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EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques

Abstract

The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)
Authors:
Rousseau, A; Genthon, J P [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1958
Product Type:
Technical Report
Report Number:
CEA-R-931
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BEAM HOLES; COMPARATIVE EVALUATIONS; EL-2 REACTOR; ENRICHED URANIUM; EXPERIMENTAL CHANNELS; FLUX DENSITY; FUEL CHANNELS; FUEL RODS; NEUTRON FLUX; POWER DENSITY; REACTOR CORES; REACTOR LATTICES; SPATIAL DISTRIBUTION; SPECIFICATIONS; THERMAL COLUMNS; THERMAL NEUTRONS
OSTI ID:
20900996
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR07R0931063219
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
38 pages
Announcement Date:
Aug 28, 2007

Citation Formats

Rousseau, A, and Genthon, J P. EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques. France: N. p., 1958. Web.
Rousseau, A, & Genthon, J P. EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques. France.
Rousseau, A, and Genthon, J P. 1958. "EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques." France.
@misc{etde_20900996,
title = {EL-2 reactor: Thermal neutron flux distribution; EL-2: Repartition du flux de neutrons thermiques}
author = {Rousseau, A, and Genthon, J P}
abstractNote = {The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)}
place = {France}
year = {1958}
month = {Jul}
}