High-density, low-enriched uranium fuel for nuclear research reactors

被引：67

作者：

Keiser, DD ^{[1
]}

Hayes, SL ^{[1
]}

Meyer, MK ^{[1
]}

Clark, CR ^{[1
]}

机构：

[1] Argonne Natl Lab W, Idaho Falls, ID 83403 USA

来源：

JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY | 2003年 / 55卷 / 09期

关键词：

D O I：

10.1007/s11837-003-0031-0

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The objective of the Reduced Enrichment for Research and Test Reactor program is to enable the conversion of test reactors using fuel containing high-enriched uranium to fuel that employs low-enriched uranium. This paper describes the development of this low-enriched fuel, including fabrication, characterization, and testing of the fuel.

引用

页码：55 / 58

页数：4

共 14 条

[1] HAYES SL, P 1999 INT M RED ENR
[2] HAYES SL, 2000, P 2000 INT M RED ENR, P225
[3] HAYES SL, P 1997 INT M RED ENR
[4] CRYSTAL-STRUCTURE STABILITY AND FISSION-GAS SWELLING IN INTERMETALLIC URANIUM-COMPOUNDS
HOFMAN, GL
[J]. JOURNAL OF NUCLEAR MATERIALS, 1986, 140 (03) : 256 - 263
[5] HOFMAN GL, 1994, MAT SCI TECHNOLOGY A, V10, P53
[6] HOFMAN GL, 2003, T 2003 INT TOP M RES, P43
[7] KEISER DD, UNPUB MET MAT T A
[8] Characteristics of U3Si and U3Si2 powders prepared by centrifugal atomization
Kim, KH
Lee, DB
Kim, CK
Kuk, IH
Paik, KW
[J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1997, 34 (12) : 1127 - 1132
[9] Irradiation behavior of U6Mn-Al dispersion fuel elements
Meyer, MK
Wiencek, TC
Hayes, SL
Hofman, GL
[J]. JOURNAL OF NUCLEAR MATERIALS, 2000, 278 (2-3) : 358 - 363
[10] Low-temperature irradiation behavior of uranium-molybdenum alloy dispersion fuel
Meyer, MK
Hofman, GL
Hayes, SL
Clark, CR
Wiencek, TC
Snelgrove, JL
Strain, RV
Kim, KH
[J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 304 (2-3) : 221 - 236

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