Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators
Jianping Zhou , Maolong Liu , Ziyi Xu , Limin Liu , Jianhua Cao
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引用次数: 0
Abstract
The transient thermal hydraulic characteristics of the helical-coiled steam generator (H-OTSG) is important for the safety of the nuclear reactor. No research has yet addressed the transition between natural circulation and forced circulation in small modular pressurized water reactors equipped with H-OTSGs. In the present study, a numerical simulation study was carried out to investigate the transient thermal hydraulic characteristics of a H-OTSG during a transient process between forced circulation and natural circulation using the SGTH-1D code. Different transition schemes have significant impact on the thermal-hydraulics characteristics of the H-OTSG. An optimized transition scheme was established to perform a smooth transition between forced circulation and natural circulation without significant perturbation on the shell- and tube-side parameters. The results of the present study can be used to optimize the operation procedure of the small modular reactor equipped with H-OTSGs.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.