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NEA-0631 CLAPTRAP.

CLAPTRAP, Pressure Transients in LWR Containment During LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  CLAPTRAP.
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2. COMPUTERS
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Program name Package id Status Status date
CLAPTRAP NEA-0631/01 Tested 01-MAY-1980

Machines used:

Package ID Orig. computer Test computer
NEA-0631/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

CLAPTRAP calculates pressure transients in total containments enclosing a breached water reactor  circuit. It allows for:

- The influx of steam-water mass and enthalpy from a breach  (alternatively as an option the primary circuit details can be  entered in which case the code will calculate the breach flow and    enthalpy).
-  The heat transfer to complex wall and plant structures.
-  The outleakage.
- Either complete equilibrium between phases or water disposition    without equilibration.
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4. METHOD OF SOLUTION

A finite difference method is used to solve the heat diffusion equation in both slab geometry (a sandwich assembly of materials) and cylindrical geometry (heat diffusion from fuel pins). The isentropic flow conditions are found using the well- known isentropic critical throat pressure relationship. The pressure and quality of a two-phase mixture of steam-water and air is determined iteratively using also a finite difference method. The code has provision for the additional heat supplied by the zirconium/water reaction but not for secondary hydrogen burning.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Six delayed neutron  energy groups are used when determining the delayed neutron heating  as a fraction of the initial power input for a step insertion of reactivity.
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

CLAPTRAP II calculates pressure transients in the interconnected compartments of a total containment enclosing a breached water reactor circuit.

The most important subroutine in CLAPTRAP, CNTN 1, which analyses the pressure transient in a containment containing air with water vapour initially present at a known dewpoint, may be attached to any code which analyses the transient conditions in a breached water circuit, such as RELAP and STEWPOT. STEWPOT enables estimates to be  made of the primary circuit depressurisation characteristics on a loss-of-coolant accident.
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9. STATUS
Package ID Status date Status
NEA-0631/01 01-MAY-1980 Tested at NEADB
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10. REFERENCES

- W. Rettig et al.:
  "RELAP-3 - A Computer Programme for Reactor Blowdown Analysis"
  IN-1321.
- W.H.L. Porter:
  "STEWPOT - A Code for Establishing Conditions in the Primary
  Circuit on Depressurising a Water Reactor"
  AEEW-M1099.
NEA-0631/01, included references:
- W.H.L. Porter:
  "CLAPTRAP - A Code for Calculating Pressure Transients in Total
  Containments Enclosing a Breached Water Reactor Circuit"
  AEEW - R965 (1977).
- W.H.L. Porter:
  "CLAPTRAP II - A Code for Calculating Pressure Transients in the
  Interconnected Compartments of a Total Containment Enclosing a
  Breached Water Reactor Circuit"
  AEEW-R1108 (1977).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0631/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

          W. H. L. Porter
          AEE Winfrith
          Near Dorchester, Dorset
          United Kingdom.
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16. MATERIAL AVAILABLE
NEA-0631/01
File name File description Records
NEA0631_01.001 INFORMATION FILE 5
NEA0631_01.002 SOURCE 2017
NEA0631_01.003 S.P. INPUT 40
NEA0631_01.004 S.P. OUTPUT 6743
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: containment systems, coolant loops, cylinders, diffusion equations, enthalpy, finite difference method, heat transfer, loss-of-coolant accident, mass transfer, pressure, slabs, steam, transients, water, water cooled reactors.