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首页> 外文会议>The 3rd International Symposium on Material Chemistry in Nuclear Environment (Material Chemistry '02 MC'02) Mar 13-15, 2002 Tsukuba >DEVELOPMENT OF SSRT FACILITY WITH ABILITY OF IN-SITU OBSERVATION DURING SCC TEST IN HIGH TEMPERATURE WATER FOR IRRADIATED MATERIALS
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DEVELOPMENT OF SSRT FACILITY WITH ABILITY OF IN-SITU OBSERVATION DURING SCC TEST IN HIGH TEMPERATURE WATER FOR IRRADIATED MATERIALS

机译：辐照材料高温水中SCC试验过程中SSRT设施的现场观察能力发展

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摘要

Irradiation assisted stress corrosion cracking (IASCC) is one of the key issues for the life management of light water reactor (LWR) core components as well as one of the possible degradation phenomena of structural materials of international thermonuclear experimental reactor (ITER). For understanding IASCC phenomenon, development of slow stain rate test (SSRT) facility with ability of in-situ observation during SSRT in high temperature water for irradiated materials was initiated. The SSRT facility, which has already been installed in a hot cell, consists of a water make-up system, a pressurized high temperature water circulation system, a tensile testing system with an autoclave, a monitoring/purification system, a hydrogen peroxide injection system, and an observation/recording system. The autoclave has a sapphire window for in-situ observation of the specimen. Images through the window can be recorded using the CCD camera system. Since the SSRT facility is designed for irradiated materials under boiling water reactor (BWR) condition, the maximum operational parameters are as follows ; temperature : 573 K, pressure :10 MPa and flow rate : 30 l /h. To simulate the normal water chemistry (NWC) and hydrogen water chemistry (HWC) under BWR environment, dissolved oxygen and hydrogen concentrations (DO and DH) can be controlled within the range of 10 ppb - 32 ppm and 10 ppb - 2.8 ppm, respectively. Hydrogen peroxide can be injected into the autoclave to simulate influence of hydrogen peroxide produced from radiolysis of water in the reactor core.
机译：辐照辅助应力腐蚀开裂（IASCC）是轻水堆（LWR）堆芯组件寿命管理的关键问题之一，也是国际热核实验堆（ITER）结构材料可能发生的降解现象之一。为了了解IASCC现象，着手开发能够在高温水中对被辐照材料进行SSRT现场观察的慢速污点率测试（SSRT）设备。 SSRT设施已经安装在热室中，包括补水系统，加压高温水循环系统，带有高压釜的拉伸测试系统，监测/纯化系统，过氧化氢注入系统。以及观察/记录系统。高压釜有一个蓝宝石窗口，用于原位观察样品。通过窗口的图像可以使用CCD摄像机系统记录。由于SSRT设备是为沸水反应堆（BWR）条件下的辐照材料设计的，因此最大运行参数如下：温度：573K，压力：10MPa，流量：30l / h。为了模拟BWR环境下的正常水化学（NWC）和氢水化学（HWC），可将溶解氧和氢的浓度（DO和DH）分别控制在10 ppb-32 ppm和10 ppb-2.8 ppm的范围内。可以将过氧化氢注入高压釜中，以模拟由反应堆堆芯中水的辐射分解产生的过氧化氢的影响。

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