Abstract

Korea has developed a Helium Cooled Ceramic Reflector Test Blanket Module (Ko HCCR TBM) related to the ITER project. Tungsten is considered as a prime candidate for the plasma facing materials in fusion reactors, and for the structure material of Ko HCCR TBM. KAERI (Korea Atomic Energy Research Institute) has been evaluating neutron cross sections of tungsten isotopes for neutron energy of up to 150 MeV based on nuclear reaction codes and available measurement data. New experimental data were measured at nELBE of HZDR (Helmholtz-Zentrum Dresden-Rossendorf) for a comparison with the evaluated and existing measurement data. The neutron source nELBE adopts a 40 MeV superconducting electron linac and a liquid Pb target for time-of-flight measurements. The nELBE neutron source uses no moderator and provides fast neutrons. An electron bunch length of 5 ps and a compact target provide a good neutron energy resolution with a relatively short flight length compared to other time-of-flight neutron sources. Transmission data of a natural tungsten sample were measured with a flight path length of 852.1 cm and a repetition rate of 101.56 kHz. The neutron total cross section of natural tungsten was obtained for an energy range of 100 keV to 10 MeV.

Highlights

  • The International Thermonuclear Experimental Reactor (ITER) has been developed to demonstrate the feasibility of electricity-producing fusion power stations

  • KAERI (Korea Atomic Energy Research Institute) has been evaluating neutron cross sections of tungsten isotopes for neutron energy of up to 150 MeV based on nuclear reaction codes and available measurement data

  • Different types of tritium breeding blankets have been developed, and one of them is the Helium Cooled Ceramic Reflector Test Blanket Module developed by Korea (Ko HCCR TBM) [1]

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Summary

Introduction

The International Thermonuclear Experimental Reactor (ITER) has been developed to demonstrate the feasibility of electricity-producing fusion power stations. Reduced Activation Ferritic/Martensitic (RAFM) steel has been developed as the structure material for the first and side walls of Ko HCCR TBM [2]. Tungsten is considered as a prime candidate of plasma facing materials in fusion reactors and an element of RAFM steel of Ko HCCR TBM. The neutron reaction cross sections of tungsten have been updated in the recent versions of the evaluated nuclear data libraries such as ENDF/B-VII.1 [3], JEFF3.2 [4] and JENDL4.0 [5]. The Korea Atomic Energy Research Institute (KAERI) has been evaluating the neutron total, elastic scattering, and inelastic scattering cross sections of tungsten for neutron energy of up to 150 MeV based on nuclear reaction codes and the available measurement data [6]

Experimental method
Data analysis
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