GNSR: a new Monte Carlo code to calculate response functions of gas-filled neutron detectors

A. Casnati; M. Weyrauch; P. Schillebeeckx

doi:10.1117/12.267948

27 February 1997 GNSR: a new Monte Carlo code to calculate response functions of gas-filled neutron detectors

A. Casnati, M. Weyrauch, P. Schillebeeckx

Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267948
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece

Abstract

The capabilities of a program named GNSR which is designed to calculate response functions and efficiencies of various gas-filled neutron detectors, are described. Included are recoil detectors filled with H₂. ³He, ⁴He, and mixtures with commonly used quenching gases. A cylindrical detector geometry is assumed. The program calculates the detector response in various neutron beam configurations: point source, isotropic source, parallel beam, extended cylindrical source, and a plane rectangular localized source. The reliability of the code was tested with measurements in various quasi-monoenergetic neutron beams as also reported.

Citation Download Citation

A. Casnati, M. Weyrauch, and P. Schillebeeckx "GNSR: a new Monte Carlo code to calculate response functions of gas-filled neutron detectors", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); https://doi.org/10.1117/12.267948

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