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Presentation on theme: "J. R. WOLF RELAP5-3D PROGRAM MANAGER"— Presentation transcript:

RELAP5-3D AT THE INL RELAP5 International Users Group Meeting and Seminar Salt Lake City, Utah July 25-28 J. R. WOLF RELAP5-3D PROGRAM MANAGER

2 RELAP5-3D History Models transient fluid flow in user-defined thermal-hydraulic networks Most widely used water-cooled nuclear reactor accident analysis code Traces roots back to the very beginning of nuclear power plant simulations Early codes were “node and branch”,RELAPSE1 and RELAP2 True loop analysis capability began in 1970 with RELAP3

3 RELAP Has Had a Continuous History of Development at the INL
T/H codes at INL derived from Bettis FLASH-1 code (1966) RELAP1 through RELAP3 ( ) RELAP4 (1973 – 1981) RELAP5 (1979 – 1995) MOD 0 (1979) MOD 1 (1982) MOD 1.5 (1982) MOD 2 (1985) MOD (1989) MOD 3 (1990) MOD 3.1 (1993) MOD 3.2 (1995) RELAP5-3D (1995 to Present) RELAP5-RT (1997 to Present)

4 FLASH 1966 3 volume system Fill via table Choke flow model
Secondary side as constant heat transfer coefficient HEM field equations Plate fuel, heat in only Explicit numerics Hot Cold Przr

5 RELAPSE-1 RELAP1 1966 Evolved from FLASH (basic leak/fill capability)
Reactor kinetics Control systems 3 Volumes Heat Ex to Rx In Rx Out to Heat Ex Pressurizer Rx Heat added at junction of volume 1 & 2 Models for nucleate and film boiling

6 RELAP-2 Similar “look&feel” of RELAPSE New models Other
07/23/11 RELAP-2 Similar “look&feel” of RELAPSE Same leak/fill capability Same heat transfer 3 volume system New models BWR considerations Bubble separation Introduced steam tables Other 2x faster than RELAPSE Improved stability Ported to other platforms RELAP2 BWR Description

7 RELAP3 1970 Evolved from RELAPSE and RELAP2 20 volumes
BWR applications Trip logic Valves Fill/leak pressure dependent Fuel pins/plates; conduction model Expanded heat transfer models

8 RELAP4 1973 Evolved from RELAP3 100 Volumes True 1-D 2-fluid, slip
N2 field for accum Secondary Network Momentum flux term (dP/dA) & form losses Reflood HT, fuel gap and metal-water Rx Implicit numerics

9 RELAP5 1979 Evolved from RELAP4 “1000” volumes 1-D and X-flow
2-fluid, nonHEM More Trips/Controls Interfacial Momentum Multi-channel/fuel rod model Much expanded models & correlations Semi-Implicit numerics

10 RELAP5-3D 1995 Evolved from RELAP5
Multi-dimensional hydraulics and Rx kinetics Models for Radiation HT & conduction enclosure Fuel/cladding deformation New fluids (Gen IV Rx) Code coupling BPLU numeric solver FORTRAN 90/95

11 RELAP has a Constant History of Added Capability
As new versions of RELAP are developed, capability is greatly increased at the expense of complexity and the need for better computer resources RELAP 1,2,3 3 Equations – mass, energy, and momentum Designed for LBLOCA analysis RELAP4 LBLOCA SBLOCA

12 RELAP has a Constant History of Added Capability (cont.)
RELAP5 MOD 0,1, 1.5 5 Equations - two mass, one energy, and two momentum LBLOCA SBLOCA Semi implicit numerics Operational transients RELAP5 MOD 2, 2.5, 3.0, 3.1, 3.2 6 Equations - two mass, two energy, and two momentum Semi, Nearly implicit numerics Crossflow model CCFL Model Metal water reactions Level tracking model

13 RELAP5 Developers

14 RELAP5-3D ModelingCapability
Single or two-phase flow 1-, 2-, or 3- dimensional flow networks Reactor kinetics – 1-, 2-, or 3-dimensional nodal kinetics model Heat Transfer – conduction, convection, radiation Components – pump, compressor, turbine, valves, phase-separators, accumulators, jet-mixers, and pressurizers Process models – critical flow, abrupt area change, form loss, phase separation at tees Coupling capability to other codes such as CFD through the PVM Executive Control systems Graphical user interface

15 Major Features of RELAP5-3D
6 equations Semi implicit hydrodynamics Nearly implicit hydrodynamics Single or two-phase flow 1-, 2-, or 3- dimensional flow networks Reactor kinetics – 1-, 2-, or 3-dimensional nodal kinetics model Heat Transfer – conduction, convection, radiation Cross Flow model Ability to couple directly to other codes through PVM and the PVM Executive Metal-water interaction model 3D hydro 3D kinetics Additional fluids BPLU solver Simulator capability ECC and ECC mixing models Godunov 2nd order in space boron tracking model Plant and piping components, trips, controls

16 Major Features of RELAP5-3D (cont.)
RELAP5 GUI and ability to link to other GUIs such as SNAP GEN IV heat transfer models Pressurizer spray model Feedwater heater model Radiological model transport 2-D conduction Alternate heat conduction to fluids Compressor model Gas diffusion model

17 26 TOTAL RELAP5-3D Working Fluids
Water (H2O) 1984 light water (H2ON) Heavy Water (D2O) Hydrogen Lithium Potassium Helium Nitrogen Sodium Sodium-Potassium (NaK) Lithium-Lead Ammonia Glycerol Bismuth-Lead 1995 light water (H2O95) Carbon Dioxide New Helium (HeN) New Xenon (XeN) New Helium-New Xenon (HeNXeN) Molten Salt 1 (LiF-BeF2 (FLiBe)) Molten Salt 2 (NaBF4-NaF) Molten Salt 3 (LiF-NaF-KF (FLiNaK)) Molten Salt 4 (NaF-ZrF4) DowThermA R134A Super Critical water Blood Different fluids can exist in thermally-coupled loops

18 Noncondensable Gases in RELAP5-3D
Air Argon Helium Hydrogen Nitrogen Xenon Krypton, SF Oxygen CO2 CO

19 The Graphical User Interface (2. 4
The Graphical User Interface (2.4.2)Facilitates Analysis of Calculated Results Graphical display generated from input data Color scale displays user-selected parameter Point & click plots Replay capability at any speed

20 VERSIONS OF RELAP5-3D RELAP5-3D Version (Current Released version) RELAP5-RT Version 2.4.2 RELAP5-3D Version Beta (Available to current license holders) RELAP5-3D Version (Release date TBD)

FORTRAN 95 Restructuring with FOR_STRUCT  Developmental Assessment  Improved Nodal Kinetics  ANS 2005 Decay Heat Standard  Improved Time Step Control Accuracy Based Thermodynamic Properties

Institutionalized Card 1, Option 3 (Consistent Sound Speed Calculation between Volumes and Junctions when Noncondensables are Present)  Added Card 1 Option 27 to set Theta Velocity in Outermost Ring of Rigid Body Rotation and R-theta Symmetric Problems to 1.0 m/s Added Card 1 Option 29 to allow more Accurate Solution to Momentum Equations for Low Flows  Allow Fluid Interactive Capability for the Working Fluid D2O  Allow Input Options NEW and NEWATH to use all Working Fluids  Added Command Line Argument ‘-stat’ for Run Statistics for Developmental Assessment 2D Heat Conduction Model without Reflood Alternate Heat Structure – Fluid Coupling Model Linux SuSe Platform Capability

Pump Head and Torque Multiplier as a Function of Pressure and Void Fraction CO2 Properties Improvement for Running near and through the Critical Point Improved Compressor Model (Allow Input Negative Flows on Speed Tables, Allow Compressors to Run with Noncondensable Gases)  Allow Efficiency Multiplier (for Type-3 Turbine) using a Control Variable and Turbine Inlet Junction Form Loss Multiplier using a Control Variable Allow PVM Coupled Restart from Uncoupled Runs  Modified PVM Coupling to send any RELAP5-3D Nodal Kinetics Variable instead of the Restricted List of Power, Zone, Heat Structure Average Temperature, etc.

24 RELAP5-3D Applications Wide range of nuclear power reactor applications Many non-nuclear and non nuclear applications Capability to analyze any type of flow and heat transfer phenomena in a piping network

25 Applications of RELAP5-3D
Naval Reactors LWR Safety Analysis AP-600 Nuclear power plant training simulators Licensing code development for INER and MHI Advanced Test Reactor DOE International Nuclear safety Program Cryogenic storage and delivery systems SP-100 nuclear system Municipal steam delivery systems Sodium fast reactors Wide Range of university applications

26 Advanced Reactor Applications
Super Critical Water Reactor Gas Fast Reactor Molten Salt Liquid Metal NGNP

27 GEN IV Advanced Reactor Design Applications
NGNP high temperature gas reactor High Temperature Test Facility Super critical water reactor Gas fast reactor Molten salt Pb-Bi

28 NGNP Advanced Reactor Applications
The foundation for a thermal-hydraulic systems analysis capability directed specifically toward the NGNP has been under development for several years at the INEEL. While the basic physical models in RELAP5-3D have been extensively validated for light water reactors, its applicability to the NGNP design must be demonstrated. A program encompassing validation, experiments, and further code development will accomplish this. High Temperature Test facility and MHTGR calculations RELAP5-3D provides a system-wide analysis capability and FLUENT or STARR CCM+ provides the CFD capability. In-vessel and ex-vessel studies

29 RELAP5-3D Coupled to STAR CCM+ and FLUENT For Detailed Analysis
Upper Plenum RELAP5-3D model Core Balance Of Plant CFD model Lower Plenum

30 GT MHTGR Fluent Calculation

31 RELAP5-3D Licenses and IRUG
RELAP5-3D is copyrighted by BEA Growing membership in IRUG Multiyear commercial and university license agreements being executed BEA continue to improved turn around time for new license requests 138 days in FY’09 compared to 32 days first quarter FY’11 state universities accepting alternative language for venue and applicable law Information about RELAP5 and the International RELAP5 Users Group can be found at

32 Current License Structure
License Costs Depends on type of code desired, source or executable Level of support needed for technical assistance

33 Future RELAP Development
Advanced code development is currently underway Starting a long term project to add uncertainty quantification to RELAP5-3D RELAP6 (Presentation later) RELAP7 (Presentation later)

34 Acknowledgements Bob Martin for material on the early codes and their capability


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