Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data
Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimenta...
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| Published in | Nuclear data sheets Vol. 113; no. 12; pp. 3054 - 3100 |
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| Main Authors | , , , , , , , , , , , , |
| Format | Journal Article |
| Language | English |
| Published |
United States
Elsevier Inc
01.12.2012
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| Subjects | |
| Online Access | Get full text |
| ISSN | 0090-3752 1095-9904 |
| DOI | 10.1016/j.nds.2012.11.005 |
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| Abstract | Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimental data used in the adjustment process and an assessment of the experimental covariance data is of primary importance in determining the accuracy of evaluated cross section data. In this contribution, uncertainty components of experimental observables resulting from total and reaction cross section experiments are quantified by identifying the metrological parameters involved in the measurement, data reduction and analysis process. In addition, different methods that can be applied to propagate the covariance of the experimental observables (i.e. transmission and reaction yields) to the covariance of the resonance parameters are discussed and compared. The methods being discussed are: conventional uncertainty propagation, Monte Carlo sampling and marginalization. It is demonstrated that the final covariance matrix of the resonance parameters not only strongly depends on the type of experimental observables used in the adjustment process, the experimental conditions and the characteristics of the resonance structure, but also on the method that is used to propagate the covariances. Finally, a special data reduction concept and format is presented, which offers the possibility to store the full covariance information of experimental data in the EXFOR library and provides the information required to perform a full covariance evaluation. |
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| AbstractList | Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimental data used in the adjustment process and an assessment of the experimental covariance data is of primary importance in determining the accuracy of evaluated cross section data. In this contribution, uncertainty components of experimental observables resulting from total and reaction cross section experiments are quantified by identifying the metrological parameters involved in the measurement, data reduction and analysis process. In addition, different methods that can be applied to propagate the covariance of the experimental observables (i.e. transmission and reaction yields) to the covariance of the resonance parameters are discussed and compared. The methods being discussed are: conventional uncertainty propagation, Monte Carlo sampling and marginalization. It is demonstrated that the final covariance matrix of the resonance parameters not only strongly depends on the type of experimental observables used in the adjustment process, the experimental conditions and the characteristics of the resonance structure, but also on the method that is used to propagate the covariances. Finally, a special data reduction concept and format is presented, which offers the possibility to store the full covariance information of experimental data in the EXFOR library and provides the information required to perform a full covariance evaluation. |
| Author | Danon, Y. Junghans, A.R. Guber, K. Becker, B. Sirakov, I. Heyse, J. Moxon, M.C. Volev, K. Harada, H. Schillebeeckx, P. Kopecky, S. Otuka, N. Massimi, C. |
| Author_xml | – sequence: 1 givenname: P. surname: Schillebeeckx fullname: Schillebeeckx, P. email: peter.schillebeeckx@ec.europa.eu organization: EC-JRC-IRMM, Retieseweg 111, B-2440 Geel, Belgium – sequence: 2 givenname: B. surname: Becker fullname: Becker, B. organization: EC-JRC-IRMM, Retieseweg 111, B-2440 Geel, Belgium – sequence: 3 givenname: Y. surname: Danon fullname: Danon, Y. organization: Rensselaer Polytechnic Institute, Troy, NY 12180, USA – sequence: 4 givenname: K. surname: Guber fullname: Guber, K. organization: Oak Ridge National Laboratory, Oak Ridge, TN 37831-6171, USA – sequence: 5 givenname: H. surname: Harada fullname: Harada, H. organization: Japan Atomic Energy Agency (JAEA), Tokai, Naka, Ibaraki 319-1195, Japan – sequence: 6 givenname: J. surname: Heyse fullname: Heyse, J. organization: EC-JRC-IRMM, Retieseweg 111, B-2440 Geel, Belgium – sequence: 7 givenname: A.R. surname: Junghans fullname: Junghans, A.R. organization: Helmholtz-Zentrum Dresden Rossendorf, D-01314 Dresden, Germany – sequence: 8 givenname: S. surname: Kopecky fullname: Kopecky, S. organization: EC-JRC-IRMM, Retieseweg 111, B-2440 Geel, Belgium – sequence: 9 givenname: C. surname: Massimi fullname: Massimi, C. organization: University of Bologna and Sezione INFN of Bologna, Via Irnerio 46, I-40126 Bologna, Italy – sequence: 10 givenname: M.C. surname: Moxon fullname: Moxon, M.C. organization: Hyde Copse 3, Marcham, UK – sequence: 11 givenname: N. surname: Otuka fullname: Otuka, N. organization: IAEA Nuclear Data Section, International Atomic Energy Agency, Wagramerstraße, Vienna, A-1400, Austria – sequence: 12 givenname: I. surname: Sirakov fullname: Sirakov, I. organization: Institute for Nuclear Research and Nuclear Energy, BG-1784 Sofia, Bulgaria – sequence: 13 givenname: K. surname: Volev fullname: Volev, K. organization: EC-JRC-IRMM, Retieseweg 111, B-2440 Geel, Belgium |
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| Snippet | Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by... |
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| SubjectTerms | ACCURACY CROSS SECTIONS DATA ANALYSIS EVALUATION LIBRARIES MATRICES MONTE CARLO METHOD NEUTRON REACTIONS NEUTRONS NUCLEAR DATA COLLECTIONS NUCLEAR PHYSICS AND RADIATION PHYSICS NUCLEAR REACTION YIELD RESONANCE |
| Title | Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data |
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