Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N and Thermomechanics

T. M. Besmann; D. Shin; T. B. Lindemer; M. K. Ferber; P. F. Becher; A. A. Wereszczak; H. T. Lin

doi:10.2172/1553394

Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N and Thermomechanics

T. M. Besmann
, D. Shin
, T. B. Lindemer
, M. K. Ferber
, P. F. Becher
, A. A. Wereszczak
, H. T. Lin

Research output: Other contribution › Technical Report

Abstract

A new concept for light water reactor (LWR) nuclear fuel has recently been proposed that utilizes pellets of tristructural isotropic (TRISO) fuel particles embedded in a SiC or zirconium alloy matrix, replacing sintered urania pellets. The fuel is considered significantly more accident tolerant than urania as the SiC matrix or coated/protected zirconium alloy and TRISO particles would be highly resistant to oxidation and fission product release under beyond-design-basis accident conditions. As is well understood, failed fuel rods release gaseous and volatile fission products, and that is greatly exacerbated as urania oxidizes from UO_2+x to higher oxidations states in failed fuel pin with resulting expansion, loss of integrity, and significant further release of fission products.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1553394
State	Published - 2023

Keywords

73 NUCLEAR PHYSICS AND RADIATION PHYSICS

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10.2172/1553394

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title = "Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N and Thermomechanics",

abstract = "A new concept for light water reactor (LWR) nuclear fuel has recently been proposed that utilizes pellets of tristructural isotropic (TRISO) fuel particles embedded in a SiC or zirconium alloy matrix, replacing sintered urania pellets. The fuel is considered significantly more accident tolerant than urania as the SiC matrix or coated/protected zirconium alloy and TRISO particles would be highly resistant to oxidation and fission product release under beyond-design-basis accident conditions. As is well understood, failed fuel rods release gaseous and volatile fission products, and that is greatly exacerbated as urania oxidizes from UO2+x to higher oxidations states in failed fuel pin with resulting expansion, loss of integrity, and significant further release of fission products.",

keywords = "73 NUCLEAR PHYSICS AND RADIATION PHYSICS",

author = "Besmann, \{T. M.\} and D. Shin and Lindemer, \{T. B.\} and Ferber, \{M. K.\} and Becher, \{P. F.\} and Wereszczak, \{A. A.\} and Lin, \{H. T.\}",

year = "2023",

doi = "10.2172/1553394",

language = "English",

type = "Other",

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AU - Besmann, T. M.

AU - Shin, D.

AU - Lindemer, T. B.

AU - Ferber, M. K.

AU - Becher, P. F.

AU - Wereszczak, A. A.

AU - Lin, H. T.

PY - 2023

Y1 - 2023

N2 - A new concept for light water reactor (LWR) nuclear fuel has recently been proposed that utilizes pellets of tristructural isotropic (TRISO) fuel particles embedded in a SiC or zirconium alloy matrix, replacing sintered urania pellets. The fuel is considered significantly more accident tolerant than urania as the SiC matrix or coated/protected zirconium alloy and TRISO particles would be highly resistant to oxidation and fission product release under beyond-design-basis accident conditions. As is well understood, failed fuel rods release gaseous and volatile fission products, and that is greatly exacerbated as urania oxidizes from UO2+x to higher oxidations states in failed fuel pin with resulting expansion, loss of integrity, and significant further release of fission products.

AB - A new concept for light water reactor (LWR) nuclear fuel has recently been proposed that utilizes pellets of tristructural isotropic (TRISO) fuel particles embedded in a SiC or zirconium alloy matrix, replacing sintered urania pellets. The fuel is considered significantly more accident tolerant than urania as the SiC matrix or coated/protected zirconium alloy and TRISO particles would be highly resistant to oxidation and fission product release under beyond-design-basis accident conditions. As is well understood, failed fuel rods release gaseous and volatile fission products, and that is greatly exacerbated as urania oxidizes from UO2+x to higher oxidations states in failed fuel pin with resulting expansion, loss of integrity, and significant further release of fission products.

KW - 73 NUCLEAR PHYSICS AND RADIATION PHYSICS

U2 - 10.2172/1553394

DO - 10.2172/1553394

M3 - Technical Report

CY - United States

ER -

Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N and Thermomechanics

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Keywords

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