Wei Liu , Jin Shi , Yang Liu , Yuhang Chen , Pan Wu , Kun Hou , Xuelin Li , Ying Zhang , Maogang He
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引用次数: 0
Abstract
Helium is a commonly used circulating working fluid in high-temperature gas-cooled reactors (HTGR). The thermophysical properties of helium are crucial for HTGR design and operation. The isobaric specific heat capacity, viscosity and thermal conductivity of helium were determined in this study based on flow method, capillary method and dynamic light scattering (DLS) method, respectively. To fill the data gap, the measurements were conducted over a temperature range of 293 K∼773 K and at pressures up to 7 MPa. The relative uncertainty estimates for the experimental apparatuses of isobaric specific heat capacity, viscosity, and thermal conductivity are less than 0.9%, 1.4%, and 2.2%, respectively. Based on the experimental data, the deviation of the existing calculation models for isobaric specific heat capacity, viscosity and thermal conductivity were analyzed. The calculation model posted by the Nuclear Safety Standards Commission (KTA) was modified to improve the reliability in the target p-T region.
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.