NEA-0567 CORAN.
CORAN, PWR and BWR Containment Response to LOCA
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| CORAN | NEA-0567/01 | Tested | 24-MAR-1981 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0567/01 | IBM 370/168 | IBM 370/168 |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
Thermodynamic analysis of an entire containment as well as subcompartment analysis due to a LOCA in PWR and BWR containments in lumped parameter form can be performed with the code. Heat transfer to containment structures of plane, cylindrical and/or spherical geometry can be simulated in order to get best estimate results. Mass and energy balances are solved for the subcompartments and the thermodynamic properties are evaluated by an implicit method. One-dimensional quasi-steady flow is assumed.
Thermodynamic analysis of an entire containment as well as subcompartment analysis due to a LOCA in PWR and BWR containments in lumped parameter form can be performed with the code. Heat transfer to containment structures of plane, cylindrical and/or spherical geometry can be simulated in order to get best estimate results. Mass and energy balances are solved for the subcompartments and the thermodynamic properties are evaluated by an implicit method. One-dimensional quasi-steady flow is assumed.
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4. METHOD OF SOLUTION
The set of differential equations is solved by predictor methods of the Adams type with the following algorithms:
a) Core integrator for advancing the solution from step to step.
b) Method for starting the integration.
c) Algorithm for changing the step size.
d) Algorithm for deciding when and by how much to change the step size based on the accuracy requested by the user.
e) Test for stability of the numerical method.
f) Test for accuracy requests which cannot be met because of round- off errors.
g) Automatic selection of the core integrator to fit the characteristics of the problem at hand.
h) Algorithm for obtaining dependent variable values at arbitrary values of independent variable.
i) Algorithm for locating the zeros of arbitrary functions of the variables appearing in the differential equations.
The set of differential equations is solved by predictor methods of the Adams type with the following algorithms:
a) Core integrator for advancing the solution from step to step.
b) Method for starting the integration.
c) Algorithm for changing the step size.
d) Algorithm for deciding when and by how much to change the step size based on the accuracy requested by the user.
e) Test for stability of the numerical method.
f) Test for accuracy requests which cannot be met because of round- off errors.
g) Automatic selection of the core integrator to fit the characteristics of the problem at hand.
h) Algorithm for obtaining dependent variable values at arbitrary values of independent variable.
i) Algorithm for locating the zeros of arbitrary functions of the variables appearing in the differential equations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
Due the variable dimensioning of the code the complexity of the problem is only restricted by the fast memory size.
The array 'A' contains all data necessary for thermodynamic calculations.
Its length is dependent on:
NZ number of subcompartments
NW number of junctions
NP number of variables to be stored for plotting (presently NP=2*NW+4*NZ+1)
ND number of differential equations
ND = 4+NZ for PWR
ND = 4+NZ+2 for BWR
NB number of breaks at the reactor
NV number of value-pairs for mass and energy release rates dimension of A = (6+3*NB*NV+3*NW+23*NZ+4*ND+NP)
The array 'S' contains all information for solution of heat transfer to and conduction inside structures, its length depends on:
NK number of structures to be simulated
NM maximum number of different materials in a structure
NSM maximum number of slabs of a structure dimension of S =
(NK*(23+9*NM+11*NSM))
Due the variable dimensioning of the code the complexity of the problem is only restricted by the fast memory size.
The array 'A' contains all data necessary for thermodynamic calculations.
Its length is dependent on:
NZ number of subcompartments
NW number of junctions
NP number of variables to be stored for plotting (presently NP=2*NW+4*NZ+1)
ND number of differential equations
ND = 4+NZ for PWR
ND = 4+NZ+2 for BWR
NB number of breaks at the reactor
NV number of value-pairs for mass and energy release rates dimension of A = (6+3*NB*NV+3*NW+23*NZ+4*ND+NP)
The array 'S' contains all information for solution of heat transfer to and conduction inside structures, its length depends on:
NK number of structures to be simulated
NM maximum number of different materials in a structure
NSM maximum number of slabs of a structure dimension of S =
(NK*(23+9*NM+11*NSM))
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10. REFERENCES
- F.T.Krogh:
VODQ/SVDQ/DVDQ - Variable Order Integrators for the Numerical
Solution of Ordinary Differential Equations
NPO - 11643
The code CORAN has been applied to experiments of the German Research Programme RS 33 and RS 50. Several unpublished reports are available via the author. Calculations performed for the German Containment Standard Problem No. 1 and its results will be published by the Ministry of Interior of the Federal Republic of Germany.
- F.T.Krogh:
VODQ/SVDQ/DVDQ - Variable Order Integrators for the Numerical
Solution of Ordinary Differential Equations
NPO - 11643
The code CORAN has been applied to experiments of the German Research Programme RS 33 and RS 50. Several unpublished reports are available via the author. Calculations performed for the German Containment Standard Problem No. 1 and its results will be published by the Ministry of Interior of the Federal Republic of Germany.
NEA-0567/01, included references:
- H. Schwan:Containment-Code CORAN (Benutzerhandbuch - in German)
GKSS 78/I/29 (1978)
- H. Schwan:
Analytical Simulation of Containment During LOCA (in German)
GKSS 78/E/36 (1978)
- H. Schwan:
CORAN - A Modular Code for the Analysis of Containments During
LOCA with Heat Sinks (in German)
GKSS 78/E/44 (1978)
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NEA-0567/01
| File name | File description | Records |
|---|---|---|
| NEA0567_01.002 | INFORMATION FILE | 9 |
| NEA0567_01.003 | SOURCE | 1482 |
| NEA0567_01.004 | S.P. INPUT | 167 |
| NEA0567_01.005 | S.P. OUTPUT | 913 |
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- G. Radiological Safety, Hazard and Accident Analysis
- H. Heat Transfer and Fluid Flow
Keywords: BWR reactors, containment, cylinders, heat transfer, loss-of-coolant accident, mass balance, pwr reactors, slabs, spheres, thermodynamics.