Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT CASL-U-2017-1280-000 v Consortium for Advanced Simulation of LWRs Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT CASL-U-2017-1280-000 1 Consortium for Advanced Simulation of LWRs Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT Consortium for Advanced Simulation of LWRs 2 CASL-U-2017-1280-000 2. ACCURACY GOALS Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT CASL-U-2017-1280-000 5 Consortium for Advanced Simulation of LWRs Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT Consortium for Advanced Simulation of LWRs 10 CASL-U-2017-1280-000 Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT CASL-U-2017-1280-000 13 Consortium for Advanced Simulation of LWRs Development of the v4.2m5 and v5.0m0 MG Cross Section Libraries for MPACT

No abstract

No abstract

Engineering demonstration reactors are nuclear reactors built to establish proof of concept for technology options that have never been built. Examples of engineering demonstration reactors include Peach Bottom 1 for high temperature gas-cooled reactors (HTGRs) and Experimental Breeder Reactor II (EBR-II) for sodium-cooled fast reactors. Engineering demonstrations have historically played a vital role in advancing the technology readiness level of reactor technologies. This paper details a preconceptual design for a fluoride salt-cooled engineering demonstration reactor. The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) is a concept for a salt-cooled reactor with 100 megawatts of thermal output (MWt). It would use tristructural-isotropic (TRISO) particle fuel within prismatic graphite blocks. FLiBe (2 7 LiF-BeF 2) is the reference primary coolant. The FHR DR is designed to be small, simple, and affordable. Core design characteristics, fuel cycle performance, and safety analysis of the FHR DR preconcept have been evaluated. The FHR DR core design features a negative or negligible void coefficient throughout a reactor operating cycle. Both single-batch (cartridge) and multiple-batch fuel cycles can be demonstrated in the FHR DR. The single-batch cycle length of the FHR DR core is estimated at between 12-18 months, assuming the successful qualification of composite carbon

No abstract