一回路水化学对燃料包壳表面CRUD (污垢)的影响
Effects of Primary Water Chemistry on Fuel CRUD
摘 要
分析了一回路水化学对CRUD （污垢）沉积影响的国外研究现状。结果表明，锆合金包壳表面CRUD沉积量随着一回路冷却剂pHT的升高而显著降低。部分研究表明CRUD沉积量随着溶解氢的提高而增加，亦有研究表明溶解氢对CRUD沉积量无任何影响。注锌可能减少CRUD的沉积，也可能增加CRUD的沉积。冷却剂中Ni、Fe腐蚀产物的浓度以及锆合金包壳材料表面初始性能同样对CRUD的沉积产生影响：腐蚀产物浓度越高，CRUD沉积量越多；锆合金表面氧化膜越厚，污垢（CRUD）沉积量越多。
CRUD
pHT
溶解氢
注锌
zirconium alloy cladding
CRUD
pHT
dissolved hydrogen
zinc injection
Abstract
The current situation of foreign researches on the effects of primary water chemistry on fuel CRUD deposition are analyzed. The results show that the CRUD deposition on the surface of zirconium alloy cladding significantly decreases with the increase of primary coolant pHT. Some studies show that CRUD deposition increases with the increase of dissolved hydrogen, while others show that dissolved hydrogen has no influence on CRUD deposition. Zinc injection might reduce CRUD deposition, and might also increase CRUD deposition. The concentration of Ni and Fe corrosion products in the coolant and the initial surface properties of zirconium alloy cladding materials also affect the deposition of CRUD:the higher the concentration of corrosion products, the more the CRUD deposition; The thicker the surface oxide film of zirconium alloy, the more the CRUD deposition.
中图分类号 TG174 DOI 10.11973/fsyfh-202210001
所属栏目 专论
基金项目 大型先进压水堆及高温气冷堆核电站（2019ZX06004002）
收稿日期 2020/11/11
修改稿日期
网络出版日期
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引用该论文: BAO Yichen,CHEN Zhigang,SHI Xiuqiang,LIU Xiaoqiang,ZHANG Lefu. Effects of Primary Water Chemistry on Fuel CRUD[J]. Corrosion & Protection, 2022, 43(10): 1
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参考文献
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【3】FYFITCH S.Corrosion and stress corrosion cracking of Ni-base alloys[M]//Comprehensive Nuclear Materials.Amsterdam:Elsevier, 2012:69-92.
【4】CASSINERI S, DUFF J, CURIONI M, et al.CRUD deposition in accelerated high-temperature water:investigation on the effect of substrate material and water chemistry[J].Journal of Nuclear Materials, 2020, 529:151915.
【5】YAGNIK S, GARDE A.Zirconium alloys for LWR fuel cladding and core internals[M]//Structural Alloys for Nuclear Energy Applications.Amsterdam:Elsevier, 2019:247-291.
【6】VAŠAACUTEK F, KAŠTÁNEK F, BOWEN B D, et al.Fine particle deposition in laminar and turbulent flows[J].The Canadian Journal of Chemical Engineering, 1995, 73(6):785-792.
【7】SZOLCEK M, CASSINERI S, CIONCOLINI A, et al.CRUD removal via hydrodynamic cavitation in micro-orifices[J].Nuclear Engineering and Design, 2019, 343:210-217.
【8】UCHIDA S, ASAKURA Y, OHSUMI K, et al.Chemical composition of crud depositing on BWR fuel surfaces[J].Journal of Nuclear Science and Technology, 1987, 24(5):385-392.
【9】PARK M S, SHIM H S, BAEK S H, et al.Effects of oxidation states of fuel cladding surface on crud deposition in simulated primary water of PWRs[J].Annals of Nuclear Energy, 2017, 103:275-281.
【10】SHIM H S, PARK M S, BAEK S H, et al.Effect of aluminum oxide coated on fuel cladding surface on crud deposition in simulated PWR primary water[J].Annals of Nuclear Energy, 2018, 121:607-614.
【11】BAEK S H, SHIM H S, KIM J G, et al.Effects of dissolved hydrogen on fuel crud deposition and subcooled nucleate boiling in PWR primary water at 328℃[J].Nuclear Engineering and Design, 2019, 345:85-93.
【12】CHOI J S, PARK S C, PARK K R, et al.Effect of zinc injection on the corrosion products in nuclear fuel assembly[J].Natural Science, 2013, 5(2):173-181.
【13】KIM M H, KIM U C, WON C W, et al.Experimental evaluation of primary water chemistry for prevention of axial offset anomaly[J].Thermochimica Acta, 2012, 542:80-88.
【14】HENSHAW J, MCGUIRE J C, SIMS H E, et al. In The Chemistry of Fuel Crud Deposits and Its Effect on AOA in PWR Plants[C]//Proc Int Conf on Water Chemistry of Nuclear Reactors System.[S.l.]:[s.n], 2006:1-7.
【15】WANG G, BYERS W A, YOUNG M Y, et al.Thermal conductivity measurements for simulated PWR crud[C]//Proceedings of 201321st International Conference on Nuclear Engineering.Chengdu:[s.n], 2014.
【16】PAN C, JONES B G, MACHIELS A J.Concentration levels of solutes in porous deposits with chimneys under wick boiling conditions[J].Nuclear Engineering and Design, 1987, 99:317-327.
【17】SHORT M P.The particulate nature of the crud source term in light water reactors[J].Journal of Nuclear Materials, 2018, 509:478-481.
【18】ODAR S, RUDLING P, Crud in PWR/VVER coolant[C]//Advanced Nuclear Technology International.[S.l.]:[s.n.], 2014.
【19】SONG M C, LEE K J.The evaluation of radioactive corrosion product at PWR as change of primary coolant chemistry for long-term fuel cycle[J].Annals of Nuclear Energy, 2003, 30(12):1231-1246.
【20】YEON J W, JUNG Y, PYUN S I.Deposition behaviour of corrosion products on the Zircaloy heat transfer surface[J].Journal of Nuclear Materials, 2006, 354(1/2/3):163-170.
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