Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 code
Source abstract
Abstract
Analysis was conducted on the Lift-Off experiment IFA-610.1 in Halden reactor by the FEMAXI-6 code using detailed measured data in the test-irradiation. Fuel center temperature was calculated on the two assumptions, i.e. (1) an enhanced thermal conductance across the pellet-clad bonding layer is maintained during the cladding creep-out by over-pressurization, and (2) the bonding layer is broken by the cladding creep-out, and these results were compared with the measured data to analyze the effect of the creep-out by over-pressure inside the test pin. The measured center temperature rise was higher by a few tens of K than the prediction performed on the assumption (1), though this difference was much smaller than the predicted rise on the assumption (2). Therefore, it is appropriate to attribute the measured center temperature rise to the decrease of effective thermal conductance by irregular re-location of pellet fragments, etc. which was caused by cladding creep-out.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
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References (13)
Show source-provided references
1. S. Beguin, HWR-544, 1998
2. Suzuki · Nucl. Eng. Des. · 2004 · 229 · 110.1016/j.nucengdes.2003.11.017 ↗
3. M. Suzuki, JAERI Data/Code 2000-030, 2000
4. Suzuki · Nucl. Eng. Des. · 2000 · 201 · 9910.1016/S0029-5493(00)00247-8 ↗
5. W. Wiesenack, M. Vankeerberghen, R. Thankappan, HWR-469, 199610.1016/S0167-2940(96)00026-X ↗
6. D. Schrire, A. Kindlund, P. Ekberg, HPR-349/22, 199810.1109/52.605926 ↗
7. D.L. Hagrman, G.A. Reyman, MATPRO-Version11, NUREG/CR-0497, TREE-1280, Rev. 3, 197910.2172/6442256 ↗
8. A.M. Ross, R.L. Stoute, CRFD-1075, 1962, p. 970
9. M.A. McGrath, in: Proceedings of the 2000 International Topical Meeting on LWR Fuel Performance, Park City, USA, 2000
10. K. Une, K. Nogita, S. Kashibe, T. Toyonaga, M. Amaya, in: Proceedings of the International Topical Meeting on LWR Fuel Performance, Portland, USA, 1997, p. 478
11. MATPRO-A, NUREG/CR-6150, 1995
12. W. Wiesenack, V. Hustadnes, HWR-338, 1993
13. M. Uchida, H. Saitou, JAERI-M 93-108, 1993 (in Japanese)10.1557/PROC-334-293 ↗