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Nuclear Cross-section Caused By The Integral K <sub> Eff Of </ Sub> Uncertainty Of One-dimensional Analysis Of Program Development

Posted on:2007-04-14Degree:MasterType:Thesis
Country:ChinaCandidate:Z GangFull Text:PDF
GTID:2192360242458667Subject:Nuclear science and engineering
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In general to solve a problem of reactor physics mainly needs calculation model, code and nuclear data. Theoretically these items influence the accuracy and precision of the calculation results. With the rapid development of computer technology and calculation technique, the influences of the model and code on the calculation precision reduce gradually. However the error of reactor physics computation caused by the uncertainty of nuclear data can not be neglected increasingly.The international investigations of reactor engineering computation uncertainty resulted from nuclear data uncertainties were began in 1970s, and widely involved with the problems of reactor physics, radiation shielding and reactor safety and so on. At present some reliable codes on sensitivity and uncertainty analysis have been developed in the world. But domestic work has not been carried out too much in this region.This thesis contents mainly two works. One is the development of one-dimensional sensitivity and uncertainty code SUCD1D of reactor integral parameter keff to cross-section data based on SN transport code ANISN and the cross section covariance matrices. The other is verification of the code by comparative calculations to CEFR with SUCD1D and MCNP.The main conclusions from the study are draw as follows:(1) The method of doing the sensitivity and uncertainty analysis of integral parameter to nuclear data with first-order perturbation theory is acquired from the investigation and learning of literature. In this paper the theoretical formulas of sensitivity and uncertainty from literature have been derived again for verification. And their numerical forms are obtained by using the discrete ordinates form with relation to ANISN code.(2) The SUCA1D code can calculate the sensitivity and uncertainty of keff resulting from the uncertainties of cross sections such as fission, capture, total, (n,p), (n,a) and fission data as spectrum and yield of fission neutron. The code reads the direct and adjoint fluxes (or angular fluxes) calculated by ANISN and the covariance data from input card, then generates the outputs of sensitivity and uncertainty by energy, region and nuclide respectively.(3)The code is validated preliminarily. The comparative calculations of sensitivity are performed for CEFR's balance core with SUCA1D and MCNP code. The comparison indicates the results are similar and consistent with theory. The uncertainty result of keff caused by some key cross sections are obtained and be comparable with the results provided by Russia using different codes and nuclear data.
Keywords/Search Tags:Nuclear data, Sensitivity, Uncertainty, Integral parameter, SUCA1D code
PDF Full Text Request
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