Session: 05-02 Fuel Performance Assessment

Paper Number: 64920

Start Time: August 5, 2021, 04:15 PM

64920 - Preliminary Research on The Thermal-Mechanical Coupling Behavior Simulation Method of M3 Fuel 

M3 fuel which microencapsulated TRISO particles in zirconium metal matrix is an integrated fuel designed to replace the traditional pellet-cladding fuel rod. The fuel design can effectively solve the problems of LWR fuel, such as water side corrosion, abrasion, pellet-cladding interaction, stress corrosion cracking and internal pressure bracing. In order to predict the in-pile behavior of M3 fuel accurately and to optimize the design of M3 fuel, it is necessary to establish a numerical simulation method of irradiation-thermal -mechanical coupling behavior of M3 fuel.In this research , based on ABAQUS commercial software, by coding related user-defined subroutines(such as UMAT subroutine,USDFLD subroutine and GAPCON subroutine), the irradiation swelling, thermal expansion, irradiation creep, thermal creep, elastic-plastic deformation of related materials(such as UO₂ kernal, Buffer layer, PyC layer, SiC layer, metal matrix), the temperature and irradiation effects on fuel material parameters etc , were all introduced into this numerical simulation, and then the irradiation - thermal - mechanical coupling behavior simulation method of M3 fuel was preliminary established. Compared with the simulation result of BISON software in open literature, the simulation result of this numerical simulation method is the same as the BISON software, the effectiveness of this numerical simulation method was verified .

Presenting Author: Changbing Tang Science and Technology On Reactor System Design Technology Laboratory, NPIC

Authors:

Changbing Tang Science and Technology On Reactor System Design Technology Laboratory, NPIC
Yongjun Jiao Science and Technology On Reactor System Design Technology Laboratory, NPIC
Yuanming Li Science and Technology On Reactor System Design Technology Laboratory, NPIC
Kun Zhang Science and Technology On Reactor System Design Technology Laboratory, NPIC