Home > Research > Publications & Outputs > Raman Studies of Advanced Gas-Cooled Reactor Si...

Electronic data

Links

Text available via DOI:

View graph of relations

Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels

Research output: Contribution to journalJournal article

Published

Standard

Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels. / Wilbraham, Richard James; Rauff-Nisthar, Nadya; Boxall, Colin; Howett, Elizabeth; Hambley, David; Hiezl, Zoltan; Lee, William; Padovani, Christiano.

In: Progress in Nuclear Science and Technology, Vol. 5, 01.11.2018, p. 213-216.

Research output: Contribution to journalJournal article

Harvard

Wilbraham, RJ, Rauff-Nisthar, N, Boxall, C, Howett, E, Hambley, D, Hiezl, Z, Lee, W & Padovani, C 2018, 'Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels', Progress in Nuclear Science and Technology, vol. 5, pp. 213-216. https://doi.org/10.15669/pnst.5.213

APA

Wilbraham, R. J., Rauff-Nisthar, N., Boxall, C., Howett, E., Hambley, D., Hiezl, Z., Lee, W., & Padovani, C. (2018). Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels. Progress in Nuclear Science and Technology, 5, 213-216. https://doi.org/10.15669/pnst.5.213

Vancouver

Author

Wilbraham, Richard James ; Rauff-Nisthar, Nadya ; Boxall, Colin ; Howett, Elizabeth ; Hambley, David ; Hiezl, Zoltan ; Lee, William ; Padovani, Christiano. / Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels. In: Progress in Nuclear Science and Technology. 2018 ; Vol. 5. pp. 213-216.

Bibtex

@article{095412b1e0e9479888a9f5791d247319,
title = "Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels",
abstract = "Analysis of advanced gas-cooled reactor (AGR) simulated used nuclear fuels (SIMFuels) has been carried out using micro-Raman spectroscopy in order to understand the effect lanthanide species (e.g. Nd, Y, Ce), representative of fission products generated during fuel burnup, have on the structure of the UO2 matrix in spent AGR fuel. Results show a decrease in perfect fluorite character with increasing burnup as well as the development of a broad lattice distortion peak between 500 and 650 cm-1. Peak analysis of this broad band reveals in it comprised of three overlapping peaks at 534 cm-1, 574 cm-1 and 624 cm-1. The peak at 534 cm-1 has been examined and is suggested to be due to a local phonon mode associated with oxygen-vacancy-induced lattice distortion as a result of lanthanide 3+ ion incorporation into the UO2 bulkmatrix.",
keywords = "Raman Microscopy, SIMFuel, advanced gas reactor, uranium dioxide",
author = "Wilbraham, {Richard James} and Nadya Rauff-Nisthar and Colin Boxall and Elizabeth Howett and David Hambley and Zoltan Hiezl and William Lee and Christiano Padovani",
year = "2018",
month = nov
day = "1",
doi = "10.15669/pnst.5.213",
language = "English",
volume = "5",
pages = "213--216",
journal = "Progress in Nuclear Science and Technology",
issn = "2185-4823",

}

RIS

TY - JOUR

T1 - Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels

AU - Wilbraham, Richard James

AU - Rauff-Nisthar, Nadya

AU - Boxall, Colin

AU - Howett, Elizabeth

AU - Hambley, David

AU - Hiezl, Zoltan

AU - Lee, William

AU - Padovani, Christiano

PY - 2018/11/1

Y1 - 2018/11/1

N2 - Analysis of advanced gas-cooled reactor (AGR) simulated used nuclear fuels (SIMFuels) has been carried out using micro-Raman spectroscopy in order to understand the effect lanthanide species (e.g. Nd, Y, Ce), representative of fission products generated during fuel burnup, have on the structure of the UO2 matrix in spent AGR fuel. Results show a decrease in perfect fluorite character with increasing burnup as well as the development of a broad lattice distortion peak between 500 and 650 cm-1. Peak analysis of this broad band reveals in it comprised of three overlapping peaks at 534 cm-1, 574 cm-1 and 624 cm-1. The peak at 534 cm-1 has been examined and is suggested to be due to a local phonon mode associated with oxygen-vacancy-induced lattice distortion as a result of lanthanide 3+ ion incorporation into the UO2 bulkmatrix.

AB - Analysis of advanced gas-cooled reactor (AGR) simulated used nuclear fuels (SIMFuels) has been carried out using micro-Raman spectroscopy in order to understand the effect lanthanide species (e.g. Nd, Y, Ce), representative of fission products generated during fuel burnup, have on the structure of the UO2 matrix in spent AGR fuel. Results show a decrease in perfect fluorite character with increasing burnup as well as the development of a broad lattice distortion peak between 500 and 650 cm-1. Peak analysis of this broad band reveals in it comprised of three overlapping peaks at 534 cm-1, 574 cm-1 and 624 cm-1. The peak at 534 cm-1 has been examined and is suggested to be due to a local phonon mode associated with oxygen-vacancy-induced lattice distortion as a result of lanthanide 3+ ion incorporation into the UO2 bulkmatrix.

KW - Raman Microscopy

KW - SIMFuel

KW - advanced gas reactor

KW - uranium dioxide

U2 - 10.15669/pnst.5.213

DO - 10.15669/pnst.5.213

M3 - Journal article

VL - 5

SP - 213

EP - 216

JO - Progress in Nuclear Science and Technology

JF - Progress in Nuclear Science and Technology

SN - 2185-4823

ER -