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Thermal neutron flux distribution in the ET R R-1 reactor core as experimentally measured and theoretically calculated by the code triton

Abstract

Thermal neutron flux distributions that were measured earlier at the ET-R R-1 reactor are compared with those calculated by the three dimensional diffusion code Triton. This comparison was made for the horizontal and vertical flux distributions. The horizontal thermal flux distributions considered in this comparison were along the core diagonals at two planes of different heights from core bottom, where one at a level passing through the control rod at core center and the other at a level below this control rod. In the meantime all the control rods were taken into consideration. The effect of the existence of a water cavity inside the core as well as the influence of the control rods on the thermal flux are illustrated in this work. The vertical thermal flux distributions considered in the comparison were at two positions in core namely; one along the core height the horizontal reactor power distribution along the core height and the horizontal reactor power distribution along the core diagonal as calculated by the code Triton are also given this work. 8 figs., 1 tab.
Authors:
Imam, M [1] 
  1. National center for nuclear safety and radiation control, atomic energy authority, Cairo, (Egypt)
Publication Date:
Oct 01, 1995
Product Type:
Miscellaneous
Report Number:
INIS-EG-001; CONF-9411323-
Reference Number:
SCA: 220100; PA: AIX-28:030873; EDB-97:054526; SN: 97001765379
Resource Relation:
Conference: 2. Arab conference on the peaceful uses of atomic energy, Cairo (Egypt), 5-9 Nov 1994; Other Information: PBD: Oct 1995; Related Information: Is Part Of Proceedings of the second Arab conference on the peaceful uses of atomic energy. Part II: A and B; Barakat, M.F.; El-Mashri, S.M. [eds.]; PB: 1199 p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; THERMAL NEUTRONS; ETRR-1 REACTOR; CALCULATION METHODS; CONTROL ELEMENTS; DISTRIBUTION; NEUTRON FLUX; NUCLEAR REACTIONS; REACTOR CORES; THEORETICAL DATA
OSTI ID:
456057
Research Organizations:
Atomic Energy Authority, Cairo (Egypt); Arab Atomic Energy Agency (AAEA), Tunis (Tunisia); Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo (Egypt)
Country of Origin:
Egypt
Language:
English
Other Identifying Numbers:
Other: ON: DE97620040; ISBN 9973-9927-3-3; TRN: EG9601637030873
Availability:
INIS; OSTI as DE97620040
Submitting Site:
INIS
Size:
pp. 91
Announcement Date:
Jan 21, 2004

Citation Formats

Imam, M. Thermal neutron flux distribution in the ET R R-1 reactor core as experimentally measured and theoretically calculated by the code triton. Egypt: N. p., 1995. Web.
Imam, M. Thermal neutron flux distribution in the ET R R-1 reactor core as experimentally measured and theoretically calculated by the code triton. Egypt.
Imam, M. 1995. "Thermal neutron flux distribution in the ET R R-1 reactor core as experimentally measured and theoretically calculated by the code triton." Egypt.
@misc{etde_456057,
title = {Thermal neutron flux distribution in the ET R R-1 reactor core as experimentally measured and theoretically calculated by the code triton}
author = {Imam, M}
abstractNote = {Thermal neutron flux distributions that were measured earlier at the ET-R R-1 reactor are compared with those calculated by the three dimensional diffusion code Triton. This comparison was made for the horizontal and vertical flux distributions. The horizontal thermal flux distributions considered in this comparison were along the core diagonals at two planes of different heights from core bottom, where one at a level passing through the control rod at core center and the other at a level below this control rod. In the meantime all the control rods were taken into consideration. The effect of the existence of a water cavity inside the core as well as the influence of the control rods on the thermal flux are illustrated in this work. The vertical thermal flux distributions considered in the comparison were at two positions in core namely; one along the core height the horizontal reactor power distribution along the core height and the horizontal reactor power distribution along the core diagonal as calculated by the code Triton are also given this work. 8 figs., 1 tab.}
place = {Egypt}
year = {1995}
month = {Oct}
}