Publication Laka-library:
A Subcritical Experiment for an Aqueos Homogeneous Suspension Reactor (1963)
| Author | J.A.H.Kersten, J.J.Went |
| Date | September 1963 |
| Classification | 1.01.8.41/14 (KEMA ARNHEM - KSTR (KEMA SUSPENSIE TEST REACTOR)) |
| Front | 
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From the publication:
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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