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Electrochemical Behavior of Accident Tolerant Fuel Cladding Materials under Simulated Light Water Reactor Conditions

机译:模拟轻水反应器条件下发生事故耐腐蚀材料的电化学行为

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After the Fukushima reactor accidents following Japan's March 2011 tsunami, the U.S. Department of Energy engaged with nuclear fuel vendors to develop improved fuels for the current fleet of light water power reactors. General Electric and Oak Ridge National Laboratory have proposed using iron-chrome-aluminum (FeCrAI) ferritic alloys as cladding material for the existing uranium dioxide fuel (U02). This is a simple approach that leaves unchanged the present coolable geometry in the reactor. FeCrAI alloys have outstanding resistance, in accident conditions, to attack by superheated steam compared to the current zirconium alloys. Since ferritic FeCrAI alloys have not been used before in nuclear power reactors, extensive characterization has been performed to determine their behavior in light water reactor conditions (e.g., normal operation and accident). The present work deals with the electrochemical behavior of the newer alloys in high-temperature water (near 300°C) containing either excess hydrogen gas or excess oxygen. Results show that chromium-containing ferritic FeCrAI have similar electrochemical high-temperature behavior like other common existing reactor alloys containing chromium for passivation (such as X-750, Alloy 600, and Type 304SS). The use of FeCrAI alloy cladding would also eliminate existing common degradation mechanisms such as shadow corrosion in boiling water reactors.
机译:随着日本2011年3月海啸的福岛反应堆事故发生后,能源的美国能源部与核燃料供应商参与开发改进燃料的轻水反应堆目前的机队。通用电气和橡树岭国家实验室已经采用铁铬铝(FeCrAl合金),铁素体合金作为现有的二氧化铀燃料(U02)覆层材料提出。这是一个简单的办法,叶不变的反应器本可冷却的几何形状。 FeCrAl合金合金具有出色的性能,在事故条件下,过热蒸汽相比,目前的锆合金的攻击。由于铁素体合金FeCrAl合金以前没有在核动力反应堆中使用,广泛表征已经被执行,以确定其在轻水反应堆的条件(例如,在正常操作和事故)的行为。在高温水较新的合金的电化学行为,本工作涉及(接近300℃)含有任一过量氢气或过量的氧。结果表明,含铬的铁素体FeCrAl合金具有类似含钝化铬(如X-750,合金600,和Type 304SS)其他常见的现有反应器的合金相似电化学高温行为。使用FeCrAl合金的合金包覆的也将消除现有的普通降解机制如阴影腐蚀在沸水反应器。

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