Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor

Xirong Chen; Jinsen Xie; Tao Yu; Zining Ni; Nianbiao Deng; Zeng Shao; Haoran Xie

doi:10.11884/HPLPB202335.230010

High Power Laser and Particle Beams, Volume. 35, Issue 5, 056002(2023)

Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor

Xirong Chen^1,2, Jinsen Xie^1,2, Tao Yu^1,2、*, Zining Ni^1,2, Nianbiao Deng^2,3, Zeng Shao⁴, and Haoran Xie^1,2

Author Affiliations

¹School of Nuclear Science and Technology, University of South China, Hengyang 421001, China

²Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hengyang 421001, China

³School of Resource Environment and Safety Engineering, University of South China, Hengyang 421001, China

⁴China Nuclear Power Engineering Co., Ltd, Beijing 100840, China

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Figures & Tables(9)

Fig. 1. Assembly NJ07OG layout of PWR TMI-1

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Fig. 2. Axial position of the sample

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Fig. 3. Irradiation history of samples

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Fig. 4. Layout of other assemblies around the TMI-1 pressurized water reactor NJ07OG assembly

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Fig. 5. Four different burnup calculation models

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Fig. 6. Comparison of relative deviations of calculated values for major nuclides

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Fig. 7. Comparison of the average relative deviations

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Table 1. Fuel assembly geometric parameters (mm)

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Table 1. Fuel assembly geometric parameters (mm)

fuel pellet inner diameter	clad inner diameter	clad outer diameter	cell pitch	absorber rod pellet diameter	absorber rod cladding inner diameter
9.40	9.58	10.92	14.43	8.64	9.14

absorber rod cladding outer diameter	guide tube inner diameter	guide tube outer diameter	instrument tube inner diameter	instrument tube outer diameter	assembly pitch
10.92	12.65	13.46	11.2	12.52	218.11

Table 2. Nuclides chosen

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Table 2. Nuclides chosen

actinide nuclides	fission products
²³⁴U, ²³⁵U, ²³⁶U, ²³⁸U	¹⁵¹Eu, ¹⁵³Eu, ¹⁴³Nd, ¹⁴⁵Nd, ¹⁴⁸Nd
²³⁸Pu, ²³⁹Pu, ²⁴⁰Pu, ²⁴¹Pu, ²⁴²Pu	¹⁴⁷Sm, ¹⁴⁹Sm, ¹⁵⁰Sm, ¹⁵¹Sm, ¹⁵²Sm
²³⁷Np, ²⁴¹Am, ²⁴³Am, ²⁴⁴Cm	¹⁵⁵Gd

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Xirong Chen, Jinsen Xie, Tao Yu, Zining Ni, Nianbiao Deng, Zeng Shao, Haoran Xie. Analysis of different burnup calculation models on nuclide components of spent fuel assembly in commercial pressurized water reactor[J]. High Power Laser and Particle Beams, 2023, 35(5): 056002

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Paper Information

Category: Nuclear Science and Engineering

Received: Jan. 13, 2023

Accepted: --

Published Online: May. 6, 2023

The Author Email: Yu Tao (yutao29@sina.com)

DOI:10.11884/HPLPB202335.230010

Topics

laser devices and laser physics

Lasers and Laser Optics

Laser physics

laser manufacturing

Instrumentation, Measurement and Metrology