EXPERIMENTAL STUDIES OF U-PU-ZR FAST-REACTOR FUEL-PINS IN THE EXPERIMENTAL BREEDER REACTOR-II

被引：85

作者：

PAHL, RG ^{[1
]}

PORTER, DL ^{[1
]}

LAHM, CE ^{[1
]}

HOFMAN, GL ^{[1
]}

机构：

[1] ARGONNE NATL LAB,ARGONNE,IL 60439

来源：

METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE | 1990年 / 21卷 / 07期

关键词：

D O I：

10.1007/BF02647233

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Argonne National Laboratory's Integral Fast Reactor (IFR) concept has been under demonstration in the Experimental Breeder Reactor II (EBR-II) since February 1985. Irradiation tests of U-Zr and U-Pu-Zr fuel pins to >15 at. pct burnup have demonstrated their viability as driver fuel prototypes in innovative design liquid metal reactors. A number of technically challenging irradiation effects have been observed and are now under study. Microstructural changes in the fuel are dominated early in exposure by grain boundary cavitation and fission gas bubble growth, producing large amounts of swelling. Irradiation creep and swelling of the austenitic (D9) and martensitic (HT-9) candidate cladding alloys have been measured and correlate well with property modeling efforts. Chemical interaction between the fuel and cladding alloys has been characterized to assess the magnitude of cladding wastage during steady-state irradiation. Significant interdiffusion of the uranium and zirconium occurs producing metallurgically distinct zones in the fuel.

引用

页码：1863 / 1869

页数：7

共 11 条

[1]

BILLONE MC, 1987, UNPUB

[2]

BILLONE MC, 1986, P INT C RELIABLE FUE, P5

[3]

Burris L., 1988, Transactions of the American Nuclear Society, V56, P68

[4]

FOX GL, 1986, P INT C RELIABLE FUE, P5

[5]

GRUBER EE, 1988, UNPUB

[6]

KEISER DD, 1988, THESIS U IDAHO MOSCO

[7]

O'Boyle D. R., 1970, 4TH P INT C PLUT OTH, P720

[8]

PORTER DL, 1986, P INT C REL FUELS LI, P4

[9]

RIGGS KR, 1965, MCW1491 TID4500

[10]

TILL CE, 1986, P AM POWER C, V48, P688

← 1 2 →