An overview is given of nuclear data applications in fusion neutronics as being addressed in different task areas of the European Fusion Technology Programme. Main applications are in the design and development of breeder blankets for fusion demonstration & power plants and test blanket modules for ITER, the International Thermonuclear Experimental Reactor. Benchmark analyses of integral 14 MeV neutron experiments are conducted to qualify nuclear data evaluations of the European Fusion & Activation Files (EFF/EAF) and to validate neutronic design calculations. Another major application area is in the development of an accelerator based Li-D intense neutron source for high fluence irradiations of fusion reactor materials. The associated development work includes evaluations of neutron cross-sections above 20 MeV and the development of a Li(d, xn) source term model for Monte Carlo calculations. The paper addresses key issues and major achievements in these areas and concludes with guidelines for future developments both with regard to nuclear data improvements and required integral experiments. © 2014 Atomic Energy Society of Japan.

Application of nuclear data in fusion neutronics

Batistoni, P.
2002

Abstract

An overview is given of nuclear data applications in fusion neutronics as being addressed in different task areas of the European Fusion Technology Programme. Main applications are in the design and development of breeder blankets for fusion demonstration & power plants and test blanket modules for ITER, the International Thermonuclear Experimental Reactor. Benchmark analyses of integral 14 MeV neutron experiments are conducted to qualify nuclear data evaluations of the European Fusion & Activation Files (EFF/EAF) and to validate neutronic design calculations. Another major application area is in the development of an accelerator based Li-D intense neutron source for high fluence irradiations of fusion reactor materials. The associated development work includes evaluations of neutron cross-sections above 20 MeV and the development of a Li(d, xn) source term model for Monte Carlo calculations. The paper addresses key issues and major achievements in these areas and concludes with guidelines for future developments both with regard to nuclear data improvements and required integral experiments. © 2014 Atomic Energy Society of Japan.
Monte Carlo transport;Intermediate energy data;Intense neutron source;Fusion reactor;Fusion nuclear data;Fusion neutronics;Design calculations;Activation data;Benchmark analyses
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/1702
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