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A Subcritical Experiment for an Aqueos Homogeneous Suspension Reactor (1963)

Auteur	J.A.H.Kersten, J.J.Went
Datum	september 1963
Classificatie	1.01.8.41/14 (KEMA - KSTR)
Voorkant

A SUBxCRITICAL EXPERIMENT FOR AN AQUEOUS HOMOGENEOUS 
SUSPENSION REACTOR

J.A.H. KERSTEN AND J.J. WENT
N.V.KEMA, ARNHEM, NETHIDUANDS

Abstract

A SUBCRITICAL EXPERIMENT FOR AN AQUEOUS HOMOGENEOUS 
SUSPENSION REACTOR. For aqueous homogeneous circulating fuel reactors, it is 
not essential to construct exponential or critical experiments for the determination 
of the standard physics information, as required for the criticality conditions and 
the optimization of heterogeneous reactors. In a homogeneous liquid fuel reactor 
the concentration of the fuel as well as the enrichment of the fissile component can 
be adjusted to the experimentally desired values, even after the construction of the 
reactor installation, so that simple reactor physical calculations ate sufficiently 
accurate.
However, in circulating fuel reactors a subcritical or near critical experiment 
instead of an exponential or critical experiment has been proven to be of great value. 
In such a reactor it is essential to keep the concentration and concentration 
distribution of the fuel during constant operational conditions between very 
narrow limits. These requirements ate so stringent that conventional concentration 
measuring devices are far too insensitive. Only the determination of the reactivity 
near the critical point can give the desired information.
With a subcritical suspension reactor that could be operated at constant temperature 
it was also possible to measure with reactor physical methods, apart from the 
afore- mentioned suspension concentrations, other important properties of the 
reactor system.
In this paper results are given from measurements on the influence of the colloid 
chemical properties of the suspension on the noise of the neutron flux, on the recoil 
separation efficiency of fission products, and on the temperature coefficient of 
reactivity. The effective delayed neutron fraction as a function of the circulating 
velocity of the suspension and the flux distribution inside the reactor vessel are 
also determined.

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