Determination of the neutron flux density at an unknown reactor power

In the present paper, relationships are derived which by using an additional measurement enable calculation of the neutron flux density measured at an unknown low reactor power to the power of 1 MW. The measurements can be carried out with activation detectors using well-known methods, see e.g. (ASTM, 1977, 1980; Zijp, 1984). Constant neutron flux density at a power of 1 MW is assumed during the measurements and a so-called ''one-point reactor'' model is employed. (author)