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Title: Neutronics Studies of Uranium-bearing Fully Ceramic Micro-encapsulated Fuel for PWRs

Journal Article · · Nuclear Technology
DOI:https://doi.org/10.13182/NT14-3· OSTI ID:1163154
 [1];  [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
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Our study evaluated the neutronics and some of the fuel cycle characteristics of using uranium-based fully ceramic microencapsulated (FCM) fuel in a pressurized water reactor (PWR). Specific PWR lattice designs with FCM fuel have been developed that are expected to achieve higher specific burnup levels in the fuel while also increasing the tolerance to reactor accidents. The SCALE software system was the primary analysis tool used to model the lattice designs. A parametric study was performed by varying tristructural isotropic particle design features (e.g., kernel diameter, coating layer thicknesses, and packing fraction) to understand the impact on reactivity and resulting operating cycle length. Moreover, to match the lifetime of an 18-month PWR cycle, the FCM particle fuel design required roughly 10% additional fissile material at beginning of life compared with that of a standard uranium dioxide (UO2) rod. Uranium mononitride proved to be a favorable fuel for the fuel kernel due to its higher heavy metal loading density compared with UO2. The FCM fuel designs evaluated maintain acceptable neutronics design features for fuel lifetime, lattice peaking factors, and nonproliferation figure of merit.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1163154
Journal Information:
Nuclear Technology, Vol. 188, Issue 3; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 12 works
Citation information provided by
Web of Science

References (11)

A review of TRISO fuel performance models journal October 2010
Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients journal December 2013
Microencapsulated fuel technology for commercial light water and advanced reactor application journal August 2012
Nuclear fuels – Present and future journal May 2009
Estimation of maximum coated particle fuel compact packing fraction journal March 2007
Data Compilation for AGR-1 Baseline Coated Particle Composite LEU01-46T report April 2006
Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback journal December 2013
Reactor Physics Methods and Analysis Capabilities in SCALE journal May 2011
Fabrication and characterization of fully ceramic microencapsulated fuels journal July 2012
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE journal May 2011
The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios journal July 2012

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Production of near‐full density uranium nitride microspheres with a hot isostatic press journal May 2018

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10 SYNTHETIC FUELS
ATF
FCM
LWR
fuel
TRISO
fully ceramic microencapsulated
accident tolerant fuel
nuclear
reactor physics
neutronics