Improved data evaluation methodology for energy ranges with missing experimental data
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A. Yu. Konobeyev
Abstract
A number of improvements of the data evaluation concerning nuclear model calculations and evaluation procedures are considered. A promising combination of the hybrid Monte Carlo simulation model of M. Blann for the modelling of non-equilibrium particle emission and the Hauser-Feshbach model, and a possible correction of simulations using intranuclear cascade evaporation model are discussed. In the last case the modelling of particle emission is improved by the consideration of nucleon-cluster interactions. The approach for reliable predictions of cross-sections using “optimal” nuclear model parameters and the method of their generation is discussed.
Kurzfassung
Eine Reihe von Verbesserungen der Datenauswertung mit Hilfe von Kernmodell-Rechnungen und der Auswertungsverfahren werden diskutiert. Eine viel-versprechende Kombination des Hybrid-Monte-Carlo-Simu-lationsmodells von M. Blann für die Modellierung der Vorgleichgewichts-Teilchenemission und des Hauser-Feshbach-Modells und eine Verbesserung der Simulation mit Hilfe des intranuklearen Kaskaden-Verdampfungsmodells werden erörtert. Im letzten Fall wird die Simulation der Teilchenemission durch die Berücksichtigung der Nukleon-Cluster-Wechsel-wirkung verbessert. Ein Ansatz für die zuverlässigen Vorher-sagen der Wirkungsquerschnitte mit Hilfe der „optimalen“ Kernmodellparameter und deren Bestimmungsmethode wird diskutiert.
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© 2015, Carl Hanser Verlag, München
Articles in the same Issue
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- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions