Strength Analysis of a Nuclear Reactor-Contained Compartment Under Design Loading Conditions
- Yi Yuan (Huazhong University of Science and Technology, CISSE, HUST) | Wen Dong (Huazhong University of Science and Technology, CISSE, HUST) | Zhengyi Zhang (Huazhong University of Science and Technology, CISSE, HUST) | Jianglong Sun (Huazhong University of Science and Technology, CISSE, HUST) | Jingxi Liu (Huazhong University of Science and Technology, CISSE, HUST) | De Xie (Huazhong University of Science and Technology, CISSE, HUST)
- Document ID
- International Society of Offshore and Polar Engineers
- The 28th International Ocean and Polar Engineering Conference, 10-15 June, Sapporo, Japan
- Publication Date
- Document Type
- Conference Paper
- 2018. International Society of Offshore and Polar Engineers
- 3D model, sequentially coupled thermal-stress analysis, finite element, Floating nuclear power plant, strength assessment
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- 11 since 2007
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A sequentially coupled thermal-stress procedure has been proposed for the strength evaluation of a typical Floating Nuclear Power Plant (FNPP) tank, which is of great importance for the nuclear security. At first, a novel 3D model has been developed for the required estimation of temperatures in tank's void spaces, followed by the calculation of the steady state temperature on the entire FNPP tank. Then, the calculation of stress distribution in the FNPP tank has been carried out using ABAQUS for given thermal and structural loading, which have been compared with the criteria provided in ASME codes.
Enabled by advances in nuclear and marine technologies, floating nuclear power plant (FNPP), which is a specific type of small modular reactors (SMRs), has recently emerged as an important facility to provide not only stable and affordable electricity but also adequate and continuous heat energy as well as desalinated water (Vujić, 2012; Lee, 2013; Jurewicz, 2015). The principle of FNPP can be defined as the combination of low-capacity nuclear power plants (LCNPPs) and floating ships/offshore platforms. It is not a completely new concept and has been explored in the past. As early as 1963, a Liberty ship that served in World War II was converted by the United States into the first FNNP (the MH-1A) equipped with a 10 MWe pressurized water reactor (PWR) (Jurewicz, 2015). After that, the FNPP research is in an inactive state until receiving resurgent attention in the last several years due to the aforementioned reasons.
Currently, there are mainly four institutions that have proposed their own designs of FNPPs. They are Naval Group formerly called Direction of Construction of Naval and Submarines (DCNS) in France (IAEA, 2014), Afrikantov OKBM in Russia, Massachusetts Institute of Technology (MIT) in the US (Jurewicz, 2015), and Korea Advanced Institute of Science and Technology (KAIST) in the Republic of Korea (Lee, 2011). While the other three are still in the early concept design stage, the Russian design is the most developed one with several attractive features, including mobility, free from the limitation of water depth, and relatively low cost.
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