Uranium-233 fission detectors for neutron flux measurement in reactors

1 June 1996

journal article
research article
Published by AIP Publishing in Review of Scientific Instruments

Vol. 67 (6) , 2197-2201
https://doi.org/10.1063/1.1147036

Abstract

Fission counters have been developed indigenously, using ²³³U as a sensing material for reactor startup applications. The first model has a counting sensitivity of 0.003 cps/nv in the pulse mode, 1×10⁻¹⁵ A/nv in the dc mode, and 6.4×10⁻²⁹ A² Hz/nv in the Campbell mode. A more sensitive counter with about 75 mg of ²³³U showed an average sensitivity of 0.02 cps/nv. A proposal for ²³³U in‐core miniature dc fission chambers is discussed. A design for high sensitivity (0.5 cps/nv) U‐233 pulse counter with transmission line‐type readout is also proposed.

Keywords

This publication has 2 references indexed in Scilit:

Ultrahigh-Sensitivity Fission Counter with Transmission Line Electrode Configuration
IEEE Transactions on Nuclear Science, 1983
Campbell Theorem - System Concepts and Results
IEEE Transactions on Nuclear Science, 1967