accidents, hydrogen played a dominant role in accident mitigation and management.