Irradiation Tests of the Sleeve for the Telescopic Arm of the ITER Blanket Remote Handling System

被引:0
作者
SAITO M. [1 ]
KAWAI Y. [1 ]
TAKEDA N. [1 ]
机构
[1] Naka Institute for Fusion Science and Technology, National Institutes for Quantum Science and Technology, Ibaraki, Naka
关键词
blanket remote handling system; ITER; radiation resistance; remote maintenance;
D O I
10.1585/PFR.19.1405020
中图分类号
学科分类号
摘要
The ITER blanket remote handling system (BRHS) must operate with high precision within the confines of the ITER vacuum vessel, which will become a gamma-ray environment filled with radioactive dust. The main structural component of the BRHS, a telescopic arm, will be covered with a sleeve that must prevent not only the radioactive dust from infiltrating into the system but also lubricant from leaking out into the vacuum vessel. Verifying the radiation resistance of this sleeve is crucial and will ultimately affect the operation scenarios and timing of preventive maintenance for the BRHS. Thermoplastic polyurethane was selected as a candidate material for the sleeve. This paper presents the results of gamma-ray irradiation tests up to either 1MGy or 2MGy for polyurethane sheets and the results of subsequent bending, tensile, and hardness tests. Based on the results of these tests, mock-ups of the sleeve were manufactured and were also irradiated up to either 1MGy or 2MGy, after which the mock-ups underwent expansion and contraction tests to simulate actual operations in ITER. We have concluded from conservative estimates that, although these polyurethane sleeve mock-ups have over 1MGy of radiation resistance, the sleeves of the BRHS should be replaced at 1MGy. © (2024), (The Japan Society of Plasma Science and Nuclear Fusion Research). All Rights Reserved.
引用
收藏
相关论文
共 9 条
  • [1] Noguchi Y., Saito M., Maruyama T., Takeda N., Design Progress of ITER Blanket Remote Handling System towards Manufacturing, Fusion Eng. Des, 136, (2018)
  • [2] Damiani G., Et al., Overview of the ITER remote maintenance design and of the development activities in Europe, Fusion Eng. Des, 136, (2018)
  • [3] Saito M., Kozaka H., Maruyama T., Noguchi Y., Nakata K., Takeda N., Kakudate S., Irradiation tests of radiation hard materials for ITER blanket remote handling system, Fusion Eng. Des, 124, (2017)
  • [4] PEEK Biomaterials Handbook, pp. 75-79, (2012)
  • [5] Saito M., Takeda N., Decontamination tests of dust under load for the ITER Blanket Remote Handling System, Fusion Eng. Des, 146, (2019)
  • [6] Schollenberger C.S., Stewart F.D., Thermoplastic Polyurethane Hydrolysis Stability, Macro Molecular Materials and Engineering, 29, 1, (1973)
  • [7] Urabe M., The Basics of Infrared Spectroscopy and Its Recent Applications, Journal of The Society of Rubber Science and Technology, Japan, 90, 12, (2017)
  • [8] Barbes L., Radulescu C., Stihi C., ATR-FTIR Spectrometry Characterisation of Polymeric Materials, Romanian Reports in Physics, 66, 3, (2014)
  • [9] Seguchi T., Sorimachi M., Tamura K., Radiation resistance of polymer materials – Degradation evaluation by accelerated testing for application condition