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NESC0529 ANVENT

ANVENT, Temperature Distribution and Pressure in Containment and Ice Condenser after LOCA for LWR

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1. NAME OR DESIGNATION OF PROGRAM:  ANVENT
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2. COMPUTERS
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Program name Package id Status Status date
ANVENT NESC0529/01 Tested 01-MAY-1974

Machines used:

Package ID Orig. computer Test computer
NESC0529/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

The   ANVENT    program   was
developed to analyze thermal effects of a loss-of-coolant accident
(LOCA) in  a Westinghouse ice  condenser nuclear unit,  similar to
the Duke Power Company's McGuire units.  The program is capable of
evaluating  (1)  steady-state   radial  temperature  distributions
corresponding to fixed inside and outside temperatures, (2) radial
temperature distributions in  the steel containment shell  and the
concrete reactor (shield) building during the post-LOCA transient,
(3)  temperature   and  pressure  in   the  annulus   between  the
containment  shell  and  reactor  building  during  the  post-LOCA
transient, and  (4) capability of  the annulus ventilation  fan to
quickly attain and  maintain a vacuum in the annulus  after a LOCA
occurs.
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4. METHOD OF SOLUTION

The system is divided into three regions-- an
upper region,  a lower  region, and the  middle, or  ice condenser
region.  Finite difference  equations are solved to  determine the
temperatures  at  various  nodes for  both  the  steady-state  and
transient condition.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The model is  one-
dimensional  with  heat  transfer occurring  only  in  the  radial
direction.  All physical properties are independent of temperature
except the  density of the annulus  air which behaves as  an ideal
gas and exists  uniformly at its mean mixed  temperature.  The air
in the annulus has a transmissivity of 1.  Radiative heat transfer
occurs  between  the  concrete  reactor  building  and  the  steel
containment  building.  Circulation  of refrigerating  air in  the
ice-condenser  air ducts  ceases at  the initiation  of the  LOCA.
Leakage of air  across the concrete reactor building  or the steel
containment shell is negligible.   Thermal contact resistances are
neglected.
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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:
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9. STATUS
Package ID Status date Status
NESC0529/01 01-MAY-1974 Tested at NEADB
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10. REFERENCE:
NESC0529/01, included references:
- R.S. Krell and J.L. Kelly:
  ANVENT Annulus Ventilation Program for Westinghouse Ice-Condenser
  Nuclear Unit
  Duke Power Company Program Description (December 3, 1971).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0529/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:    GE635 MARK  2
Time-Sharing System.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

                 J. L. Kelly and R. S. Krell
                 Duke Power Company
                 422 South Church Street
                 Charlotte, North Carolina  28201
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16. MATERIAL AVAILABLE
NESC0529/01
File name File description Records
NESC0529_01.001 SOURCE PROGRAM (F4) 443
NESC0529_01.002 SAMPLE INPUT 16
NESC0529_01.003 OUTPUT LIST OF SAMPLE PROBLEM 294
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, coolants, heat transfer, reactor safety.