Center for Neutron Research Project. Status Report

摘要

The Center for Neutron Research (CNR) will provide the world's best facilities for the study of neutron scattering. The CNR will contain a very high flux reactor that will achieve an extremely high power density (between 4 and 8 MW/L). The reactor is to be fueled with uranium silicide and cooled, moderated, and reflected by D sub 2 O. Initial reactor physics calculations indicate that a power level of 270 MW with a reactor core volume of 35 L will achieve a peak thermal flux in the reflector of 10 sup 20 neutrons x m sup -2 x s sup -1 . The reactor fuel will be contained in thin (1.3-mm) plates, similar to those employed in the very successful High-Flux Isotope Reactor, and will be graded in the axial and radial directions. Coolant velocity is to be 27 m/s, and core inlet pressure is to be 5.6 MPa. Maximum fuel centerline temperature will be approx.350 deg C. Initial thermal-hydraulic studies indicate that some method of preventing the formation of aluminum oxide on the fuel clad is required if the highest performance is to be achieved. Tests to confirm these calculations are planned. One of the experimental facilities is to be a cold (10-MeV) neutron source. Calculations to determine the size of the source have been initiated, but additional cross-section data are needed. An abbreviated version of a tentative program plan for fiscal year 1987 and beyond is described. Total program expenditures are expected to be $40 million over 5 years. (ERA citation 12:000471)