Swelling behavior of U-Pu-Zr fuel

Gerard L. Hofman; R. G. Pahl; C. E. Lahm; D. L. Porter

doi:10.1007/BF02671924

Swelling behavior of U-Pu-Zr fuel

Gerard L. Hofman
, R. G. Pahl
, C. E. Lahm
, D. L. Porter

Research output: Contribution to journal › Article › peer-review

135 Scopus citations

Abstract

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.

Original language	English
Pages (from-to)	517-528
Number of pages	12
Journal	Metallurgical Transactions A
Volume	21
Issue number	2
DOIs	https://doi.org/10.1007/BF02671924
State	Published - Feb 1990
Externally published	Yes

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10.1007/BF02671924

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title = "Swelling behavior of U-Pu-Zr fuel",

abstract = "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.",

author = "Hofman, \{Gerard L.\} and Pahl, \{R. G.\} and Lahm, \{C. E.\} and Porter, \{D. L.\}",

year = "1990",

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T1 - Swelling behavior of U-Pu-Zr fuel

AU - Hofman, Gerard L.

AU - Pahl, R. G.

AU - Lahm, C. E.

AU - Porter, D. L.

PY - 1990/2

Y1 - 1990/2

N2 - 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.

AB - 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.

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DO - 10.1007/BF02671924

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VL - 21

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JO - Metallurgical Transactions A

JF - Metallurgical Transactions A

IS - 2

ER -

Swelling behavior of U-Pu-Zr fuel

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