Experimental Research Progress of Chalk River Unidentified Deposits on PWR Fuel Element Surface

WU Zongpei; JIANG E; TANG Yueming; XIONG Jing; DENG Ping; ZHAO Yongfu; ZHANG Pingping

doi:10.11973/fsyfh-202403009

Corrosion & Protection > 2024 > 45(3): 61-68. > DOI: 10.11973/fsyfh-202403009

WU Zongpei, JIANG E, TANG Yueming, XIONG Jing, DENG Ping, ZHAO Yongfu, ZHANG Pingping. Experimental Research Progress of Chalk River Unidentified Deposits on PWR Fuel Element Surface[J]. Corrosion & Protection, 2024, 45(3): 61-68. DOI: 10.11973/fsyfh-202403009

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Experimental Research Progress of Chalk River Unidentified Deposits on PWR Fuel Element Surface

Nuclear Power Institute of China, Chengdu 610213, China

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Received Date: September 21, 2023

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Abstract

The chalk river unidentified deposits (CRUD) on the surface of pressurized water reactors (PWR) fuel elements has many adverse effects on the stable and reliable operation of the system. Therefore, it is very important for the safe and high-quality development of PWR to study the key influencing factors of the CRUD on PWR fuel elements and to develop the mitigation technology of CRUD. This paper summarizes the important results of the experimental study on the surface CRUD of fuel elements in PWR, summarizes the harm of CRUD on the cladding surface to the operation of the system, reviews the analysis and characterization results of the CRUD, and introduces the test methods of the out-of-pile hydrodynamic loop established by different research institutions. The influence law of material properties, thermal-hydraulic characteristics, coolant chemical conditions and corrosion product characteristics on CRUD on the surface of fuel elements are analyzed. The CRUD mitigation technology and related applications are investigated, and suggestions for the follow-up experimental research direction are put forward.
- chalk river unidentified deposit (CRUD),
- experimental investigation,
- fuel element,
- pressurized water reactor (PWR)

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[1]	KAZI S N, DUFFY G G, CHEN X D. Fouling and fouling mitigation on heated metal surfaces[J]. Desalination, 2012, 288: 126-134.
[2]	唐婵, 张靖周. 飞灰颗粒横掠管束的沉积特性数值研究[J]. 电站系统工程, 2016, 32(1): 1-4.
[3]	赵琳, 秦冰, 江建林, 等. 原油沥青质沉积影响因素[J]. 科学技术与工程, 2021, 21(15): 6278-6284.
[4]	秦冰, 赵琳, 江建林. 原油沥青质沉积抑制及解堵技术研究进展[J]. 石油炼制与化工, 2020, 51(10): 7-15.
[5]	DESHON J, HUSSEY D, KENDRICK B, et al. Pressurized water reactor fuel crud and corrosion modeling[J]. JOM, 2011, 63(8): 64-72.
[6]	(日)石榑显吉等编, 左民等译. 核设施去污技术[M]. 北京: 原子能出版社, 1997.
[7]	O′BRIEN C J, RÁK Z, BUCHOLZ E W, et al. First principles calculations predict stable 50 nm nickel ferrite particles in PWR coolant[J]. Journal of Nuclear Materials, 2014, 454(1/2/3): 77-80.
[8]	DUMNERNCHANVANIT ICharacterization and mitigation of crud at pressurized water reactor ConditionsBostonMassachusetts Institute of Technology2017DUMNERNCHANVANIT I. Characterization and mitigation of crud at pressurized water reactor Conditions [D]. Boston: Massachusetts Institute of Technology, 2017.
[9]	SOLOMON Y, ROESMER J. Measurement of fuel element crud deposits in pressurized water reactors[J]. Nuclear Technology, 1976, 29(2): 166-173.
[10]	TSAI T L, SU T Y, WANG T Y, et al. Characterization of crud deposited on fuel rods under HWC environment in Kuosheng Nuclear Power Plant[J]. Nuclear Science and Techniques, 2016, 27(1): 1.
[11]	GÜNTHER-LEOPOLD I, KROIS M, WALDIS J K, et al. Investigation of fuel crud by means of ICP-MS and TEM[J]. Procedia Chemistry, 2012, 7: 673-678.
[12]	SANDLER Y L. Structure of PWR primary corrosion products[J]. Corrosion, 1979, 35(5): 205-208.
[13]	YEON J W, CHOI I K, PARK K K, et al. Chemical analysis of fuel crud obtained from Korean nuclear power plants[J]. Journal of Nuclear Materials, 2010, 404(2): 160-164.
[14]	SAWICKI J A. Analyses of crud deposits on fuel rods in PWRs using Mössbauer spectroscopy[J]. Journal of Nuclear Materials, 2010, 402(2/3): 124-129.
[15]	BURRILL K A, SHADDICK AWater chemistry and the deposition of corrosion products on nuclear reactor fuelChalk River1980BURRILL K A, SHADDICK A. Water chemistry and the deposition of corrosion products on nuclear reactor fuel[R]. Chalk River: [s. n.], 1980.
[16]	WANG G, BYERS W A, YOUNG M Y, et alWestinghouse advanced loop tester (WALT) updateProceedings of 16th International Conference on Nuclear EngineeringOrlandor2009WANG G, BYERS W A, YOUNG M Y, et al. Westinghouse advanced loop tester (WALT) update[C]//Proceedings of 16th International Conference on Nuclear Engineering. Orlandor: [s. n.],2009.
[17]	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.
[18]	MCGRADY J, DUFF J, STEVENS N, et al. Development of a microfluidic setup to study the corrosion product deposition in accelerated flow regions[J]. NPJ Materials Degradation, 2017, 1: 21.
[19]	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.
[20]	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.
[21]	BAEK S H, SHIM H S, KIM J G, et al. Effect of chemical etching of fuel cladding surface on crud deposition behavior in simulated primary water of PWRs at 328 ℃[J]. Annals of Nuclear Energy, 2018, 116: 69-77.
[22]	IWAHORI T, MIZUNO T, KŌYAMA H. Role of surface chemistry in crud deposition on heat transfer surface[J]. Corrosion, 1979, 35(8): 345-350.
[23]	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.
[24]	BAEK S H, SHIM H S, KIM J G, et al. Effects of heat flux on fuel crud deposition and sub-cooled nucleate boiling in simulated PWR primary water at 13 MPa[J]. Annals of Nuclear Energy, 2019, 133: 178-185.
[25]	CASSINERI S, DUFF J, CIONCOLINI A, et al. Deposition of corrosion products under pressurised water nuclear reactor conditions: the effect of flow velocity and dissolved hydrogen[J]. Corrosion Science, 2019, 159: 108113.
[26]	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.
[27]	JEON S H, LEE E H, HUR D H. Effects of dissolved hydrogen on general corrosion behavior and oxide films of alloy 690TT in PWR primary water[J]. Journal of Nuclear Materials, 2017, 485: 113-121.
[28]	KIM K S, BAEK S H, SHIM H S, et al. Effect of zinc addition on fuel crud deposition in simulated PWR primary coolant conditions[J]. Annals of Nuclear Energy, 2020, 146: 107643.
[29]	PARK J Y, PARK K H, KIM K T, et alThe Effect of Zn Addition on CRUD formationTransactions of the Korean Nuclear Society Spring MeetingGwangjur2013PARK J Y, PARK K H, KIM K T, et al. The Effect of Zn Addition on CRUD formation[C]//Transactions of the Korean Nuclear Society Spring Meeting. Gwangjur: [s. n.], 2013.
[30]	PARK J Y, PARK K H, SATO NThe effect of Zn addition on the CRUD structureTransactions of the Korean Nuclear Society Autumn MeetingGyeongju2013PARK J Y, PARK K H, SATO N. The effect of Zn addition on the CRUD structure[C]//Transactions of the Korean Nuclear Society Autumn Meeting. Gyeongju: [s. n.], 2013.
[31]	HOLDSWORTH S, SCENINI F, BURKE M G, et al. The effect of high-temperature water chemistry and dissolved zinc on the cobalt incorporation on type 316 stainless steel oxide[J]. Corrosion Science, 2018, 140: 241-251.
[32]	LIU X H, WU X Q, HAN E H. Effect of Zn injection on established surface oxide films on 316 L stainless steel in borated and lithiated high temperature water[J]. Corrosion Science, 2012, 65: 136-144.
[33]	ZIEMNIAK S E, HANSON M. Zinc treatment effects on corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J]. Corrosion Science, 2006, 48(9): 2525-2546.
[34]	ZIEMNIAK S E, HANSON M. Zinc treatment effects on corrosion behavior of Alloy 600 in high temperature, hydrogenated water[J]. Corrosion Science, 2006, 48(10): 3330-3348.
[35]	BAEK S H, KIM U C, SHIM H S, et al. Effect of Ni/Fe ion concentration ratio on fuel cladding crud deposition[J]. Corrosion Science and Technology, 2014, 13(4): 145-151.
[36]	马忠英, 陆道纲, 袁博, 等. 压水堆一回路颗粒性腐蚀产物沉积机理的实验研究[J]. 原子能科学技术, 2015, 49(12): 2239-2244.
[37]	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.
[38]	HAM J, LEE Y J, YOO S C, et al. Effect of TiN coating on the fouling behavior of crud on pressurized water reactor fuel cladding[J]. Journal of Nuclear Materials, 2021, 549: 152870.
[39]	DUMNERNCHANVANIT I, ZHANG N Q, ROBERTSON S, et al. Initial experimental evaluation of CRUD-resistant materials for light water reactors[J]. Journal of Nuclear Materials, 2018, 498: 1-8.
[40]	SONG M, KIM S I, LEE K. Development of moving alternating magnetic filter using permanent magnet for removal of radioactive corrosion product from nuclear power plant[J]. Nuclear Engineering and Technology, 2002, 34: 494-501.

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Experimental Research Progress of Chalk River Unidentified Deposits on PWR Fuel Element Surface

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