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dc.contributor.authorMeagher, Paul Christopheren_US
dc.contributor.authorLanning, David D.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-16T23:36:09Z
dc.date.available2014-09-16T23:36:09Z
dc.date.issued1976en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89730
dc.description"September 1976."en_US
dc.descriptionAlso issued as a Ph. D. thesis by the first author and supervised by the second author, MIT Dept. of Nuclear Engineering, 1977en_US
dc.descriptionIncludes bibliographical references (pages 94-95)en_US
dc.description.abstractDesign analysis studies have been made for various in-core irradiation facility designs which are presently used, or proposed for future use in the MITR-II. The information obtained includes reactivity effects, core flux and power distributions, and estimates of the safety limits and limiting conditions for operation. A finite-difference, diffusion theory computer code was employed in two and three dimensions, and with three and fifteen group energy schemes. The facilities investigated include the single-element molybdenum sample holder, a proposed double-element irradiation facility and a proposed central irradiation facility design encompassing most of the area of the three central core positions. In addition, a comparison of the effects of various absorber materials has been made for a core configuration which includes three solid dummies. Flux levels in the molybdenum holder facility and in the beam ports were calculated for both three and five dummy cores. Flooding the sample tube in these cases was found to increase the safety and operating limits, but not to unacceptable levels for an 8 inch blade height. For the five dummy case, the operating limit in the C-ring was predicted to reach its maximum allowed value at a blade bank height of 13.6 inches. The reactivity effect of flooding was calculated to be 0.19%AK for the five dummy case, in direct agreement with the measured value. Flooging the large sample channel in the double element facility was found to increase the reactivity by 1.5 6%AK ff and also to cause an unacceptable power-peaking. The proposed central irradiation facility is a thermal flux-trap which could produce thermal flux values of up to 2.0 x 1014 n/cm 2 sec. Computer estimates show that flooding this facility's central sample tube would increase this value to 2.5 x 1014 n/cm2 sec, without resulting in an unacceptable power peak.en_US
dc.format.extent197 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976]en_US
dc.relation.ispartofseriesMITNE ; no. 190en_US
dc.subject.lccTK9008.M41 N96 no.190en_US
dc.subject.lcshMassachusetts Institute of Technology. Research Reactoren_US
dc.subject.lcshNuclear fuel elementsen_US
dc.subject.lcshIrradiationen_US
dc.titleDesign of central irradiation facilities for the MITR-II research reactoren_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857230553en_US


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