skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Effect of fission rate on the microstructure of coated UMo dispersion fuel

Journal Article · · Journal of Nuclear Materials

Compared to previous irradiation experiments containing UMo/Al dispersion fuel plates, the SELENIUM irradiation experiment performed at the SCK.CEN BR2 reactor in 2012 showed an improved plate swelling behavior. However, in the high burn-up area of the plates a significant increase in meat thickness was still measured. The origin of this increase is currently not firmly established, but it is clear from the observed microstructure that the swelling rate still is too high for practical purposes and needs to be reduced. It was stipulated that the swelling occurred at the high burnup areas which are also the high power zones at beginning of life. For that reason, an experiment was proposed to investigate the influence of fission rate (i.e. power) on some of the observed phenomena. For this purpose, a sibling plate to a high power (BOL>470 W/cm(2)) SELENIUM plate was irradiated during four BR2 cycles. The SELENIUM 1a fuel plate was submitted to a local maximum heat flux below 350 W/cm(2), throughout the full irradiation. At the end of the last cycle, the SELENIUM 1a fuel plate reached a maximum local burnup value of close to 75%U-235 compared to 70%U-235 for the SELENIUM high power plates. When comparing to the results on the SELENIUM plates, the non-destructive tests clearly show a continued linear swelling behavior of the low power irradiated fuel plate SELENIUM 1a in the high burn-up region. The influence of the fission rate is also evidenced in the microstructural examination of the fuel showing that there is no formation of interaction layer at the high burn-up region.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA) - Office of Counterterrorism and Counterproliferation
DOE Contract Number:
AC02-06CH11357
OSTI ID:
1436468
Journal Information:
Journal of Nuclear Materials, Vol. 494, Issue C; ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English

Similar Records

Nuclear fuel development based on UMo alloys under irradiation evaluation of LEU U{sub 3}Si{sub 2} - 4.8 gU/cm{sup 3} test fuel
Conference · Tue Jul 15 00:00:00 EDT 2008 · OSTI ID:1436468

Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position
Conference · Thu May 01 00:00:00 EDT 2008 · OSTI ID:1436468

TEM Characterization of U-Mo Irradiated with High-Energy Xe Ions
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1436468

Related Subjects