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Shurong Ding

Fudan University

Beijing West District Baiyun Load 10th

Shanghai, 100045

China

SCHOLARLY PAPERS

7

DOWNLOADS

216

TOTAL CITATIONS

2

Scholarly Papers (7)

1.

Multi-Scale Modelling and Underlying Mechanism Analysis for Volume Growth of U-Zr Alloys Under Irradiation

Number of pages: 27 Posted: 16 May 2024
affiliation not provided to SSRN, Fudan University, Fudan University, Fudan University and Fudan University
Downloads 52 (1,063,489)

Abstract:

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diffusion creep and dislocation creep, multi-scale modeling, bubble growth mechanism, hydrostatic pressure, fission gas swelling

2.

Multi-Scale Simulation of the Thermo-Mechanical Coupling Behaviors in a Helical Cruciform Fuel Assembly with U-70at%Zr Fuel Core and Zr-4 Cladding

Number of pages: 47 Posted: 01 Aug 2024
affiliation not provided to SSRN, Fudan University, Fudan University, Fudan University, Harbin Engineering University, affiliation not provided to SSRN, Shanghai Jiao Tong University (SJTU), affiliation not provided to SSRN and Fudan University
Downloads 46 (1,121,190)
Citation 1

Abstract:

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helical cruciform fuel assembly, thermo-mechanical coupling, multi-scale volume growth, fission gas swelling, thermal creep and irradiation creep.

3.

Modeling and analysis of annealing-induced blister behaviors  in irradiated U-10Mo/Al monolithic fuel plates

Number of pages: 39 Posted: 31 Oct 2025
Fudan University, Fudan University, Fudan University, Tongji University and Fudan University
Downloads 38 (1,249,711)

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cohesive zone model, fission gas release-volume-pressure coupling model, U-10Mo/Al monolithic fuel plate, cracking, blister threshold temperature

4.

Modeling of the Damage and Fracture Behaviors of a Sic Triplex Tube During the Burst Test with Elastomeric Insert

Number of pages: 22 Posted: 29 Mar 2024
Fudan University, Fudan University, affiliation not provided to SSRN, Fudan University, affiliation not provided to SSRN, China Nuclear Power Technology Research Institute Co., Ltd, Fudan University, Fudan University and Fudan University
Downloads 25 (1,385,945)
Citation 1

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SiC triplex tube, Damage, Fracture, Numerical simulation, Hoop strength

5.

Modeling and Mechanism Analysis for the Anisotropic Irradiation Swelling of Porous Sic/Sic Composites

Number of pages: 29 Posted: 15 Oct 2024
Luning Chen, Jing Zhang and Shurong Ding
Fudan University, Fudan University and Fudan University
Downloads 23 (1,411,822)

Abstract:

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SiC/SiC composites, Anisotropic irradiation swelling, Residual stress, Irradiation creep, Numerical simulation

6.

On the Young's Modulus Degradation of Irradiated U-10mo Fuels

Number of pages: 26 Posted: 14 Jan 2025
Fudan University, Fudan University, Fudan University, Fudan University, Fudan University, Fudan University and Tongji University
Downloads 22 (1,436,435)

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Young's modulus degradation, fission gas bubbles, U-10Mo fuel skeleton, porosity

7.

Modeling of fission-gas-related near-interface cracking and thermo-mechanical coupling in TRISO fuel under high temperature irradiation

Number of pages: 46 Posted: 25 Jun 2026
Zekun Li, Jing Zhang, Shurong Ding and Qi-Sen Ren
Fudan University, Fudan University, Fudan University and affiliation not provided to SSRN
Downloads 10

Abstract:

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Near-interface cracking, fission gas swelling and release, TRISO particle, Cohesive Model, HTGR fuel pellet