Abstract
It is shown that fuel elements consisting of a fissioning material can be simulated from the standpoint of the influence on the characteristics of the neutron field in the experimental channel of a pulsed graphite reactor by models fabricated from paraffin mixed with boric acid. It is suggested that a method be developed for monitoring the movement of the melt in the experimental channel of a pulsed graphite reactor on the basis of signals from small neutron detectors. It is suggested that the model components be melted in a pulsed graphite reactor by radiation heating by neutrons. In the future the method should be refined in experiments with actual assemblies.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
REFERENCES
I. V. Kurchatov, S. M. Feinberg, N. A. Dollezhal', et al., “Pulsed graphite reactor IGR,” At. Énerg., 17, No. 6, 463–474 (1964).
N. V. Gorin, Ya. Z. Kandiev, A. I. Ul'yanov, et al., “Measurement of the temperature of radiation heating of the structural materials by radiation of a pulsed graphite reactor,” ibid., 90, No. 1, 17–21 (2001).
M. A. Arnautova, Ya. Z. Kandiev, B. E. Lukhminsky, and G. N. Malishkin, “Monte Carlo simulation in nuclear geophysics. Comparison of the PRIZMA Monte Carlo program and benchmark experiments,” Nucl. Geophys., 7, No. 3, 407–418 (1993).
“Calculations of certain experiments on uranium-235 and uranium-238 systems with BAS spectral neutron constants,” in: Neutron Physics (1984), Vol. 2, pp. 119–123.
Oak Ridge National Laboratory. RSIC Computer Code Collection, MCNP-4A. Monte Carlo N-Particle Transport Code System, contributed by Los Alamos National Laboratory, Los Alamos, New Mexico.
A. P. Vasil'ev, N. V. Gorin, Ya. Z. Kandiev, et al., “Verification of methods for calculating the characteristics of a pulsed graphite reactor,” At. Énerg., 80, No. 3, 150–153 (1996).
A. P. Vasil'ev, N. P. Gorin, Ya. Z. Kandiev, et al., “Investigation of a three-dimensional neutron field in the core of a pulsed graphite reactor,” ibid., 82, No. 6, 407–413 (1997).
N. V. Gorin, Ya. Z. Kandiev, R. M. Kozybaev, et al., “Bleaching of uranium- graphite fuel in a pulsed graphite reactor,” ibid., 85, No. 5, 419–422 (1998).
N. V. Gorin, Ya. Z. Kandiev, R. M. Kozybaev, et al., “Investigation of the neutron field in the central channel of a pulsed graphite reactor with motion of the neutron absorber,” ibid., 85, No. 6, 474–476 (1998).
N. V. Gorin, Ya. Z. Kandiev, and Yu. M. Kaz'min, “PRIZMA D computational investigation of physical processes in a pulsed graphite reactor,” ibid., 88, No. 2, 83–88 (2000).
N. V. Gorin, Ya. Z. Kandiev, and V. I. Litvin, “Computational-experimental investigation of the special features of the neutron spectrum of a pulsed graphite reactor,” ibid., 89, No. 3, 233–237 (2000).
N. V. Gorin, Ya. Z. Kandiev, E. A. Kashaeva, et al., “Special features of the thermal-neutron field in the experimental channel of a pulsed graphite reactor,” ibid., 90, No. 4, 251–256 (2001).
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Gorin, N.V., Kandiev, Y.Z., Shcherbina, A.N. et al. Monitoring of the Movement of a Melt of Fissioning Material in the Experimental Channel of a Pulsed Graphite Reactor IGR Using Small Neutron Detectors. Atomic Energy 92, 239–245 (2002). https://doi.org/10.1023/A:1016046030363
Issue Date:
DOI: https://doi.org/10.1023/A:1016046030363