RESULTS OF THERMAL CREEP TEST ON HIGHLY  IRRADIATED ZIRLO

M. QUECEDO; M. LLORET; J. M. CONDE; C. ALEJANO; J.A. GAGO; F.J. FERNANDEZ

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자료유형: 학술저널

저자정보: M. QUECEDO M. LLORET J. M. CONDE C. ALEJANO J.A. GAGO F.J. FERNANDEZ

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제41권 제2호

발행연도: 2009.1

수록면: 179 - 186 (8page)

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This paper presents a thermal creep test under internal pressure and post-test characterization performed on high burnup (68 MWd/kgU) ZIRLO. This research has been done by the CSN, ENRESA, and ENUSA in order to investigate the behavior of advanced cladding materials in contemporary PWRs at higher burnup under dry cask storage conditions. Also, to investigate the hydride reorientation, the cool-down of the samples after the test has been done in a coordinated manner with the internal pressure. The creep results obtained are consistent with the expected behavior from reference CWSR material, Zr-4. During the test, the material retained significant ductility: one specimen leaked during the test at an engineering strain of the tube section of 17%; remarkably, the crack closed due to de-pressurization. Although significant hydride reorientation occurred during the cool-down under pressure, no specimen failed during the cool-down.

#Spent Fuel #ZIRLO #Thermal Creep #High Burnup #Hydride Reorientation #Failure Mechanism

참고문헌 (16)

참고문헌 신청

/ 2003 / US NRC Spent Fuel Office Interim Staff Guidance-11, Revision 3, November 2003

A-M. ALVAREZ-HOLSTON / 2007 / Studies of hydrogen assisted failures initiating at the cladding outer surface of high burn-up fuel using a modified Ring Tensile Technique / Proc. o

C. CAPPELAERE / 2001 / Long Term Behavior of the Spent Fuel Cladding in Dry Storage Conditions / Proc. Int. Conf. on Environmental Management : 188 ~ 194

D. SCHRIRE / 1994 / Scanning Electron Microscope Technique for Studying Zircaloy Corrosion and Hydriding / Zirconium in the Nuclear Industry : Tenth Int. Symposium. ASTM STP 1245

H-U. ZWICKY / 2004 / Isotopic Analysis of Irradiated Fuel Samples in the Studsvik Hotcell Laboratory / Proc. of the 2004 Int. Meeting on LWR Fuel Performance : 1104 ~

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