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Simulating safety analytics INLs premier reactor safety and systems analysis tool will soon be MOOSE-based. The Reactor Excursion and Leak Analysis Programs newest version RELAP-7 will include several improvements including enhanced models improved numerical approximations and the ability to couple with multidimensional core simulators being developed in other DOE research programs. The RAVEN software tool will provide a RELAP-7 user interface and use RELAP-7 to perform Risk Informed Safety Characterization. Broadening approach Probabilistic risk assessment fuels with enhanced accident tolerance and instrumentation improvements all relate to broader questions of light water reactor safety. Yet specialized research programs like this can become isolated. Thats why INL is taking a more systems-based approach to reactor safety methodology. A new program at the lab will integrate these areas to enable the advances that result from broader collaborations. Producing safer waste forms The DOE and INL are studying advanced nuclear waste forms that may perform better than the global standard. For example glass waste forms isolate radioactive materials very effectively but their effectiveness is limited by the temperatures that can be achieved in conventional melters. INL has developed a more efficient approach for making advanced glass-ceramic waste forms right and successfully demonstrated that Since this publication first described these tools last year numerous additions have been added to the herd. PEREGRINE is an offshoot of BISON designed specifically to model light water reactor fuel performance. It incorporates proprietary Electric Power Research Institute EPRI models and supports DOEs Consortium for Advanced Simulation of Light Water Reactors. Modeling multitudes Other applications developed under the MOOSE framework include the Grizzly code for materials aging which is being developed jointly with Oak Ridge National Lab and EPRI. The code models degradation in reactor pressure vessels and other components which can build up after years of use. Data from Grizzly could help nuclear power plant owners understand the sources of change in safety margin and inform decisions on component replacement and repair. The RattleSnake code could be used to design and study new nuclear fuels with enhanced accident tolerance. The code models the behavior of neutrons in nuclear fuel and reactor cores. A better understanding of this neutron transport physics can sharpen understanding of factors that impact energy generation and material damage. 25 approach last year. The labs state-of-the- art Cold Crucible Induction Melter has unique features that are well suited for producing advanced glass-ceramic high- level waste forms such as the ability to operate at higher temperatures than conventional melters.