Self-powered neutron detectors (SPNDs) are widely used in reactors to monit
or neutron flux. While they have several advantages such as small size, and
relatively simple electronics required in conjunction with those usages, t
hey have some intrinsic problems of the low level of output current-a slow
response time and the rapid change of sensitivity-that make it difficult to
use for a long term. Monte Carlo simulation was used to calculate the esca
pe probability as a function of the birth position of emitted beta particle
for geometry of rhodium-based SPNDs. A simple numerical method calculated
the initial generation rate of beta particles and the change of generation
rate due to rhodium burnup. Using results of the simulation and the simple
numerical method, the burnup profile of rhodium number density and the neut
ron sensitivity were calculated as a function of burnup time in reactors. T
his method was verified by the comparison of this and other papers., and da
ta of YGN3.4 (Young Gwang Nuclear plant 3, 4) about the initial sensitivity
. In addition, for improvement of some properties of rhodium-based SPNDs, w
hich are currently used, a modified geometry is proposed. The proposed geom
etry, which is tube-type, is able to increase the initial sensitivity due t
o increase of the escape probability. The escape probability was calculated
by changing the thickness of the insulator and compared solid-type with tu
be-type about each insulator thickness. The method used here can be applied
to the analysis and design of other types of SPNDs.