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

[31] THE BEHAVIOR OF FISSION PRODUCTS CAPTURED IN GRAPHITE POWDER BY NUCLEAR RECOIL .6. THE CHEMICAL STATE OF IODINE-131 DIFFUSED OUT FROM GRAPHITE, URANIUM DIOXIDE AND THORIUM DIOXIDE
YAJIMA, S
SHIBA, K
HANDA, M
BULLETIN OF THE CHEMICAL SOCIETY OF JAPAN, 1963, 36 (03) : 253 - 258
[32] The behavior of uranium and fission products in the processing of model spent nuclear fuel in iron(III) nitrate solutions in the presence of supercritical tributyl phosphate-containing carbon dioxide
Samsonov, M. D.
Trofimov, T. I.
Kulyako, Yu M.
Vinokurov, S. E.
Myasoedov, B. F.
RUSSIAN JOURNAL OF PHYSICAL CHEMISTRY B, 2014, 8 (08) : 1033 - 1037
[33] The behavior of uranium and fission products in the processing of model spent nuclear fuel in iron(III) nitrate solutions in the presence of supercritical tributyl phosphate-containing carbon dioxide
M. D. Samsonov
T. I. Trofimov
Yu. M. Kulyako
S. E. Vinokurov
B. F. Myasoedov
Russian Journal of Physical Chemistry B, 2014, 8 : 1033 - 1037

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