This paper describes experimental analyses using the SIMMER-III computer code, which were precedently carried out to give boundary conditions for the integral verification of the new COMPASS code, which is based on MPS method. Two topics of key phenomena in core disruptive accidents were presented in this paper: molten fuel freezing and dispersion; and boiling behavior of molten fuel pool. Related experimental database are reviewed to select appropriate experiments. To analyze the fuel freezing behavior, the GEYSER out-of-pile and the CABRI-EFM1 in-pile experiments were selected. The SIMMER-III calculations were in good agreement with fuel penetration lengths measured in a series of the GEYSER experiments. The fuel freezing behavior in the CABRI-EFM1 experiment was also reasonably simulated by SIMMER-III. The boiling pool consisting principally of molten fuel/steel mixtures is characterized by the heat transfer between fuel and steel. The CABRI-TPA2 experiment has suggested low transient heat flux from fuel to steel due to a steel vapor blanketing around a steel droplet. SIMMER-III well simulated the steel boiling behavior observed in the CABRI-TPA2 experiment by applying reduced heat transfer coefficients between fuel and steel. These experimental analyses by SIMMER-III have also identified key processes to be clarified by mesoscopic simulations using the COMPASS code.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4815-9
PROCEEDINGS PAPER
R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS Available to Purchase
Hidemasa Yamano,
Hidemasa Yamano
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Search for other works by this author on:
Yoshiharu Tobita
Yoshiharu Tobita
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Search for other works by this author on:
Hidemasa Yamano
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Yoshiharu Tobita
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Paper No:
ICONE16-48385, pp. 307-314; 8 pages
Published Online:
June 24, 2009
Citation
Yamano, H, & Tobita, Y. "R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Orlando, Florida, USA. May 11–15, 2008. pp. 307-314. ASME. https://doi.org/10.1115/ICONE16-48385
Download citation file:
24
Views
Related Proceedings Papers
Related Articles
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
ASME J of Nuclear Rad Sci (July,2016)
A Modified Correlation for Flow Boiling Heat Transfer in Plate Heat Exchangers
J. Thermal Sci. Eng. Appl (December,2020)
Measurement and Analysis for Rewetting Velocity Under Post-BT Conditions During Anticipated Operational Occurrence of BWR
J. Eng. Gas Turbines Power (October,2010)
Related Chapters
Factors to be Considered
Consensus for the Lay-up of Boilers, Turbines, Turbine Condensors, and Auxiliary Equipment (CRTD-66)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Long.Term Reactivity Change and Control: On.Power Refuelling
Fundamentals of CANDU Reactor Physics