Abstract

In this paper, a two-dimensional characteristic unit was used to simulate the thermal–mechanical performance of a fully ceramic microencapsulated (FCM) fuel pellet, and the criterion of FCM structure integrity was discussed. FCM structure integrity can be reflected though the integrity of the silicon carbide (SiC) matrix or SiC layers because of the excellent fission retention capability of SiC ceramics. The maximum temperature of the SiC matrix under normal conditions of the pressure water reactor (PWR) environment was about 1390 K, which was lower than the decomposition point of SiC. The maximum hoop stress of the SiC matrix, especially the inner part, was up to about 1200 MPa, and the hoop stress of the non-fuel region part was lower than the inner part, which can be attributed to the deformation of tristructural-isotopic (TRISO) particles. The hoop stress of the SiC layers at the end of life was only about 180 MPa, which is much lower than the strength of the chemical vapor deposition (CVD)-SiC. The failure probability of the SiC layer was lower than 9 × 10−5; thus, the integrity of SiC layers and the fission retention capability were maintained. The structure integrity of FCM fuel was broken because the SiC matrix cracked.

Highlights

  • Ceramic microencapsulated (FCM) fuel, which can improve the accident tolerance of light water reactors (LWRs), receives much attention because of its excellent oxidation resistance, fission retention capability, high thermal conductivity, and irradiation stability [1,2,3,4]

  • The results indicated that uranium nitride (UN) kernel fully ceramic microencapsulated (FCM)

  • The results indicate that the thickness of the silicon carbide (SiC) matrix has an obvious influence on the stress distribution of the SiC and inner pyrocarbon (IPyC) layers

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Summary

Introduction

Ceramic microencapsulated (FCM) fuel, which can improve the accident tolerance of light water reactors (LWRs), receives much attention because of its excellent oxidation resistance, fission retention capability, high thermal conductivity, and irradiation stability [1,2,3,4]. The performance of the UN kernel TRISO fuel in the LWR environment was reported, and the influence of temperature and kernel size on internal pressure and the survivability of TRISO fuel was studied [9]. Ougouag and co-workers [13] studied the influence of the SiC matrix on the performance of TRISO fuel by adding an SiC matrix on the outer surface of a single TRISO particle model. The interaction between the TRISO particle and the SiC matrix was investigated, and the thermal–mechanical properties of the coated layers and SiC matrix were discussed. The fission production capacity of the FCM pellet was evaluated by investigating the failure probability of SiC layers and the hoop stress of the SiC matrix

Governing Equation
Material Properties
SiC Layer and SiC Matrix
Temperature Distribution of FCM Pellet
Mechanical
MPa at 1400
Mechanical Performance of SiC Layer
Conclusions
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