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Research Papers

Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver

[+] Author and Article Information
Hiroshi Madokoro

Karlsruhe Institute of Technology,
Hermann-von-Helmholtz-Platz 1,
Eggenstein-Leopoldshafen 76344, Germany
e-mail: hiroshi.madokoro@kit.edu

Alexei Miassoedov, Thomas Schulenberg

Karlsruhe Institute of Technology,
Hermann-von-Helmholtz-Platz 1,
Eggenstein-Leopoldshafen 76344, Germany

Manuscript received June 8, 2018; final manuscript received August 17, 2018; published online January 24, 2019. Assoc. Editor: Walter Ambrosini.

ASME J of Nuclear Rad Sci 5(1), 011017 (Jan 24, 2019) (9 pages) Paper No: NERS-18-1035; doi: 10.1115/1.4041278 History: Received June 08, 2018; Revised August 17, 2018

Due to the recent high interest on in-vessel melt retention (IVR), development of detailed thermal and structural analysis tool, which can be used in a core-melt severe accident, is inevitable. Although RELAP/SCDAPSIM is a reactor analysis code, originally developed for U.S. NRC, which is still widely used for severe accident analysis, the modeling of the lower head is rather simple, considering only a homogeneous pool. PECM/S, a thermal structural analysis solver for the reactor pressure vessel (RPV) lower head, has a capability of predicting molten pool heat transfer as well as detailed mechanical behavior including creep, plasticity, and material damage. The boundary condition, however, needs to be given manually and thus the application of the stand-alone PECM/S to reactor analyses is limited. By coupling these codes, the strength of both codes can be fully utilized. Coupled analysis is realized through a message passing interface, OpenMPI. The validation simulations have been performed using LIVE test series and the calculation results are compared not only with the measured values but also with the results of stand-alone RELAP/SCDAPSIM simulations.

Copyright © 2019 by ASME
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References

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Figures

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Fig. 1

Illustration of homogeneous corium pool

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Fig. 2

Illustration of a corium pool with a metal layer above an internally heated oxide layer

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Fig. 3

Execution of coupled analysis system

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Fig. 4

LIVE test facility

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Fig. 5

Nodalization scheme for coupled analysis

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Fig. 6

LIVE-L1: outer wall temperature at 1000 s and 6000 s in the transient phase

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Fig. 7

LIVE-L1: vertical melt pool temperature profile at 0.175m from the center line

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Fig. 8

LIVE-L1: heat flux profile along vessel wall

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Fig. 9

LIVE-L1: wall temperature along vessel wall (7 kW)

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Fig. 10

LIVE-L1: crust thickness along inner wall

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Fig. 11

LIVE-L7V: heat balance

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Fig. 12

LIVE-L7V: heat flux profile along vessel wall

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Fig. 13

LIVE-L6: vertical melt pool temperature profile at 0.175m from the center line

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Fig. 14

LIVE-L6: heat flux profile along vessel wall

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Fig. 15

LIVE-L6: wall temperature along vessel wall (18 kW)

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Fig. 16

LIVE-L6: crust thickness along inner vessel

Tables

Errata

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