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首页> 外文期刊>Thermal engineering >Evaluation of the Corrosion State of Equipment of the First Circuit of Transport Nuclear Reactors Using the Parameters of Water Chemistry
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Evaluation of the Corrosion State of Equipment of the First Circuit of Transport Nuclear Reactors Using the Parameters of Water Chemistry

机译：利用水化学参数评价运输核反应堆第一电路的腐蚀状态

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Abstract— An analysis of the results of investigation into the composition of the primary coolant of power units of nuclear-powered ice breakers Soviet Union and Arktika and the Sevmorput’ light carrier has revealed that an increase in the reactor power generation above 14 TW h leads to a sharp increase in the ammonia concentration in the coolant. An assumption was made that this effect was related with the radiation-chemical synthesis of ammonia from the nitrogen dissolved in the coolant and hydrogen resulting from enhancement of corrosion of the core structural members and fuel rod claddings made of zirconium alloys. To test the proposed hypothesis on the basis of the verified MORAVA H2 software package, a procedure was developed for calculating changes in the composition of the primary coolant in water-cooled water-moderated reactors (VVER) on exposure to reactor radiation with simultaneous metering of hydrogen at a controlled rate into the primary circuit (to simulate formation of corrosive hydrogen) during irradiation. This procedure was used to perform a computational experiment to find the qualitative regularities of the effect of “corrosive” hydrogen on the characteristics of water chemistry. The dependence of the calculated ratio of molar concentrations [NH~(3)]/[H~(2)] on the irradiation time has been demonstrated to linearly correlate with the measured dependencies of this ratio on the power output of similar reactor units on various nuclear-powered ships. This correlation allows for the statement on a reasonable basis that the [NH~(3)]/[H~(2)] ratio in the primary coolant of transport nuclear units is a fair indicator of the fact of general corrosion of zirconium alloys in the core having a structural member made of alloy E110.
机译：摘要 - 对核动力分布苏联和arktika电力单元的主要冷却剂组成的调查结果分析，Sevmorput'光载体的揭示揭示了14 TW HID以上的反应器发电增加在冷却剂中氨浓度的急剧增加。假设这一效果与溶解在冷却剂和氢气中的氮的氨的辐射和氢气的辐射化学合成有关，这是由核心结构构件和由锆合金制成的燃料杆包层的腐蚀的腐蚀而导致的。为了在验证的Morava H2软件包的基础上测试所提出的假设，开发了一种程序，用于在暴露于反应器辐射的情况下计算水冷水调节反应器（Vver）中的初级冷却剂组合物的变化。同时计量在照射期间，以受控速率的氢气以受控速率（以模拟腐蚀性氢的形成）。该程序用于执行计算实验，以找到“腐蚀性”氢对水化学特性的效果的定性规律。已经证明了摩尔浓度[NH〜（3）] / [H〜（2）]对照射时间对照射时间的依赖性的依赖性，以线性地关联与类似电抗器单元的功率输出的该比率的测量依赖性各种核动力船只。这种相关性允许合理的陈述，即运输核单位的主要冷却剂中的[NH〜（3）] / [H〜（2）]比率是锆合金一般腐蚀的公平指标具有由合金E110制成的结构构件的芯。

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