Abstract
Thermal and fast reactor irradiation experiments on mixed oxide fuel pins under steady-state and power change conditions reveal evidence for significant fuel-cladding mechanical interaction (FCMI) effects. Analytical studies with the LIFE-III fuel performance code indicate that high cladding stresses can be produced by general and local FCMI effects. Also, evidence is presented to show that local cladding strains can be caused by the accumulation of cesium at the fuel-cladding interface. Although it is apparent that steady-state FCMI effects have not given rise to cladding breaches in current fast reactors, it is anticipated that FCMI may become more important in the future because of interest in: higher fuel burnups; increased power ramp rates; load follow operation; and low swelling cladding alloys. (author)
Boltax, A;
[1]
Biancheria, A
- Westinghouse Electric Corporation, Advanced Reactor Division, Madison, PA (United States)
Citation Formats
Boltax, A, and Biancheria, A.
Fuel-cladding mechanical interaction effects in fast reactor mixed oxide fuel.
IAEA: N. p.,
1977.
Web.
Boltax, A, & Biancheria, A.
Fuel-cladding mechanical interaction effects in fast reactor mixed oxide fuel.
IAEA.
Boltax, A, and Biancheria, A.
1977.
"Fuel-cladding mechanical interaction effects in fast reactor mixed oxide fuel."
IAEA.
@misc{etde_20137476,
title = {Fuel-cladding mechanical interaction effects in fast reactor mixed oxide fuel}
author = {Boltax, A, and Biancheria, A}
abstractNote = {Thermal and fast reactor irradiation experiments on mixed oxide fuel pins under steady-state and power change conditions reveal evidence for significant fuel-cladding mechanical interaction (FCMI) effects. Analytical studies with the LIFE-III fuel performance code indicate that high cladding stresses can be produced by general and local FCMI effects. Also, evidence is presented to show that local cladding strains can be caused by the accumulation of cesium at the fuel-cladding interface. Although it is apparent that steady-state FCMI effects have not given rise to cladding breaches in current fast reactors, it is anticipated that FCMI may become more important in the future because of interest in: higher fuel burnups; increased power ramp rates; load follow operation; and low swelling cladding alloys. (author)}
place = {IAEA}
year = {1977}
month = {Apr}
}
title = {Fuel-cladding mechanical interaction effects in fast reactor mixed oxide fuel}
author = {Boltax, A, and Biancheria, A}
abstractNote = {Thermal and fast reactor irradiation experiments on mixed oxide fuel pins under steady-state and power change conditions reveal evidence for significant fuel-cladding mechanical interaction (FCMI) effects. Analytical studies with the LIFE-III fuel performance code indicate that high cladding stresses can be produced by general and local FCMI effects. Also, evidence is presented to show that local cladding strains can be caused by the accumulation of cesium at the fuel-cladding interface. Although it is apparent that steady-state FCMI effects have not given rise to cladding breaches in current fast reactors, it is anticipated that FCMI may become more important in the future because of interest in: higher fuel burnups; increased power ramp rates; load follow operation; and low swelling cladding alloys. (author)}
place = {IAEA}
year = {1977}
month = {Apr}
}