NESC0529 ANVENT
ANVENT, Temperature Distribution and Pressure in Containment and Ice Condenser after LOCA for LWR
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCE, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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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.
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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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.
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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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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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 |
Keywords: accidents, coolants, heat transfer, reactor safety.