SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln

被引：30

作者：

Benson, Michael T. ^{[1
]}

King, James A. ^{[1
]}

Mariani, Robert D. ^{[1
]}

Marshall, M. Craig ^{[1
]}

机构：

[1] Idaho Natl Lab, POB 1625,MS 6188, Idaho Falls, ID 83415 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2017年 / 494卷

关键词：

Metallic fuel; FCCI; Fuel additive; CLADDING CHEMICAL INTERACTION; DIFFUSION COUPLES; SN SYSTEM; ZR ALLOYS; BEHAVIOR; TIN; REDUCTION; PALLADIUM; NEODYMIUM; PHASES;

D O I：

10.1016/j.jnucmat.2017.07.057

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Tin is being investigated as a potential additive to metallic fuel to control fuel-cladding chemical interaction (FCCI). A primary cause of FCCI is the lanthanide fission products moving to the fuel periphery and interacting with the cladding. This interaction will lead to wastage of the cladding and eventually to a cladding breach. The current study is a scanning electron microscopy (SEM) characterization of as-cast and annealed U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln, where Ln = 53Nd-25Ce-16Pr-6La. The present study shows that tin preferentially binds the lanthanides, which will prevent lanthanide migration and interaction with the cladding. (C) 2017 Elsevier B.V. All rights reserved.

引用

页码：334 / 341

页数：8

共 29 条

[1] Thermophysical investigations of the uranium-zirconium alloy system [J].

Ahn, Sangjoon ;

Irukuvarghula, Sandeep ;

McDeavitt, Sean M. .

JOURNAL OF ALLOYS AND COMPOUNDS, 2014, 611 :355-362

[2] Microstructural evaluation of U-rich U-Zr alloys under near-equilibrium condition [J].

Basak, Chandra Bhanu .

JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (03) :280-287

[3]

Benson M.T., UNPUB

[4] A CONTRIBUTION TO THE STUDY OF THE ALLOYING BEHAVIOR OF THE RARE-EARTHS WITH TIN [J].

BORZONE, G ;

BORSESE, A ;

FERRO, R .

ZEITSCHRIFT FUR ANORGANISCHE UND ALLGEMEINE CHEMIE, 1983, 501 (06) :199-208

[5] ON THE ALLOYING BEHAVIOR OF CERIUM WITH TIN [J].

BORZONE, G ;

BORSESE, A ;

FERRO, R .

JOURNAL OF THE LESS-COMMON METALS, 1982, 85 (02) :195-203

[6] Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins [J].

Carmack, W. J. ;

Chichester, H. M. ;

Porter, D. L. ;

Wootan, D. W. .

JOURNAL OF NUCLEAR MATERIALS, 2016, 473 :167-177

[7] Reduction of FCCI effects in lanthanide-iron diffusion couples by doping with palladium [J].

Egeland, G. W. ;

Mariani, R. D. ;

Hartmann, T. ;

Porter, D. L. ;

Hayes, S. L. ;

Kennedy, J. R. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 440 (1-3) :178-192

[8] Reducing fuel-cladding chemical interaction: The effect of palladium on the reactivity of neodymium on iron in diffusion couples [J].

Egeland, G. W. ;

Mariani, R. D. ;

Hartmann, T. ;

Porter, D. L. ;

Hayes, S. L. ;

Kennedy, J. R. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 432 (1-3) :539-544

[9] DIMORPHISM OF LA5SN3, CE5SN3 AND PR5SN3 COMPOUNDS [J].

FRANCESCHI, E .

JOURNAL OF THE LESS-COMMON METALS, 1979, 66 (02) :175-181

[10] SEPARATION AND RECOVERY OF URANIUM METAL FROM SPENT LIGHT WATER REACTOR FUEL VIA ELECTROLYTIC REDUCTION AND ELECTROREFINING [J].

Herrmann, S. D. ;

Li, S. X. .

NUCLEAR TECHNOLOGY, 2010, 171 (03) :247-265

← 1 2 3 →