Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels

Kazuhiro Nogita, Katsumi Une

Research output: Contribution to journalArticle

Abstract

Thermal recovery of radiation defects and microstructural change in UO2 fuels irradiated under LWR conditions (burnup : 25 and 44 GWd/t) have been studied after annealing at temperature range of 4501, 800°C by X-ray diffractometry and transmission electron microscopy (TEM). The lattice parameter of as-irradiated fuels increase with higher burnup, which was mainly due to the accumulation of fission induced point defects. The lattice parameter for both fuels began to recover around 450∼650°C with one stage and was almost completely recovered by annealing at 850°C for 5 h. Based on the recovery of broadening of X-ray reflections and TEM observations, defect clusters of dislocations and small intragranular bubbles began to recover around 1,150∼1,450°C. Complete recovery of the defect clusters, however, was not found even after annealing at 1, 800°C for 5 h. The effect of irradiation temperature on microstructural change of sub-grain structure in high burnup fuels was assessed from the experimental results.

Original languageEnglish
Pages (from-to)900-910
Number of pages11
Journaljournal of nuclear science and technology
Volume30
Issue number9
DOIs
Publication statusPublished - Jan 1 1993

Fingerprint

recovery
Radiation
Recovery
Defects
defects
radiation
Annealing
Lattice constants
annealing
lattice parameters
Transmission electron microscopy
transmission electron microscopy
Crystal microstructure
Point defects
point defects
X ray diffraction analysis
fission
x rays
bubbles
Irradiation

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

Cite this

Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels. / Nogita, Kazuhiro; Une, Katsumi.

In: journal of nuclear science and technology, Vol. 30, No. 9, 01.01.1993, p. 900-910.

Research output: Contribution to journalArticle

@article{30a556cf34fe4a889b9a813512964126,
title = "Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels",
abstract = "Thermal recovery of radiation defects and microstructural change in UO2 fuels irradiated under LWR conditions (burnup : 25 and 44 GWd/t) have been studied after annealing at temperature range of 4501, 800°C by X-ray diffractometry and transmission electron microscopy (TEM). The lattice parameter of as-irradiated fuels increase with higher burnup, which was mainly due to the accumulation of fission induced point defects. The lattice parameter for both fuels began to recover around 450∼650°C with one stage and was almost completely recovered by annealing at 850°C for 5 h. Based on the recovery of broadening of X-ray reflections and TEM observations, defect clusters of dislocations and small intragranular bubbles began to recover around 1,150∼1,450°C. Complete recovery of the defect clusters, however, was not found even after annealing at 1, 800°C for 5 h. The effect of irradiation temperature on microstructural change of sub-grain structure in high burnup fuels was assessed from the experimental results.",
author = "Kazuhiro Nogita and Katsumi Une",
year = "1993",
month = "1",
day = "1",
doi = "10.3327/jnst.30.900",
language = "English",
volume = "30",
pages = "900--910",
journal = "Journal of Nuclear Science and Technology",
issn = "0022-3131",
publisher = "Atomic Energy Society of Japan",
number = "9",

}

TY - JOUR

T1 - Thermal Recovery of Radiation Defects and Microstructural Change in Irradiated UO2 Fuels

AU - Nogita, Kazuhiro

AU - Une, Katsumi

PY - 1993/1/1

Y1 - 1993/1/1

N2 - Thermal recovery of radiation defects and microstructural change in UO2 fuels irradiated under LWR conditions (burnup : 25 and 44 GWd/t) have been studied after annealing at temperature range of 4501, 800°C by X-ray diffractometry and transmission electron microscopy (TEM). The lattice parameter of as-irradiated fuels increase with higher burnup, which was mainly due to the accumulation of fission induced point defects. The lattice parameter for both fuels began to recover around 450∼650°C with one stage and was almost completely recovered by annealing at 850°C for 5 h. Based on the recovery of broadening of X-ray reflections and TEM observations, defect clusters of dislocations and small intragranular bubbles began to recover around 1,150∼1,450°C. Complete recovery of the defect clusters, however, was not found even after annealing at 1, 800°C for 5 h. The effect of irradiation temperature on microstructural change of sub-grain structure in high burnup fuels was assessed from the experimental results.

AB - Thermal recovery of radiation defects and microstructural change in UO2 fuels irradiated under LWR conditions (burnup : 25 and 44 GWd/t) have been studied after annealing at temperature range of 4501, 800°C by X-ray diffractometry and transmission electron microscopy (TEM). The lattice parameter of as-irradiated fuels increase with higher burnup, which was mainly due to the accumulation of fission induced point defects. The lattice parameter for both fuels began to recover around 450∼650°C with one stage and was almost completely recovered by annealing at 850°C for 5 h. Based on the recovery of broadening of X-ray reflections and TEM observations, defect clusters of dislocations and small intragranular bubbles began to recover around 1,150∼1,450°C. Complete recovery of the defect clusters, however, was not found even after annealing at 1, 800°C for 5 h. The effect of irradiation temperature on microstructural change of sub-grain structure in high burnup fuels was assessed from the experimental results.

UR - http://www.scopus.com/inward/record.url?scp=85007758041&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85007758041&partnerID=8YFLogxK

U2 - 10.3327/jnst.30.900

DO - 10.3327/jnst.30.900

M3 - Article

AN - SCOPUS:85007758041

VL - 30

SP - 900

EP - 910

JO - Journal of Nuclear Science and Technology

JF - Journal of Nuclear Science and Technology

SN - 0022-3131

IS - 9

ER -