Persistent Link:
http://hdl.handle.net/10150/278144
Title:
Reactivity feedback mechanisms in aqueous fissile solutions
Author:
Kornreich, Drew Edward, 1968-
Issue Date:
1992
Publisher:
The University of Arizona.
Rights:
Copyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.
Abstract:
Solutions of fissile materials are often encountered during spent-fuel reprocessing. In order to estimate the hazards from accidental criticalities in these solutions, models have been developed to understand better the dynamics involved. Accurate representation of reactivity feedback mechanisms are a crucial part of such models. Reactivity feedback from uniform volumetric solution expansion is studied. For faster transients, density redistribution may also occur due to a variation of nuclear energy as a function of position in the assembly. Neutronic spectral temperature reactivity effects are studied using two methods: cross section corrections via a Maxwellian flux weighting and creation of temperature dependent cross sections from ENDF/B-VI data. The volumetric and temperature reactivity feedback coefficients are determined for the CRAC, KEWB-5, SILENE, and SHEBA solution assemblies. Spectral temperature coefficients are also calculated for poisoned, unpoisoned, and reflected plutonium solutions. Feedback coefficients are seen to be functions of geometry and isotopic contents of the assemblies. Results for plutonium solutions agree with British calculations reported in 1991, confirming the possibility of autocatalytic excursions in large, dilute solutions.
Type:
text; Thesis-Reproduction (electronic)
Keywords:
Engineering, Nuclear.
Degree Name:
M.S.
Degree Level:
masters
Degree Program:
Graduate College
Degree Grantor:
University of Arizona
Advisor:
Hetrick, David L.

Full metadata record

DC FieldValue Language
dc.language.isoen_USen_US
dc.titleReactivity feedback mechanisms in aqueous fissile solutionsen_US
dc.creatorKornreich, Drew Edward, 1968-en_US
dc.contributor.authorKornreich, Drew Edward, 1968-en_US
dc.date.issued1992en_US
dc.publisherThe University of Arizona.en_US
dc.rightsCopyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.en_US
dc.description.abstractSolutions of fissile materials are often encountered during spent-fuel reprocessing. In order to estimate the hazards from accidental criticalities in these solutions, models have been developed to understand better the dynamics involved. Accurate representation of reactivity feedback mechanisms are a crucial part of such models. Reactivity feedback from uniform volumetric solution expansion is studied. For faster transients, density redistribution may also occur due to a variation of nuclear energy as a function of position in the assembly. Neutronic spectral temperature reactivity effects are studied using two methods: cross section corrections via a Maxwellian flux weighting and creation of temperature dependent cross sections from ENDF/B-VI data. The volumetric and temperature reactivity feedback coefficients are determined for the CRAC, KEWB-5, SILENE, and SHEBA solution assemblies. Spectral temperature coefficients are also calculated for poisoned, unpoisoned, and reflected plutonium solutions. Feedback coefficients are seen to be functions of geometry and isotopic contents of the assemblies. Results for plutonium solutions agree with British calculations reported in 1991, confirming the possibility of autocatalytic excursions in large, dilute solutions.en_US
dc.typetexten_US
dc.typeThesis-Reproduction (electronic)en_US
dc.subjectEngineering, Nuclear.en_US
thesis.degree.nameM.S.en_US
thesis.degree.levelmastersen_US
thesis.degree.disciplineGraduate Collegeen_US
thesis.degree.grantorUniversity of Arizonaen_US
dc.contributor.advisorHetrick, David L.en_US
dc.identifier.proquest1349111en_US
dc.identifier.bibrecord.b27623774en_US
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