NUCLEAR TECHNIQUES, Volume. 48, Issue 4, 040602(2025)
Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor
[1] Deshon J. PWR axial offset anomaly (AOA) guidelines, revision 1: 1008102[R](2004).
[9] Rocher A, Bretelle J L, Berger M. Impact of main radiological pollutants on contamination risks (ALARA) optimization of physico chemical environment and retention technics during operation and shutdown[C](2003).
[10] QIU Bin, MAO Yulong, YAN Yalun et al. Study of corrosion products deposition and primary circuit source term levels in hybrid core[J]. Nuclear Science and Engineering, 43, 25-29(2023).
[12] Kang S, Sejvar J. CORA-II model of PWR corrosion-product transport[R]. EPRI NP-4246(1985).
[16] Jancic S J, Grootscholten P A M[M]. Progress in crystal growth and characterization, 434(1984).
[20] Best S E. Characterization of the MIT research reactor for fusion reactor related studies[D]. Department of Nuclear Engineering(1979).
[22] Wicks J H. Design, construction and testing of an in-pile loop for PWR simulation[D](1987).
[23] Bergmann C A, Durkosh D E, Lindsay W T et al[M]. The role of coolant chemistry in PWR radiation-field buildup, 2-18(1985).
[24] LIU Xinfu. Influence of primary water chemistry of PWR on the integrity of fuel cladding[D](2007).
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Shiwei WANG, Xiaojing LIU, Tengfei ZHANG, Hui HE. Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(4): 040602
Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING
Received: Dec. 19, 2023
Accepted: --
Published Online: Jun. 3, 2025
The Author Email: Hui HE (何辉)