2022 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3H07-10] Heat Load Testing of Divertor Materials

Fri. Sep 9, 2022 11:00 AM - 12:00 PM Room H (E1 Bildg.3F No.33)

Chair:Akira Hasegawa(Tohoku Univ.)

11:15 AM - 11:30 AM

[3H08] Multiple irradiation experiment of tungsten materials by negative hydrogen ion beam

(1)Study of beam target materials

*Koichiro Hirano1, Makoto Fukuda3, Koichiro Ezato3, Kazutoshi Tokunaga2 (1. JAEA , 2. Kyushu Univ., 3. QST)

Keywords:beam target , ITER, tungsten , Multiple irradiation

The beam targets of the J-PARC linac are multiply irradiated by hydrogen negative ion beams with beam energy of 3 MeV. The purpose of this study is to clarify the pulsed heat load conditions that can withstand multiple irradiations when beam targets made of tungsten materials are used. Using an off-line beam test-stand with a 3 MeV hydrogen negative ion beam, multiple irradiation tests were conducted on tungsten materials for ITER, in which temperature changes of heating (3200°C) and cooling (160°C) were repeatedly given at a period of 5 Hz. This paper reports on the surface observation of the tungsten materials and the partial pressure measurements by a quadrupole mass spectrometer.