Page 1 Page 2 Page 3 Page 4 Page 5 Page 6 Page 7 Page 8 Page 9 Page 10 Page 11 Page 12 Page 13 Page 14 Page 15 Page 16 Page 17 Page 18 Page 19 Page 20 Page 21 Page 22 Page 23 Page 24 Page 25 Page 26 Page 27 Page 28 Page 29 Page 30 Page 31 Page 32 Page 33 Page 34 Page 35 Page 36 Page 37 Page 38 Page 39 Page 40Technology Transfer 26 The ITER (“the way” in Latin) project intends to advance fusion science to maintain fusion for long periods of time to supply fusion power plants.This international agreement is in concert with the following members of the ITER Project: China, the European Union, India, Japan, Korea, Russia and the United States to collectively conduct fusion research.The U.S. government’s oversight organization for this project is the Department of Energy’s Office of Fusion Energy Sciences. The purpose of this agreement is to conduct the benchmark study of the MAGARC code as a supplementary activity to the ITER contract ‘Electromagnetic Assessments of ITER Magnets in Safety-related Fault Conditions’ which is currently being conducted in the UK.The goals of this agreement are 1) to benchmark and to validate the MAGARC code that performed previous analysis for ITER coils fault events; 2) to collaborate with CCFE on benchmarking and validating the analysis package developed for the assessment of ITER magnets arcing safety. Public benefit:The ITER International Agreement is a project between seven entities (U.S., EU, Japan, Russia, India, Korea and China) to build a 500 MWt fusion tokamak reactor, designated as ITER, at Cadarache, France.The INL Fusion Safety Program (FSP) has been OFES’s lead laboratory in magnetic fusion energy (MFE) safety for more than 35 years. FSP has supplied many of the safety analysis codes used to license ITER in France. For ITER Agreement 2, INL is the lead laboratory for magnetic fusion safety in the U.S., as designated by the U.S. DOE in 1979.The INL Fusion Safety Program (FSP) is the group at INL developing fusion safety analysis tools, performing fusion reactor safety analyses and performing safety related materials experiments. Computer codes developed by the INL FSP have been used, and are still being used, to license the ITER device, in particular the code calledTritium Migration Analysis Program (TMAP) and the MELCOR computer code modified for fusion applications.The principal investigator (PI) involved in this agreement developed these computer codes, and has been involved with the safety assessment of the ITER reactor through its various design phases from 1994 to present.This PI serves on the ITERTest Blanket Module (TBM) Program Committee as the U.S. representative safety expert.This agreement supports the ITER IO in safety analyses required to design, license and operate the ITER nuclear facility. Nuclear Science & Technology The mission of the Department of Energy, Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource capable of meeting the nation’s energy, environmental and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development and demonstration (RD&D). The CRADAs listed below support the DOE-NE voucher program under the GAIN initiative and are intended to help accelerate the commercialization of innovation that supports advanced nuclear technology. Creare, LLC: the participant aims to develop and advance a continuous casting technique that will be applicable to metallic nuclear fuels, such as uranium-10wt% zirconium (U-10Zr). As part of this system, the fuel alloy will remain molten in a crucible for up to eight hours. Due to the reactive nature of U-10Zr, many of the standard crucible materials (Al2O3, MgO, etc.) will react with the melt, contaminating the fuel alloy and causing a crucible failure in the equipment. Developing a successful casting system requires an inert material identified and tested under prototypic conditions. CeramicTubular Products, LLC: the participant is developing an accident tolerant fuel cladding for commercial pressurized water reactor (PWR) fuel based on a multilayered silicon carbide (SiC) material, known asTRIPLEX cladding, which offers major improvements in the safety of LWRs during severe accident conditions.To improve the economics and the corrosion resistance of this clad under normal operating conditions, participant has refined the technology to include advanced fabrication processes, lower cost SiC fibers, and an improved corrosion resistant surface coating. Before proceeding to full commercial application of this improved product, an irradiation test of the product with these new features under typical PWR chemistry and radiation conditions is needed.The MIT Nuclear Reactor Lab will perform this irradiation test in the MIT reactor clad test loop. INL will provide project oversight. In FY 2016, INL entered into two separate SPP Agreements with ITER that support the International Fusion Energy Organization Agreement.The significance of this collaboration and implementation is identified in the contractor’s M&O contract with the Department of Energy.