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        The U.S. Department of Energy (DoE) is launching a new project referred to as the Versatile Fast Neutron Source project. This new reactor will be used to provide fast neutron testing capability to assist in the development of advanced nuclear reactor technology. The project is also called the Versatile Test Reactor (VTR).
        Sources of fast neutrons for nuclear technology testing are only operating at a few places in the world and the U.S. has not had one for twenty years. This has prevented the U.S. from using accelerated irradiating testing on new reactor technology, fuels and related materials unless U.S. companies were willing to appeal to China or Russia to help with such testing.
        The Nuclear Energy Innovation Capabilities Act was implemented last September. It directs the DoE to develop a reactor-based fast neutron source for testing advanced reactor components and fuels. In addition, it also directs the DoE to begin a program to use high-performance computer modeling and simulation techniques to assist in the development of new reactor technologies.
       Rick Perry is the U.S. Secretary of Energy. He introduced the VTR program February 28th at a joint press conference with the Executive Director of the International Atomic Energy Agency. Perry said, “This cutting-edge Advanced Reactor will give American companies the ability they currently lack to conduct advanced technology and fuels tests without having to go to our competitors in Russia and China.”
       The DoE says that the VTR will remove a “research gap” and “drastically” reduce the time required to test, develop and qualify advanced reactor technologies. It will also be critical in the creation of new fuels, materials, sensors and instrumentation. Ed McGinnis is the Principle Deputy Assistant Secretary of the DoE Office of Nuclear Energy. He said, “Having this domestic capability is critical to our national security and our ability to re-establish ourselves as a global leader in advanced reactor technologies.” The DoE Idaho National Laboratory has already selected GE Hitachi Nuclear Energy’ (GEH) PRISM technology to support the VTR project.
        PRISM stands for Power Reactor Innovative Small Module. The PRISM is a GEH Generation IV reactor which GEH hopes will help close the nuclear fuel cycle in the U.S. PRISM is also part of the GEH proposal for its Advanced Recycling Center proposal which was delivered to the U.S. Congress as a way to deal with nuclear waste. PRISM is a sodium-cooled fast breeder reactor based on a scaled up Experimental Breeder Reactor II design. It is a commercial version of the Integral Fast Reactor that was developed by Argonne National Laboratory between 1984 and 1994.
      The PRISM design is intended to be fabricated in factories to lower the cost and standardize the construction. It has passive cooling systems which will always operate and automatically lower the core temperature in case the reactor gets too hot.
        GEH has been subcontracted to collaborate with the Bechtel Corporation to develop the design and cost estimates for the construction of an PRISM integral sodium-cooled fast reactor. On March 1st, DoE said that it will begin conceptual design of the reactor which may be completed as early as 2026.