Change of fuel-to-cladding gap width with burn-up in FBR MOX fuel irradiated to high burn-up

被引：21

作者：

Maeda, K ^{[1
]}

Asaga, T ^{[1
]}

机构：

[1] Japan Nucl Cycle Dev Inst, Oarai Engn Ctr, Fuels & Mat Div, Ibaraki 3111393, Japan

来源：

JOURNAL OF NUCLEAR MATERIALS | 2004年 / 327卷 / 01期

关键词：

D O I：

10.1016/j.jnucmat.2004.01.003

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

In order to study the dependence of the gap width change on the burn-up, the fuel-to-cl adding gap widths were investigated by ceramography in a large number of FBR MOX fuel pins irradiated to high burn-up. The dependence of gap widths on the burn-up was closely connected with the formations of JOG (joint oxyde-gaine) and rim structure. The gap widths decreased gradually due to the fuel swelling until similar to30 GWd/t, but beyond this burn-up the dependence showed two different tendencies. With the increase of burn-up, the gap widths decreased due to the increase of fuel swelling in the low fuel temperature region where the rim structure was observed, but they increased in the high fuel temperature region where the JOG rich in Cs and Mo formed in the gap. (C) 2004 Elsevier B.V. All rights reserved.

引用

页码：1 / 10

页数：10

共 50 条

[41] GAMMA-SPECTROMETRIC DETERMINATION OF BURN-UP OF RA REACTOR-FUEL .3. MODEL OF BURN-OUT PROCESS AND A METHOD FOR DETERMINATION OF BURN-UP OF FUEL
BULOVIC, V
MAKSIMOVIC, Z
KRTIL, J
SUSIC, M
[J]. JADERNA ENERGIE, 1977, 23 (12): : 456 - 461
[42] Triton burn-up
Stefanie Reichert
[J]. Nature Physics, 2019, 15 : 622 - 622
[43] Burn-up and Operation Time of Fuel Elements Produced in IPEN
Marin Tondin, Julio Benedito
Madi Filho, Tufic
[J]. XXXIII BRAZILIAN WORKSHOP ON NUCLEAR PHYSICS, 2011, 1351
[44] EFFECT OF UNCERTAINTY OF FUEL BURN-UP KNOWLEDGE ON ITS ECONOMICS
MEYER, K
[J]. KERNENERGIE, 1971, 14 (7-8): : 235 - &
[45] Mechanical property evaluation of high burn-up nuclear fuel cladding using the ring tensile test
Kim, Sun-Ki
Bang, Je-Geon
Kim, Dae-Ho
Yang, Yong-Sik
Song, Kun-Woo
Kim, Do-Sik
[J]. METALS AND MATERIALS INTERNATIONAL, 2009, 15 (04) : 547 - 553
[46] VALMOX: validation of nuclear data for high burn-up MOX fuels
Lance, B
Pilate, S
Jacqmin, R
Santamarina, A
Bernard, D
Verboomen, B
Kuijper, JC
[J]. NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (2-4) : 369 - 378
[47] The fuel behaviour code FUROM and its high burn-up simulation capabilities
Gado, Janos
Griger, Agnes
Kulacsy, Katalin
[J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 327 : 274 - 285
[48] Examination and reactivity studies of the metallic residues of a high burn-up BWR fuel
McNamara, Bruce K.
Buck, Edgar C.
Soderquist, Chuck Z.
Smith, Frances N.
Mausolf, Edward J.
[J]. ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 2014, 248
[49] Phase characterisation of simulated high burn-up UO2 fuel
Cobos, J
Papaioannou, D
Spino, J
Coquerelle, M
[J]. JOURNAL OF ALLOYS AND COMPOUNDS, 1998, 271 : 610 - 615
[50] Determination of the radionuclide composition and burn-up of high-burn-up WWER-1000 fuel by destructive methods
E. R. Petrov
B. A. Bibichev
V. D. Domkin
V. V. Kozharin
N. V. Kurenkov
V. S. Mukhin
Yu. A. Panteleev
[J]. Radiochemistry, 2012, 54 (4) : 379 - 382

← 1 2 3 4 5 →