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DEVELOPMENT OF AN IN-SITU CREEP TESTING CAPABILITY FOR ADVANCED TEST REACTOR

机译:开发前提测试反应堆的原位蠕变测试能力

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An instrumented creep testing capability is being developed for specimens irradiated in Pressurized Water Reactor (PWR) coolant conditions in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). The test rig is developed such that samples will be subjected to applied loads ranging from 92 to 350 MPa at temperatures between 290 and 370°C up to at least 2 dpa (displacement per atom). This paper reports the status of INL efforts to develop this testing capability. In addition to providing an overview of in-pile creep test capabilities available at other test reactors, this paper focuses on efforts to evaluate a prototype test rig in an autoclave at INL's High Temperature Test Laboratory (HTTL). Initial data obtained for stainless steel 304 in autoclave tests are presented.
机译:正在为爱达荷州国家实验室(INL)的高级测试反应器(ATR)中加压水反应器(PWR)冷却剂条件下照射的试样进行仪表蠕变测试能力。开发试验台,使得样品将在290至370℃的温度下,高达至少2dPa(每种原子的位移)的温度下的施加载荷范围为92至350MPa。本文报告了INL努力的状态以开发此测试能力。除了提供其他测试反应堆中可用的桩内蠕变测试能力的概述外,本文侧重于在INL的高温测试实验室(HTTL)的高压釜中评估原型试验室的努力。提出了在高压釜测试中获得的不锈钢304获得的初始数据。

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