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FHR Research

USA-Czech Cooperation in research of FHR

Professional links between Czech and American research institutes initiated the discussion about bilateral Czech-American collaboration in the field and the cooperation of both parties intensify in the year 2008, when there were presented at the several international conferences the results of ongoing projects of Ministry of Industry and Trade of the Czech Republic related to the several US designs proposals of FHR reactor.

Towards the cooperation there were following steps taken:

  • On 6 December 2010, the Declaration of the cooperation in the field of nuclear energy between the Ministry of Industry and Trade of the Czech Republic and the U. S. Department of Energy was signed.
  • After the meeting of President Obama and Prime Minister Nečas In October 2011, when the support of technological cooperation between U.S. and Czech Republic was initiated, the ÚJV Group participates in the project of establishment a joint U.S. – Czech Center for Civil Nuclear Cooperation in Prague. Based on this technological cooperation a barrel with fluoride salt was sent from U.S. to Czech Republic and this enabled Czech Republic to participate in research of alternative coolant technology for in U.S. designed Fluoride cooled High temperature Reactor (FHR).
  • On 12 December 2012, the Memorandum of Understanding between the U.S. Department of Energy and the Ministry of Industry and Trade of the Czech Republic was signed; this was the very next step to the agreement for mutual cooperation.
  • On 17 May 2013, a special transport container including 75 kg of FLIBE (7LiF-BeF2, fused fluoride salts) for the research part of FHR programme arrived to ÚJV Řež.
  • On 26 March 2014 was signed the Agreement between the Ministry of Industry and Trade of the Czech Republic and the U.S. Department of Energy on cooperation in civilian research and development in the field of nuclear energy, where the research for FHR is explicitly mentioned among others research topics.
  • Salts testing protocol

    Container with FLIBE salt supplied from Oak Ridge National Laboratory was gradually heated to the operating temperature of 450 – 600°C, solidified molten salt in the container was gradually melted (melting point of FLIBE is approx. 454°C), then a part of melted material was transfused to the special ampoule, for further neutronic performance measurements in experimental reactor LR-0.
    Then further samples of the melted FLIBE salts were separated for subsequent experiments.

    FLIBE – Irradiation Experiment