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A standard graphite block

Abstract

A graphite block was calibrated for the thermal neutron flux of the Ra-Be source using indium foils as detectors. Experimental values of the thermal neutron flux along the central vertical axis of the system were corrected for the self-shielding effect and depression of flux in the detector. The experimental values obtained were compared with the values calculated on the basis of solving the conservation neutron equation by the continuous slowing-down theory. In this theoretical calculation of the flux the Ra-Be source was divided into three resonance energy regions. The measurement of the thermal neutron diffusion length in the standard graphite block is described. The measurements were performed in the thermal neutron region of the system. The experimental results were interpreted by the diffusion theory for point thermal neutron source in the finite system. The thermal neutron diffusion length was calculated to be L= 50.9 {+-}3.1 cm for the following graphite characteristics: density = 1.7 g/cm{sup 3}; boron content = 0.1 ppm; absorption cross section = 3.7 mb.
Authors:
Ivkovic, M; Zdravkovic, Z; Sotic, O [1] 
  1. Department of Reactor Physics and Dynamics, Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)
Publication Date:
Apr 15, 1966
Product Type:
Miscellaneous
Report Number:
INIS-RS-1289
Resource Relation:
Other Information: 8 refs. 6 figs., 4 tabs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; DIFFUSION LENGTH; EXPERIMENTAL DATA; FISSION FOIL DETECTORS; GRAPHITE; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON SOURCES; SELF-SHIELDING; THERMAL NEUTRONS
OSTI ID:
21021491
Country of Origin:
Serbia
Language:
English
Other Identifying Numbers:
TRN: RS08RB099043319
Availability:
Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca
Submitting Site:
INIS
Size:
v. 17(2) 16 pages
Announcement Date:
May 23, 2008

Citation Formats

Ivkovic, M, Zdravkovic, Z, and Sotic, O. A standard graphite block. Serbia: N. p., 1966. Web.
Ivkovic, M, Zdravkovic, Z, & Sotic, O. A standard graphite block. Serbia.
Ivkovic, M, Zdravkovic, Z, and Sotic, O. 1966. "A standard graphite block." Serbia.
@misc{etde_21021491,
title = {A standard graphite block}
author = {Ivkovic, M, Zdravkovic, Z, and Sotic, O}
abstractNote = {A graphite block was calibrated for the thermal neutron flux of the Ra-Be source using indium foils as detectors. Experimental values of the thermal neutron flux along the central vertical axis of the system were corrected for the self-shielding effect and depression of flux in the detector. The experimental values obtained were compared with the values calculated on the basis of solving the conservation neutron equation by the continuous slowing-down theory. In this theoretical calculation of the flux the Ra-Be source was divided into three resonance energy regions. The measurement of the thermal neutron diffusion length in the standard graphite block is described. The measurements were performed in the thermal neutron region of the system. The experimental results were interpreted by the diffusion theory for point thermal neutron source in the finite system. The thermal neutron diffusion length was calculated to be L= 50.9 {+-}3.1 cm for the following graphite characteristics: density = 1.7 g/cm{sup 3}; boron content = 0.1 ppm; absorption cross section = 3.7 mb.}
place = {Serbia}
year = {1966}
month = {Apr}
}