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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：利用水化学参数评估运输核反应堆一回路设备的腐蚀状态

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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—对苏联和阿尔克蒂卡核动力破冰船动力装置的主要冷却剂组成以及塞夫莫普特轻型载具的调查结果分析表明，反应堆发电量增加了14 TW h以上，导致急剧增加冷却液中氨的浓度。假定这种影响与由溶解在冷却剂中的氮和氢的辐射化学合成有关，氢是由锆合金制成的核心结构件和燃料棒包壳的腐蚀增强而产生的。为了在经过验证的MORAVA H2软件包的基础上检验提出的假设，开发了一种程序，用于计算水冷水慢化反应堆（VVER）暴露于反应堆辐射并同时计量加入时的主要冷却剂组成的变化。在辐照过程中，氢气以受控的速率进入初级回路（以模拟腐蚀性氢的形成）。该程序用于进行计算实验，以发现“腐蚀性”氢对水化学特性的影响的定性规律。已证明计算的摩尔浓度比[NH〜（3）] / [H〜（2）]对辐照时间的依赖性与该比率对类似反应堆装置的功率输出的测量依赖性呈线性相关。各种核动力船。这种相关性可以合理地说明运输核单位一次冷却剂中的[NH〜（3）] / [H〜（2）]比可以很好地表明锆合金普遍腐蚀的事实。芯具有由合金E110制成的结构构件。

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