SWELLING BEHAVIOR OF U-PU-ZR FUEL

被引：96

作者：

HOFMAN, GL

PAHL, RG

LAHM, CE

PORTER, DL

机构：

[1] Experimental Breeder Reactor (EBR-11|Division, Argonne National Laboratory, Argonne, 60439, IL

来源：

METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE | 1990年 / 21卷 / 03期

关键词：

D O I：

10.1007/BF02671924

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Recent fast reactor driver fuel tests in the Experimental Breeder Reactor II (EBR-II) have demonstrated good performance of U-Pu-Zr fuel alloys to burnups >15 at. pct. Postirradiation examination of these tests has yielded a large amount of fuel-swelling data and metallographic information. These data show that prior to making contact with the cladding tube, metallic alloy fuel swells rapidly due to its high fission-enhanced creep rate and irradiation growth. Measurements of macroscopic fuel slug growth during the entire fuel pin lifetime can now be understood by properly taking into account the irradiation environment and microstructural changes for the various alloy compositions. It has been determined that fission rate, temperature, and plutonium concentrations influence the observed macroscopic swelling rate. © 1990 The Metallurgical of Society of AIME.

引用

页码：517 / 528

页数：12