Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (3) effect of B4C addition on thermophysical properties of austenitic stainless steel in a liquid state

Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano

研究成果: Paper査読

1 被引用数 (Scopus)

抄録

Thermophysical properties of molten mixture of 316L stainless steel (SS316L) and control-rod material (B4C) are necessary for the development of computer simulation codes that describe core degradation mechanisms during severe accidents in nuclear power plants involving sodium-cooled fast reactors. The effect of B4C addition to SS316L on the solidus and liquidus temperatures were first measured by differential scanning calorimetry. An electromagnetic levitation technique performed in a static magnetic field was used to measure the density, surface tension, normal spectral emissivity, specific heat capacity, and thermal conductivity of molten SS316L and SS316L containing B4C. The effects of B4C addition to SS316L on the thermophysical properties were studied up to 10 mass% of B4C.

本文言語English
ページ853-857
ページ数5
出版ステータスPublished - 2020 1 1
イベント14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
継続期間: 2019 9 222019 9 27

Conference

Conference14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
CountryUnited States
CitySeattle
Period19/9/2219/9/27

ASJC Scopus subject areas

  • Fuel Technology
  • Nuclear Energy and Engineering

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