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Title: Application of fully ceramic microencapsulated fuels in light water reactors

Abstract

This study performs a preliminary evaluation of the feasibility of incorporation of Fully Ceramic Microencapsulated (FCM) fuels in light water reactors (LWRs). In particular, pin cell, lattice, and full core analyses are carried out on FCM fuel in a pressurized water reactor (PWR). Using uranium-based fuel and Pu/Np-based fuel in TRistructural isotropic (TRISO) particle form, each fuel design was examined using the SCALE 6.1 analytical suite. In regards to the uranium-based fuel, pin cell calculations were used to determine which fuel material performed best when implemented in the fuel kernel as well as the size of the kernel and surrounding particle layers. The higher fissile material density of uranium mononitride (UN) proved to be favorable, while the parametric studies showed that the FCM particle fuel design with 19.75% enrichment would need roughly 12% additional fissile material in comparison to that of a standard UO{sub 2} rod in order to match the lifetime of an 18-month PWR cycle. As part of the fuel assembly design evaluations, fresh feed lattices were modeled to analyze the within-assembly pin power peaking. Also, a 'color-set' array of assemblies was constructed to evaluate power peaking and power sharing between a once-burned and a fresh feed assembly.more » In regards to the Pu/Np-based fuel, lattice calculations were performed to determine an optimal lattice design based on reactivity behavior, pin power peaking, and isotopic content. After obtaining a satisfactory lattice design, the feasibility of core designs fully loaded with Pu/Np FCM lattices was demonstrated using the NESTLE three-dimensional core simulator. (authors)« less

Authors:
; ;  [1]; ; ;  [2]
  1. Dept. of Nuclear Engineering, Univ. of Tennessee-Knoxville, Knoxville, TN 37996-2300 (United States)
  2. Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107763
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 12 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CERAMICS; COMPARATIVE EVALUATIONS; DESIGN; ENRICHMENT; FISSILE MATERIALS; FUEL ASSEMBLIES; FUEL PARTICLES; FUEL PINS; NEPTUNIUM; NUCLEAR FUELS; NUCLEAR POWER PLANTS; PARAMETRIC ANALYSIS; PEAK LOAD; PLUTONIUM; PWR TYPE REACTORS; REACTOR SIMULATORS; THREE-DIMENSIONAL CALCULATIONS; URANIUM; URANIUM DIOXIDE; URANIUM NITRIDES

Citation Formats

Gentry, C., George, N., Maldonado, I., Godfrey, A., Terrani, K., and Gehin, J. Application of fully ceramic microencapsulated fuels in light water reactors. United States: N. p., 2012. Web.
Gentry, C., George, N., Maldonado, I., Godfrey, A., Terrani, K., & Gehin, J. Application of fully ceramic microencapsulated fuels in light water reactors. United States.
Gentry, C., George, N., Maldonado, I., Godfrey, A., Terrani, K., and Gehin, J. Sun . "Application of fully ceramic microencapsulated fuels in light water reactors". United States.
@article{osti_22107763,
title = {Application of fully ceramic microencapsulated fuels in light water reactors},
author = {Gentry, C. and George, N. and Maldonado, I. and Godfrey, A. and Terrani, K. and Gehin, J.},
abstractNote = {This study performs a preliminary evaluation of the feasibility of incorporation of Fully Ceramic Microencapsulated (FCM) fuels in light water reactors (LWRs). In particular, pin cell, lattice, and full core analyses are carried out on FCM fuel in a pressurized water reactor (PWR). Using uranium-based fuel and Pu/Np-based fuel in TRistructural isotropic (TRISO) particle form, each fuel design was examined using the SCALE 6.1 analytical suite. In regards to the uranium-based fuel, pin cell calculations were used to determine which fuel material performed best when implemented in the fuel kernel as well as the size of the kernel and surrounding particle layers. The higher fissile material density of uranium mononitride (UN) proved to be favorable, while the parametric studies showed that the FCM particle fuel design with 19.75% enrichment would need roughly 12% additional fissile material in comparison to that of a standard UO{sub 2} rod in order to match the lifetime of an 18-month PWR cycle. As part of the fuel assembly design evaluations, fresh feed lattices were modeled to analyze the within-assembly pin power peaking. Also, a 'color-set' array of assemblies was constructed to evaluate power peaking and power sharing between a once-burned and a fresh feed assembly. In regards to the Pu/Np-based fuel, lattice calculations were performed to determine an optimal lattice design based on reactivity behavior, pin power peaking, and isotopic content. After obtaining a satisfactory lattice design, the feasibility of core designs fully loaded with Pu/Np FCM lattices was demonstrated using the NESTLE three-dimensional core simulator. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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