contain linkage presentation - relap5-3d

Idaho National Engineering and Environmental Laboratory

SCDAP/RELAP5-3D©

- CONTAIN Linkage

J. L. Rempe and D. L. Knudson


202-GA50119-32

Objective and Outline• Objective

– To discuss motivation and plans for linking SCDAP/RELAP5-3D© with CONTAIN 2.0

• Outline– Motivation for improved SCDAP/RELAP5-3D© -

CONTAIN 2.0 linkage– Existing linkage using PVM and test case results– Proposed improved linkage– Summary


302-GA50119-32

References• OECD/NEA Group of Experts, SOAR on Containment

Thermalhydraulics and Hydrogen Distribution, NEA-CSNI-R-99-16, June 1999.

• SCDAP/RELAP5-3D© Code Development Team, SCDAP/RELAP5-3D© CODE MANUALS, Volumes 1 through 5, INEEL/EXT-02-00589, May 2002.

• Murata, K. K., et al., Code Manual for CONTAIN 2.0: A Computer Code for Nuclear Rector Containment Analysis, NUREG/CR-6533, SAND97-1735, Sandia National Laboratories, December 1997.

• K. A. Smith, Multi-Processor Based Simulation of Degraded Core and Containment Responses, PhD Thesis, The Pennsylvania State University, December 1992.

• Gauntt, Randall, O., et al., MELCOR Computer Code Manuals -User's Manual, NUREG/CR-6119, Rev. 1, Sandia National Laboratories, October 1997.


402-GA50119-32

Linked mechanistic vessel/containment response analysis tool important for advanced reactors.

• Increased dependence on passive systems – ERVC– IRWST– PCCS

• Requires analyses with increased fidelity in heat and mass transfer between RCS and containment

Motivation

Containmentsump

Cavity sump

Cavityclosureplate

Reactorcavity


502-GA50119-32

SCDAP/RELAP5-3D© - CONTAIN linkage provides mechanistic tool for vessel/containment analysis.

Motivation

Thermal hydraulics

Core melting

Release from fuel

Transport in RCS

RCS failure

Concrete interactions

Release from

debris

Transport in containment

Containment loads

Containment performance

Off-site consequences

Integrated Codes

MAAP

MELCOR

Detailed Mechanistic Codes

SCDAP/RELAP5-3D©

VICTORIA CONTAIN

Accident Progression Phenomena

MAAP4-DOSE

MACCS

MACCS


602-GA50119-32

CONTAIN provides mechanistic containment analyses tool.

Motivation

AEROSOLS• Particle size distribution• Material composition• Deposition

FISSION PRODUCTS• Radioisotope inventory• Decay and heating• Release and acceptance

THERMAL HYDRAULICS• Gas and liquid flow• Heat transfer• Thermodynamics• Engineered safety features• Debris fields

Distribution of fission products

Heat to gas,walls, pool

Intercelltransport

Evaporablecoolant

inventory

Deposition/agglomeration

rates

Transport of gas or fission products


702-GA50119-32

CONTAIN provides mechanistic containment analyses tool. (continued)

Motivation

Code Function CONTAIN MELCOR

Transport of Direct Containment Heating (DCH) materials throughout the containment

Mechanistic models Parametric models require user specified transportation

Radiation from corium to containment structures

Yes No

Film flow modeling on structure walls

Yes No

Coupling containment sprays with direct impingement on containment structures

No, but could be added No

Flow solver Advanced hybrid solver that automatically mitigates overmixing and allows stratification.

Flow path approach requiring judicious nodalization to prevent over-mixing

Local time-dependent velocities for calculating convection heat transfer coefficients

Flexible input allowed Difficult to simulate

Inertial impact of aerosols Yes None

Variable solubility of aerosols Yes To be added in MELCOR 1.8.5


802-GA50119-32

User modeling and input influence CONTAIN and MELCOR results.

Motivation

Wide range of MELCOR temperature predictions observed for BMC/VANAM M-3 (ISP 37)

CONTAIN MELCOR


902-GA50119-32

CONTAIN results better matched HDR Test E11.2 data.

MELCOR and CONTAIN results calculated by AEA for ISP 29

Motivation

0

20

40

60

80

100

0 500 1000 1500Time (min)

Tem

pera

ture

(°C

)

Exp

CONTAIN

MELCOR

0.05

0.1

0.15

0.2

0.25

0 500 1000 1500Time (min)

Pre

ssur

e (M

Pa)

Exp

CONTAIN

MELCOR


1002-GA50119-32

CONTAIN results better matched HDR Test E11.2 data. (continued)

MELCOR and CONTAIN results calculated by AEA for ISP 29

Motivation

0

20

40

60

0 500 1000 1500Time (min)

Ste

am c

once

ntra

tion

(vol

%)

Exp

CONTAIN

MELCOR

0

5

10

15

20

-5 0 5 10 15 20 25 30 35 40 45 50Containment height (m) @ 60 minutes after release

Gas

co

nce

ntr

atio

n (

vol

%)

Exp

CONTAIN

MELCOR


1102-GA50119-32

CONTAIN with new hybrid flow solver better matches HDR Test E11.2 data.

Motivation

0

5

10

15

20

25

700 800 900 1000 1100 1200 1300Time (min)

Lig

ht

gas

co

nce

ntr

atio

n

(vo

l %

)

CONTAIN with Hybrid SolverContain with Old SolverExperiment


1202-GA50119-32

Initial SCDAP/RELAP5-CONTAIN PVM linkage completed by PSU.• Used PVM software to link SCDAP/RELAP5/MOD3.0 and

CONTAIN 1.1.

• “Limited” linkage”:– Transfers break flowrates, SRV discharges, pool injection

sources– Heat transfer from selected structures– Instantaneous flowrates, rather than integrated flowrates– Doesn’t transfer non-condensable gases (hydrogen), fission

products, aerosols, or discharged corium

• Demonstrated capabilities by analyzing Brown’s Ferry ATWS

Existing Linkage


1302-GA50119-32

Calculation results illustrate feasibility and importance of linkage.• Fully linked

– Coupled with PVM software

• Stand-alone– SCDAP/RELAP5 containment conditions taken from CONTAIN

input deck and assumed to remain constant; – SCDAP/RELAP5 output entered as tabular data into CONTAIN

Existing Linkage


1402-GA50119-32

Similar reactor power results predicted by linked and stand-alone SCDAP/RELAP5.

Existing Linkage

0.00

0.05

0.10

0.15

0 600 1200 1800Time (s)

Inte

gra

ted

rea

cto

r p

ow

er

(x 1

013 J

)

Fully-linked

Stand-alone


1502-GA50119-32

Linked code predicts higher LPCI flow into RCS.

0.E+00

1.E+05

2.E+05

3.E+05

4.E+05

0 600 1200 1800Time (s)

Inte

gra

ted

LP

CI f

low

(kg

)

Fully-linked

Stand-alone


1602-GA50119-32

Linked code predicts higher containment temperatures and pressures.

More defensible vessel/containment response achievable through fully-linked analysis.

320

330

340

350

360

370

380

390

400

410

420

0 500 1000 1500 2000Time (s)

Tem

per

atu

re (

K)

Fully-coupled

Stand-alone

0

0.1

0.2

0.3

0.4

0.5

0.6

0 500 1000 1500 2000Time (s)

Pre

ssur

e (M

Pa)

Fully-coupled

Stand-alone


1702-GA50119-32

Proposed PVM linkage will improve upon previous linkage efforts.• Integrate SCDAP/RELAP5-3D© and CONTAIN 2.0 codes

using PVM software and Executive Program

• Use insights gained from previous linkage efforts:– Relative time for calculations to advance (and relative

timestep)– Form of variables for data transfer (enthalpy and mass

flowrate)– Subroutines selected for extracting and receiving data– Review previous coding and improve, as needed

• Compare advanced reactor plant analysis with and without integrated code– AP600 analysis performed for DVI “3BE” LOCA

scenario


1802-GA50119-32

Proposed PVM linkage will improve upon previous linkage efforts. (continued)

KINETICS CODE

SCDAP/RELAP5-3D

CFD CODE

CONTAIN

EXECUTIVE PROGRAM

Edit ControlTime Step ControlSemi-implicitAsynchronousSynchronous


1902-GA50119-32

Summary• SCDAP/RELAP5-3D© and CONTAIN embody state-

of-the-art thermal-hydraulic and severe accident models for mechanistic analyses

• SCDAP/RELAP5-3D© and CONTAIN results consistently serve as reference for comparison

• Proposed PVM linkage of SCDAP/RELAP5-3D© and CONTAIN 2.0 will provide a state-of-the-art mechanistic tool needed for coupled vessel / containment analyses

contain linkage presentation - relap5-3d

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