A preliminary kinetic study of a sodium-beryllium-uranium circulating fuel reactor

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dc.contributor.authorThompson, JJen_AU
dc.date.accessioned2007-11-22T04:10:21Zen_AU
dc.date.accessioned2010-04-30T04:31:33Zen_AU
dc.date.available2007-11-22T04:10:21Zen_AU
dc.date.available2010-04-30T04:31:33Zen_AU
dc.date.issued1956-11en_AU
dc.description.abstractThe initial response of a 1:100:2000 U-Na-Be Reactor, operating at a power density of 1200 cals/cc/sec, to a sudden change in the fuel concentration in the circulating carrier, has been calculated on the assumption of constant inlet temperature and no delayed neutrons. The result confirmed that the peak temperatures and power can be accurately calculated by ignoring the moderator temperature rise, and that the approach to the new steady state values is given by the solution of the linearized equations. The slow moderator heating implies that the departure from the steady state are still large when the carrier and fuel have completed one transit of the external circuit. The assumption that the mean temperature is the arithmetic peak but overestimates the maximum power and outlet temperature excursions by 15 1/2% and 7% respectively.en_AU
dc.identifier.citationThompson, J. J. (1956). A preliminary kinetic study of a sodium-beryllium-uranium circulating fuel reactor (AAEC/E.14). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc288en_AU
dc.identifier.otherAAEC-E-14en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/88en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectKineticsen_AU
dc.subjectSodiumen_AU
dc.subjectBerylliumen_AU
dc.subjectUraniumen_AU
dc.subjectNuclear fuelsen_AU
dc.titleA preliminary kinetic study of a sodium-beryllium-uranium circulating fuel reactoren_AU
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