Swelling due to fission products and additives dissolved within the uranium dioxide lattice

被引：36

作者：

Middleburgh, S. C. ^{[1
,2
]}

Grimes, R. W. ^{[1
]}

Desai, K. H. ^{[1
]}

Blair, P. R. ^{[2
]}

Hallstadius, L. ^{[2
]}

Backman, K. ^{[2
]}

Van Uffelen, P. ^{[3
]}

机构：

[1] Univ London Imperial Coll Sci Technol & Med, Dept Mat, Ctr Nucl Engn, London SW7 2AZ, England

[2] Westinghouse Elect Sweden AB, Dept Mat & Fuel Rod Design, Vasteras, Sweden

[3] Commiss European Communities, Joint Res Ctr, D-76344 Eggenstein Leopoldeshafe, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2012年 / 427卷 / 1-3期

关键词：

INERT MATRIX FUEL; GAS RELEASE; UO2; OXIDATION; BEHAVIOR; PROGRAM; STATE; PHASE;

D O I：

10.1016/j.jnucmat.2012.03.037

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Simulations using empirical inter-atomic potentials have been used to predict the change in volume of the uranium dioxide lattice due to the accommodation of soluble fuel additives and fission products. The incorporation of divalent, trivalent and tetravalent cations are considered. The change in accommodation mechanism for aliovalent cations between UO2 and UO2+x gives rise to markedly different defect volumes. Experimental data is in good agreement with the predictions made in this work, particularly swelling as a function of dopant concentration under different conditions. The predicted defect volumes have been combined to predict the change in lattice volume with burnup (fission product inventory) due to incorporation of these soluble species, which agrees well with swelling data from irradiated fuel. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：359 / 363

页数：5

共 33 条

[1] Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide
Cooper, M. W. D.
Middleburgh, Sc
Grimes, R. W.
PROGRESS IN NUCLEAR ENERGY, 2014, 72 : 33 - 37
[2] Fission products stability in uranium dioxide
Brillant, G.
Gupta, F.
Pasturel, A.
JOURNAL OF NUCLEAR MATERIALS, 2011, 412 (01) : 170 - 176
[3] Corrosion of Uranium Dioxide Containing Simulated Fission Products in Dilute Hydrogen Peroxide and Dissolved Hydrogen
Broczkowski, M. E.
Keech, P. G.
Noel, J. J.
Shoesmith, D. W.
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 2010, 157 (08) : C275 - C281
[4] Calculations of solution energies of fission products in uranium dioxide
Grimes, R.W., 1856, Pharmacotherapy Publications Inc. (72):
[5] Calculations of solution energies of fission products in uranium dioxide
Grimes, Robin W., 1856, (72):
[6] THERMODYNAMICS OF THE SYSTEM URANIUM DIOXIDE FISSION PRODUCTS ZIRCALOY
KOHLI, R
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 281 - 282
[7] THE STABILITY OF FISSION-PRODUCTS IN URANIUM-DIOXIDE
GRIMES, RW
CATLOW, CRA
PHILOSOPHICAL TRANSACTIONS OF THE ROYAL SOCIETY A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES, 1991, 335 (1639): : 609 - 634
[8] INVESTIGATIONS ON SWELLING AND FISSION-GAS BEHAVIOR IN URANIUM-DIOXIDE
ZIMMERMANN, H
JOURNAL OF NUCLEAR MATERIALS, 1978, 75 (01) : 154 - 161
[9] FISSION PRODUCTS AND PLUTONIUM MIGRATE IN URANIUM-DIOXIDE FUEL
BATES, JL
ROAKE, WE
CHRISTENSEN, JA
NUCLEONICS, 1962, 20 (03): : 88 - &
[10] CALCULATIONS OF SOLUTION ENERGIES OF FISSION-PRODUCTS IN URANIUM-DIOXIDE
GRIMES, RW
CATLOW, CRA
STONEHAM, AM
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1989, 72 (10) : 1856 - 1860

← 1 2 3 4 →