NEA-0705 ALARM-P1.
ALARM-P1, PWR Thermohydraulics for ECCS During Blowdown
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, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ALARM-P1 | NEA-0705/01 | Tested | 22-OCT-1982 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0705/01 | IBM 3033 | IBM 3033 |
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3. DESCRIPTION OF PROBLEM OR FUNCTION
The ALARM-P1 is a part of the code series for evaluation of performance of the emergency core cooling system (ECCS) in pressurized water reactors according to the safety evaluation guidelines provided by the Nuclear Safety Commission of Japan. ALARM-P1 is for analyzing the thermo-hydraulic phenomena during blowdown following a large break in the primary coolant system.
ALARM-P1 models the PWR system fluid condition including flow, pressure, mass inventory, fluid quality and heat transfer. It solves integral forms of fluid conservation and state equations for user-defined volumes treated as one-dimensional homogeneous, thermal-equilibrium elements with interconnecting flow paths and also finite difference forms of the one-dimensional heat conduction equations describing temperature profiles within solid material and the fluid-solid interface conditions.
The ALARM-P1 is a part of the code series for evaluation of performance of the emergency core cooling system (ECCS) in pressurized water reactors according to the safety evaluation guidelines provided by the Nuclear Safety Commission of Japan. ALARM-P1 is for analyzing the thermo-hydraulic phenomena during blowdown following a large break in the primary coolant system.
ALARM-P1 models the PWR system fluid condition including flow, pressure, mass inventory, fluid quality and heat transfer. It solves integral forms of fluid conservation and state equations for user-defined volumes treated as one-dimensional homogeneous, thermal-equilibrium elements with interconnecting flow paths and also finite difference forms of the one-dimensional heat conduction equations describing temperature profiles within solid material and the fluid-solid interface conditions.
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4. METHOD OF SOLUTION
The resulting set of simultaneous equations for fluid conservation is linearized and advanced for a small time increment by a simple explicit numerical technique. The finite differences of the one-dimensional heat conduction equation are linearized and solved by Crank-Nicolson implicit method.
The resulting set of simultaneous equations for fluid conservation is linearized and advanced for a small time increment by a simple explicit numerical technique. The finite differences of the one-dimensional heat conduction equation are linearized and solved by Crank-Nicolson implicit method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
The code is of a variable dimension so the only limit on the size of a problem is the amount of core memory available. The number of control volumes, and the manner in which they are connected, is arbitrary. However, since the fluid flow equation is based on the assumption of one- dimensional flow, the actual arrangement must be viewed in terms of the inherent assumption. A multiconnected flow path should be used only when it can be approximated with one-dimensional flow.
The code should be compiled using no optimization (OPT = 0).
The code is of a variable dimension so the only limit on the size of a problem is the amount of core memory available. The number of control volumes, and the manner in which they are connected, is arbitrary. However, since the fluid flow equation is based on the assumption of one- dimensional flow, the actual arrangement must be viewed in terms of the inherent assumption. A multiconnected flow path should be used only when it can be approximated with one-dimensional flow.
The code should be compiled using no optimization (OPT = 0).
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6. TYPICAL RUNNING TIME
Running time is highly dependent on a problem and is a function of the number of control volumes, flow paths and heat conductors, and the time step size used. For example, the calculation with 31 control volumes, 35 junctions and one heat conductor for the analysis of LOFT L1-4 experiment required the CPU time of about 3.67 hours (0.165 sec/time step) on the FACOM 230-75 computer.
Running time is highly dependent on a problem and is a function of the number of control volumes, flow paths and heat conductors, and the time step size used. For example, the calculation with 31 control volumes, 35 junctions and one heat conductor for the analysis of LOFT L1-4 experiment required the CPU time of about 3.67 hours (0.165 sec/time step) on the FACOM 230-75 computer.
NEA-0705/01
NEA-DB ran the sample case on IBM 3033 in 480 seconds.[ top ]
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NEA-0705/01, included references:
- M. Akimoto et al.:ALARM-P1: A Computer Program for Pressurized Water Reactor
Blowdown Analysis
JAERI-M 8004 (Dec. 1978).
- K. Soda et al.:
Predicition of LOFT L1-4 Experiment - CSNI Standard Problem No. 5
JAERI-M 7329 (Oct. 1977).
- S. Sasaki:
An Analysis of LOFT L1-2 Experiment by ALARM-P1 Computer Code
JAERI-M 7947 (Oct. 1978).
- S. Sasaki et al.:
An Analysis of CSNI Standard Problem No. 8
JAERI-M 8746 (Mar. 1980).
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11. MACHINE REQUIREMENTS
Main storage: 900 kbytes on IBM 3033.
The required auxiliary storage is as follows:
Logical unit 1 disc-scratch
Logical unit 2 input file for restarting
Logical unit 3 output file for restart information
Logical unit 4 output file for graphic information
Logical unit 10 input file for steam table
Main storage: 900 kbytes on IBM 3033.
The required auxiliary storage is as follows:
Logical unit 1 disc-scratch
Logical unit 2 input file for restarting
Logical unit 3 output file for restart information
Logical unit 4 output file for graphic information
Logical unit 10 input file for steam table
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NEA-0705/01
| File name | File description | Records |
|---|---|---|
| NEA0705_01.001 | ALARM-P1 INFORMATION | 122 |
| NEA0705_01.002 | ALARM-P1 SOURCE (FORTRAN-4) | 18977 |
| NEA0705_01.003 | SETPAR SUBROUTINE (FORTRAN-4) | 248 |
| NEA0705_01.004 | BLOCK DATA (ADDITIONAL) | 30 |
| NEA0705_01.005 | SETB99 (REPLACING ENCODE) (ASSEMBLER) | 100 |
| NEA0705_01.006 | ALARM-P1 INPUT FOR TEST CASE 1 | 128 |
| NEA0705_01.007 | ALARM-P1 OUTPUT OF TEST CASE 1 | 2799 |
| NEA0705_01.008 | ALARM-P1 INPUT FOR TEST CASE 2 | 30 |
| NEA0705_01.009 | ALARM-P1 OUTPUT OF TEST CASE 2 | 459 |
| NEA0705_01.010 | PREEDIT SOURCE (FORTRAN-4) | 610 |
| NEA0705_01.011 | PREEDIT INPUT FOR TEST CASE | 4 |
| NEA0705_01.012 | PREEDIT OUTPUT OF TEST CASE | 40 |
| NEA0705_01.013 | ALPPLOT SOURCE (FORTRAN-4) | 1686 |
| NEA0705_01.014 | ALPPLOT INPUT FOR TEST CASE | 25 |
| NEA0705_01.015 | ALPPLOT OUTPUT OF TEST CASE | 61 |
| NEA0705_01.016 | STEAM TABLE LIBRARY CONVERTER (FORTRAN-4) | 14 |
| NEA0705_01.017 | STEAM TABLE LIBRARY (BCD) | 1908 |
| NEA0705_01.018 | ALARM-P1 JCL FOR TEST CASE | 80 |
| NEA0705_01.019 | STEAM TABLE LIBRARY (BIN) | 79 |
Keywords: ECCS, blowdown, hydraulics, loss-of-coolant accident, pwr reactors, reactor safety, thermodynamics.