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Diversification and the common ground
Craig Piercycpiercy@ans.org
Who would have thought, just a few years ago, that we would see so many long-standing barriers to new nuclear development falling like dominoes? Public opinion, policy, regulatory reform, finance and investment, design maturity, nuclear fuel enrichment, and fuel fabrication capacity have all advanced with remarkable speed in the United States.
Conventional wisdom holds that the most effective way to scale up the nuclear supply chain is to do so strategically, matching investments to the needs of reactor developers.
H. Kumawat
Nuclear Science and Engineering | Volume 199 | Number 4 | April 2025 | Pages 550-556
Review Article | doi.org/10.1080/00295639.2024.2380636
Articles are hosted by Taylor and Francis Online.
The Monte Carlo Nucleon Transport (MONC) code for nucleon transport is extended for below 20-MeV proton transport using the ENDF and EXFOR databases. It is used to simulate the p + 7Li reaction up to 20-MeV proton energies, with the produced neutron spectra reported here. The simulated results are compared with the calculated values from other available codes like PINO, EPEN, and SimLiT, as well as experimental data. The spectra reported here can be used to get the neutron cross section for the quasi-monoenergetic neutron reaction and will help to subtract the low-energy contribution. The primary neutron spectra and its transport are useful, as this reaction has the potential for accelerator-based boron neutron capture therapy. The backing materials are used to fully stop the proton beam, hence the contributions of the neutrons from backing materials are estimated. It is found that tantalum is a good backing material below ~8 MeV and that carbon is better at higher energies.