Researching | Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor

NUCLEAR TECHNIQUES, Volume. 48, Issue 4, 040602(2025)

Prediction model of fouling radioactive distribution in primary loop of pressurized water reactor

Shiwei WANG^1,2, Xiaojing LIU^1,2, Tengfei ZHANG^1,2, and Hui HE^1,2、*

Author Affiliations

¹School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

²Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center, Shanghai 200240, China

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Figures&Tables (11)

References (24)

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Figures & Tables(11)

Fig. 1. Corrosion product transport mode in the primary loop

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Fig. 2. Computational flowchart for CRUD deposition model and radioactive prediction model

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Fig. 3. Radioactive material transport mode in the primary loop

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Fig. 4. Prediction results of the SG and core corrosion product inventory

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Fig. 5. Prediction results of the SG and core radioactive product inventory

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Fig. 6. Radioactive materials inventory and distribution at different coolant flow rates

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Fig. 7. Radioactive materials inventory and distribution at different hydrogen concentrations

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Fig. 8. Radioactive materials inventory and distribution at different coolant inlet temperatures

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Table 1. Neutron fluxes and cross sections in NITR-II

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Table 1. Neutron fluxes and cross sections in NITR-II

反应

Reaction

中子通量 Neutron

flux / n·cm^-2·s^-1

截面值

Cross section

{}^{59} C o (n, γ) {}^{60}C o

{\bar{ϕ}}_{2 200} = 2.6 \times 10^{13}

{\bar{σ}}_{2 200} = 37 b

{}^{58} N i (n, p) {}^{58}C o

{\bar{ϕ}}_{E > 1 M e V} = 5.0 \times 10^{13}

{\bar{σ}}_{E > 1 M e V} = 100 m b

{}^{60} N i (n, p) {}^{60}C o

{\bar{ϕ}}_{E > 4 M e V} = 4.6 \times 10^{12}

{\bar{σ}}_{E > 4 M e V} = 23.4 m b

Table 2. Parameters of PCCL reference run No.2

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Table 2. Parameters of PCCL reference run No.2

参数 Parameters	数值 Value
堆芯温度 Core temperature / ℃	273.9
SG温度 SG temperature / ℃	315.6
硼浓度 Boron concentration / 10^-6	800
氢氧化锂浓度 Lithium hydroxide concentration / 10^-6	1.84
氢气浓度 Hydrogen concentration / mL·(kg·H₂O)^-1	25
冷却剂流速 Coolant flow rate / (kg^.H₂O)·day^-1	5 914

Table 3. Typical PWR operating parameters

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Table 3. Typical PWR operating parameters

参数 Parameter	数值 Value
燃料棒长度 Fuel rod length / m	3.66
冷却剂入口温度 Coolant inlet temperature / ℃	292.4
硼浓度 Boron concentration / 10^-6	800
氢氧化锂浓度 Lithium hydroxide concentration / 10^-6	1.84
氢气浓度 Hydrogen concentration / mL·(kg·H₂O)^-1	25
堆芯冷却剂流速 The coolant flow rate of core / m·s^-1	4.2
燃料周期 Fuel cycle / d	540

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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

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Paper Information

Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

Received: Dec. 19, 2023

Accepted: --

Published Online: Jun. 3, 2025

The Author Email: Hui HE (何辉)

DOI:10.11889/j.0253-3219.2025.hjs.48.230476

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