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NEA-0671 NORCOOL.

NORCOOL, BWR LOCA Analysis with Thermal Non-Equilibrium and Counter Current Flow

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1. NAME OR DESIGNATION OF PROGRAM:  NORCOOL.
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2. COMPUTERS
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Program name Package id Status Status date
NORCOOL-I NEA-0671/02 Tested 14-JAN-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0671/02 CDC CYBER 174 CDC CYBER 174
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3. DESCRIPTION OF PROBLEM OR FUNCTION

NORCOOL-I is a model for the behaviour of a BWR under LOCA conditions, and is a result of a joint Nordic cooperation. It contains a simplified, fixed geometry model of a BWR, models for the heat conduction in the fuel rods and  the structural materials, and for the two-phase flow.
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4. METHOD OF SOLUTION

The model for the two-phase flow consists of a  model for the continuous water region (single phase water and bubbly flow) and a model for the dispersed annular flow region. Each of the models is based on a one-dimensional, separate description of the phases, which allows for thermal non-equilibrium and counter current flow, and a special tracing of the two-phase level between the two regions is performed.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

NEA-DB executed the test case on CDC CYBER 174 without segmentation  in 272 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-0671/02 14-JAN-1982 Tested at NEADB
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10. REFERENCES:
NEA-0671/02, included references:
- Poul Astrup:
  NORCOOL-I. A Programme for Analysis of BWR Emergency Core Cooling
  by Top Spray and Reflooding. Input Description. NORHAV-D-82 (3/81)
- N. Bech:
  Numerical Methods for the Hydrodinamic Equations used in the
  Reflood Part of NORCOOL-I.  NORHAV-D-63 (March 1978, Rev. 3/1983)
- J.G. Munthe Andersen et al.:
  A Model for Analysis of a BWR under LOCA Conditions Part II.
  Program Description.  NORHAV-D-33  (October 1977)
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11. MACHINE REQUIREMENTS

Main storage (CDC CYBER 174): 275,000 octal words (no segmentation)
                              257,000 octal words (segmentation).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0671/02 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NOS Level 501 (CDC CYBER 174).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

      Risoe National Laboratory
      DK-4000 Roskilde
      Denmark
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16. MATERIAL AVAILABLE
NEA-0671/02
File name File description Records
NEA0671_02.002 INFORMATION 54
NEA0671_02.003 NORCOOL-I SOURCE 20756
NEA0671_02.004 NORCOOL-I JCL FOR TEST CASE 1 + SEG. CARDS 52
NEA0671_02.005 NORCOOL-I INPUT FOR TEST CASE 1 188
NEA0671_02.006 NORCOOL-I OUTPUT OF TEST CASE 1 4689
NEA0671_02.007 NORLIN SOURCE (F4,AUX. OF NORCOOL-I) 614
NEA0671_02.008 NORLIN JCL FOR TEST CASE 2 10
NEA0671_02.009 NORLIN INPUT FOR TEST CASE 2 188
NEA0671_02.010 NORLIN OUTPUT OF TEST CASE 2 464
NEA0671_02.011 NORDIM1 SOURCE (F4,AUX. OF NORCOOL-I) 848
NEA0671_02.012 NORDIM1 JCL FOR TEST CASE 3 14
NEA0671_02.013 NORDIM1 INPUT FOR TEST CASE 3 188
NEA0671_02.014 NORDIM1 OUTPUT OF TEST CASE 3 300
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, bubble growth, convection, counter current, heat transfer, loss-of-coolant accident, radiation heat, two-phase flow.