The Federal Environmental, Industrial and Nuclear Supervision Service (Rostechnadzor) gave JSC SCC the license for building of the world’s first pilot demonstration power unit with a lead-cooled fast neutron reactor BREST-OD-300 which uses mixed uranium-plutonium nitride fuel and integrated design. The license was signed by Head of Rostechnadzor Aleksei Aleshin on February 10.
“First of all, I congratulate all the industry with this important event which we approached in a planned and systemic manner. The license issue means that Rostechnadzor got all necessary answers on its questions concerning building the BREST power unit. In turn, it speaks that all key results of the project will be achieved by the RTTM Complex Program as planned for 2021,” said Vyacheslav Pershukov, Head of Proryv Project and Special Representative of ROSATOM for International, Science and Technology Projects.
New federal standards and regulations, which consider features of the project, were developed during safety evaluation of the pilot demonstration power unit. They included “Requirements to Layout and Safe Operation of the Reactor, Equipment and Pipelines of Lead-Cooled Nuclear Installations” and “Requirements to Justification of Strength of the Reactor and Pipelines of Lead-Cooled Nuclear Installations”. Sixteen standards of ROSATOM, which detail requirements and consider all features of BREST-OD-300 power unit, have been put into force.
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The pilot demonstration power facility (ODEK) is being built in the territory of Siberian Chemical Combine. It will consist of a power unit with the lead-cooled reactor BREST-OD-300 and on-site closed nuclear fuel cycle which will include the reprocessing module (RM) for irradiated mixed uranium-plutonium (nitride) fuel and fabrication/re-fabrication module (FRM) for production of start-up fuel rods from brought-in materials and, later, fuel rods from reprocessed irradiated nuclear fuel. For the first time ever in the world ODEK has to demonstrate sustainable operation of the complete facility which closes nuclear fuel cycle. The on-site nuclear fuel cycle provides for testing technologies of the “short fuel cycle” within short time on one site.
