last modified: 15-FEB-1990 | catalog | categories | new | search |

NEA-1169 HORN.

HORN, Fission Products Transport in Primary Coolant System of BWR and PWR in LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  HORN.
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2. COMPUTERS
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Program name Package id Status Status date
HORN NEA-1169/01 Tested 15-FEB-1990

Machines used:

Package ID Orig. computer Test computer
NEA-1169/01 FACOM M-380 IBM 3083
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3. DESCRIPTION OF PROGRAM OR FUNCTION

HORN analyzes the transport of  airbone fission products (either gaseous or aerosol) in dry primary  cooling circuit during severe accidents of LWRs.
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4. METHOD OF SOLUTION

The central part of the code is a subcode for solid-gas chemical equilibrium (separately published as MPEC2). The  results of this subcode, concentrations of gaseous or condensed chemical species, are used for mass transport calculation with simple empirical correlations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  The maximum number of control volumes is 50.
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6. TYPICAL RUNNING TIME

The running time was 24 second for a case in  which the flow path was divided into eight and the number of time steps was 60 (for a phenomenon lasting for 300 s).
NEA-1169/01
The test case included in this package ran at NEADB on  an IBM 3083 computer in 205 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

The code considers the chemical forms of seven relatively volatile fission products: Cs, I, Te, Ag,  Cd, Sb and Ba. Because of the fundamental assumption of instantaneous chemical equilibrium, the system must be analyzed at high temperature.
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8. RELATED AND AUXILIARY PROGRAMS

The principal subcode NEK for chemical equilibrium is published as an independent code MPEC2 (with slight modifications).
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9. STATUS
Package ID Status date Status
NEA-1169/01 15-FEB-1990 Tested at NEADB
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10. REFERENCES:
NEA-1169/01, included references:
- M. Uchida and H. Saito:
  HORN: A Computer Code to Analyze the Gas-Phase Transport of
  Fission Products in Reactor Cooling System Under Severe Accidents.
  JAERI-M 86-158  (November 1986)
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11. MACHINE REQUIREMENTS

None.
NEA 1169/01: To run the test case included in this package on an IBM 3083 computer, 1392K bytes of main storage are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1169/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The code uses in  several parts a manufacturer-supplied subroutine GAUELD. GAUELD is a subroutine that solves a set of simultaneous arithmetic equations by the Gauss elimination method.
NEA-1169/01
MVS/XA (IBM 3083) with compiler VS FORTRAN Level 2.3.0.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
No particular restrictions or unusual features.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          Masaaki UCHIDA
          Department of Fuel Safety Research
          Tokai Research Establishment
          Japan Atomic Energy Research Establishment
          Tokai-mura, Naka-gun, Ibaraki-ken, JAPAN

          Hiroaki SAITO
          Century Research Center Corporation
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16. MATERIAL AVAILABLE
NEA-1169/01
File name File description Records
NEA1169_01.001 Information file 101
NEA1169_01.002 HORN source file 6508
NEA1169_01.003 GAUELD simulation routine 143
NEA1169_01.004 Sample data 46
NEA1169_01.005 JCL used at Data Bank 15
NEA1169_01.006 Sample output by Data Bank 3976
NEA1169_01.007 Sample output by the author 1121
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, accidents, chemical reactions, coolant loops, fission products, loss-of-coolant accident, pwr reactors.