Abstract

Using the Fully Ceramic Microencapsulated (FCM) fuel in light water reactors has multiple advantages, as it is accident tolerant because of; no hydrogen generation due to the cladding interaction with steam at high temperature, better retention of fission fragments and proliferation resistant due to very small production of transuranic elements during the burnup as compared to the standard UO2 fuel. In this study neutronics analysis of AT-FCM fuel consisting of TRISO particles embedded in SiC matrix is performed for replacement in existing VVER-1000 reactors. Standard VVER-1000 fuel assembly is transformed to Accident Tolerant Fully Ceramic Microencapsulated (AT-FCM) fuel assembly based on hydraulic diameter of the VVER-1000 assembly, the number of fuel pins are decreased with increased diameter and enrichment to conserve the initial fissile loading in AT-FCM assembly. Fuel centerline temperature of the AT-FCM assembly is found to be lower than the reference UO2 fuel assembly at the same total power produced because of the much higher thermal conductivity. FCM-TRISO fuel assembly namely Array 15 with 169 pins is proposed and analyzed. Pin cell, assembly level and full core calculations have been performed with SERPENT code using implicit and explicit models. VVER-1000 full core is modelled using the transformed FCM assembly. The embedded TRISO particles in a SiC matrix and the use of FeCrAl cladding turns out to be the perfect case for accident tolerance. High burnup of AT-FCM core in terms of MWd/kgHM for the same number of EFPDs is observed as compared to reference UO2 core due to the small breeding of transuranic elements Pu-239, Pu-240 and Pu-241. Appreciable quantity of the power is produced due to the fission of transuranic elements in reference UO2 assembly so the burnup in MWd/kgHM remains smaller than the AT-FCM fuel. Comparatively more softening of spectrum is found in AT-FCM fuel cells and assemblies towards the middle of the cycle (MOC) and End of the Cycle (EOC), this softening of spectrum tends to increase the rate of U-235 depletion. Very small quantities of plutonium isotopes are produced in AT-FCM as compared to the reference UO2 assembly because of small loading of U-238 at the BOC. The neutronics performance of AT-FCM core with burnable poison consisting of Gd2O3 and Er2O3 turn out to be better than reference UO2 assembly as it exhibits smooth burnup. Fuel Temperature Coefficient (FTC) and Moderator Temperature Coefficient (MTC) of the AT-FCM assembly is negative for most part of the cycle however, towards the end of cycle it becomes less negative due to small quantities of resonance absorbers, softening of thermal flux and increased rate of fission absorption in UO2.

Highlights

  • The idea of using Fully Ceramic Microencapsulated (FCM)-TRISO fuel in LWRs is under consideration since the severe accident of Fukushima Daiichi power plants because of its proven performance in High Temperature Gas Cooled Reactors (HTGRs)

  • Many options are available for fuel kernel of the TRISO particles but lately most of the research work has been focused on Uranium Carbide (UC) and Uranium Nitride (UN)

  • The purpose of this study is to perform a preliminary neutronics analysis of FCM-TRISO fuel to be used in VVER-1000 reactor core

Read more

Summary

Introduction

The idea of using FCM-TRISO fuel in LWRs is under consideration since the severe accident of Fukushima Daiichi power plants because of its proven performance in High Temperature Gas Cooled Reactors (HTGRs). It has multiple advantages such as better fission fragments retention, accident tolerant due to the use of innovative claddings, which does not interact with steam at high temperatures and proliferation resistance because of very small production transuranic elements. Relatively new cladding concepts such as ferritic steel FeCrAl, Silicon Carbide SiC and alloys of zirconium have been studied; each one has its own advantages and disadvantages [2] This neutronics analysis is performed using SERPENT code with explicit and implicit methods.

Objectives
Methods
Results
Conclusion
Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call