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

Research output: Contribution to conferencePaperpeer-review

1 Citation (Scopus)

Abstract

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.

Original languageEnglish
Pages853-857
Number of pages5
Publication statusPublished - 2020 Jan 1
Event14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
Duration: 2019 Sep 222019 Sep 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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