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dc.rights.licenseRestricted to current Rensselaer faculty, staff and students. Access inquiries may be directed to the Rensselaer Libraries.
dc.contributorBecker, Martin, 1940-
dc.contributorBlock, Robert C., 1929-
dc.contributorFrancis, Norman C., 1931-
dc.contributorWhite, Frederick Andrew, 1918-
dc.contributor.authorHarris, Donald R.
dc.date.accessioned2021-11-03T08:44:53Z
dc.date.available2021-11-03T08:44:53Z
dc.date.created2017-02-23T15:29:14Z
dc.date.issued1976-12
dc.identifier.urihttps://hdl.handle.net/20.500.13015/1879
dc.descriptionDecember 1976
dc.descriptionSchool of Engineering
dc.description.abstractPath B analyses are carried out both by direct methods and by a nonlinear perturbation technique. Direct Path B investigations are carried out by the batch depletion code FASTCELL, the core analysis code FASTCORE, and the reactor cost code COSTR. FASTCELL depletes a cell using methods comparable to industry cell codes except for a few group treatment of cell flux distribution. FASTCORE is used here with the Haling strategy of fixed power sharing among batches in the core. COSTR computes costs using components and techniques as in industry costing codes except that COSTR uses fixed payment schedules.
dc.description.abstractPath A sensitivity analyses are carried out for the pressurized water reactor at middle-of-exposure. Resonance group cross sections are found to be sensitive to resonance parameters and, to a lesser extent, to cross section formalisms. Thermal group cross sections are found to be markedly sensitive to data at Maxwellian energies.
dc.description.abstractSensitivity analyses are carried out for a pressurized water reactor. In direct Path B analysis each few group nuclear parameter is changed, and initial enrichment is also changed so as to keep the end of-cycle core multiplication factor unchanged, i.e., to preserve cycle time at the demand power. Sensitivities of fuel cycle cost are determined with respect to some ninety nuclear parameters both for a normal fuel cycle and for a throw-away fuel cycle. Particularly large dollar implications are found for thermal and resonance range cross sections in fissile and fertile materials. Sensitivities constrained by adjustment of fission neutron yield so as to preserve agreement with zero exposure integral data also are computed. It is found that some sensitivities are greatly reduced by this constraint, but others, notably for fissile and fertile reactions, are aggravated.
dc.description.abstractPath A analysis methods are developed for the thermal and resonance ranges. A thermal range perturbation method is developed for which required adjoints are computed by forward calculations. This method is implemented by code FASTT. Resonance region sensitivities are computed by the slowing-down code FASTR. Resonance cross sections are computed by code MLEVL incorporating a novel multilevel formalism that is Doppler broadened by the w and x functions. An improved w-x Doppler broadening technique is developed. FASTR and MLEVL determine sensitivities of resonance absorption to resonance parameters and formalisms.
dc.description.abstractA sensitivity analysis system is developed for assessing the economic implications of uncertainties in nuclear data and related computational methods for light water power reactors. Results of the sensitivity analysis indicate directions for worthwhile improvement in data and methods. Benefits from improvements in data and methods are related to reduction of margins that are provided by designers to ensure meeting reactor and fuel objectives.
dc.description.abstractThe sensitivity analysis system relates costs to uncertainties in nuclear data and methods by two sequences of operations broken at the few group data level. Path B determines the sensitivity of reactor fuel cycle cost to uncertainties in few group microscopic cross sections. Then for important cases Path A analysis relates few energy group cell averaged microscopiccross sections to uncertainties in basic nuclear data and in related computational methods.
dc.description.abstractA perturbation theory is developed for sensitivity analysis of nonlinear systems. It is applied to Path B analysis by code FCYCL linked to CaSTR. FCYCL computes forward and nonlinear adjoint solutions for batch depletion, then combines these to determine rates of changes in inventory of fresh and spent fuel with respect to changes in group data, power demand, and other parameters. The perturbation technique deter mines not only sensitivities, but also initial conditions required tachieve desired end-of-cycle conditions.
dc.language.isoENG
dc.publisherRensselaer Polytechnic Institute, Troy, NY
dc.relation.ispartofRensselaer Theses and Dissertations Online Collection
dc.subjectNuclear engineering
dc.titleSensitivity of nuclear fuel cycle costs to uncertainties in nuclear data and methods
dc.typeElectronic thesis
dc.typeThesis
dc.digitool.pid177972
dc.digitool.pid177973
dc.digitool.pid177974
dc.rights.holderThis electronic version is a licensed copy owned by Rensselaer Polytechnic Institute, Troy, NY. Copyright of original work retained by author.
dc.description.degreePhD
dc.relation.departmentDepartment of Nuclear Engineering


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