Open AccessQuarterly Report, Dec. 1, 1999-Feb. 29, 2000, Novel, Integrated Reactor
Author(s) -
D.V. Paramono
Publication year - 2000
Language(s) - English
Resource type - Reports
DOI - 10.2172/762161
Subject(s) - neutron flux , fluence , fissile material , nuclear engineering , mox fuel , materials science , nitride , carbide , neutron , burnup , nuclear reactor core , nuclear physics , irradiation , physics , nanotechnology , metallurgy , engineering , uranium , layer (electronics)
The basic core design requirements were defined in the previous reporting period. During the second quarter, several series of neutronic calculations were performed. Monte Carlo BOL (Beginning-of-Life) simulations were performed to evaluate the impact of various design alternatives on key core parameters. Fuel design alternatives that were examined by these studies included: fuel form (oxide, carbide and nitride) (note that due to the AMTEC high temperature requirement, metal fuel was eliminated from further considerations); fissile fuel content, and fuel rod and lattice pitch. The key neutronic parameters that were compared include: core reactivity, neutron spectrum, fast neutron flux and projected lifetime fast fluence (E > 0.1 MeV), and material damage indicator, dpa (displacement-per-atom) and dpa rate. These analyses indicated that the fast neutron fluence will probably be the most limiting factor, with estimated fast fluence ranging between 3 x 10{sup 23} n/cm{sup 2} and up to 9 x 10{sup 23} n/cm{sup 2}, depending on the fuel characteristics. Therefore, different fuel forms were examined and the projected fast fluence and dpa compared. Using MOX fuel results in the highest fast fluence and dpa, about 10% higher than for the carbide or nitride fuel. The nitride fuel leads to the lowest dpa, for the same reactor power density, up to {approx} 4% and {approx} 7% lower than for the carbide and MOX fuel, respectively