Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection

Prasser, Horst-Michael; Grunwald, Gerhard; Höhne, Thomas; Kliem, S.; Rohde, Ulrich L.; Weiß, Frank-Peter

doi:10.13182/nt03-a3396

Cited by 72 publications

(27 citation statements)

References 3 publications

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“…Hot legs #3 and #4 are not affected. Experimental investigations at the ROCOM facility have shown that the temperature perturbation is limited to the faulted loop (8) (9) . The following two figures (Fig.…”

Section: Selected Resultsmentioning

confidence: 99%

Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS

Jaeger

Espinoza

Lischke

2008

JPES

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This study was performed at the Institute of Reactor Safety at the Forschungszentrum Karlsruhe. It is embedded in the ongoing investigations of the international code assessment and maintenance program (CAMP) for qualification and validation of system codes like TRACE(1) and PARCS (2) . The chosen reactor type used to validate these two codes was the Russian designed VVER-1000 because the OECD/NEA VVER-1000 Coolant Transient Benchmark Phase 2 (3) includes detailed information of the Bulgarian nuclear power plant (NPP) Kozloduy unit 6. The post-test investigations of a coolant mixing experiment have shown that the predicted parameters (coolant temperature, pressure drop, etc.) are in good agreement with the measured data. The coolant mixing pattern, especially in the downcomer, has been also reproduced quiet well by TRACE. The coupled code system TRACE/PARCS which was applied on a postulated main steam line break (MSLB) provided good results compared to reference values and the ones of other participants of the benchmark. The results show that the developed three-dimensional nodalization of the reactor pressure vessel (RPV) is appropriate to describe the coolant mixing phenomena in the downcomer and the lower plenum of a VVER-1000 reactor. This phenomenon is a key issue for investigations of MSLB transient where the thermal hydraulics and the core neutronics are strongly linked. The simulation of the RPV and core behavior for postulated transients using the validated 3D TRACE RPV model, taking into account boundary conditions at vessel in-and outlet, indicates that the results are physically sound and in good agreement to other participant's results.

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Section: Selected Resultsmentioning

confidence: 99%

Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS

Jaeger

Espinoza

Lischke

2008

JPES

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“…Extended discussion is provided for a boron dilution validation exercise using experimental results from the ROCOM mixing test facility [13]. As part of the exercise the ECORA Best Practice Guidelines were followed and some special benchmark problems were used to study the impact of turbulence model selection, discretization schemes, boundary conditions, nodalization, and time step size.…”

Section: Modeling Guidelinesmentioning

confidence: 99%

Development of Best Practice Guidelines for CFD in Nuclear Reactor Safety

Mahaffy¹

2010

Nuclear Engineering and Technology

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“…In contrast to the Maryland tests, demineralised water was used in these tests, supplemented by the injection of slugs of a tracer solution (diluted salt) into one loop. The salt concentration was measured by means of wire-mesh sensors [61]. Of these, one was installed in the cold-leg inlet nozzle of the disturbed loop (232 measuring points), two were placed in the downcomer just below the inlet nozzles and before the entrance to the lower plenum (2x232 measuring points), while the fourth sensor was integrated into the lower core support plate, with one measuring position at each fuel element location.…”

Section: Boron Dilutionmentioning

confidence: 99%

Assessment of CFD Codes Used in Nuclear Reactor Safety Simulations

Smith¹

2010

Nuclear Engineering and Technology

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Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection

Cited by 72 publications

References 3 publications

Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS

Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS

Development of Best Practice Guidelines for CFD in Nuclear Reactor Safety

Assessment of CFD Codes Used in Nuclear Reactor Safety Simulations

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