NEA-0705 ALARM-P1. (Abstract last modified 22-OCT-1982)
1.
NAME OR DESIGNATION OF PROGRAM - ALARM-P1. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
NEA-0705/01 IBM 3033 IBM 3033
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.
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.
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.
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.
7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - Auxiliary routines: 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - Main storage: 900 kbytes on IBM 3033. 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - The code is operable on FACOM 230-75 M-VII or FACOM M200 F/4 operating system using Fortran H compiler.
14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHOR - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: BLOWDOWN, ECCS, HYDRAULICS, LOCA, PWR REACTORS, REACTOR SAFETY, THERMODYNAMICS
Program-name Package-ID Status
ALARM-P1 NEA-0705/01 Tested
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 code should be compiled using no optimization (OPT = 0).
NEA-0705/01:
NEA-DB ran the sample case on IBM 3033 in 480 seconds.
PREEDIT An editing program for ALARM-P1 plot data file
PLOT 4 A plotting program for RELAP 4
NEA-0705/01: 22-OCT-1982 Tested at NEADB
NEA-0705/01:
- 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).
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
NEA-0705/01: FORTRAN-IV
OS370/033 (IBM 3033).
Division of Reactor Safety Evaluation
Tokai Research Establishment
Japan Atomic Energy Research Institute
Japan
NEA-0705/01:
NEA0705_01.001 ALARM-P1 INFORMATION 122 records
NEA0705_01.002 ALARM-P1 SOURCE (FORTRAN-4) 18977 records
NEA0705_01.003 SETPAR SUBROUTINE (FORTRAN-4) 248 records
NEA0705_01.004 BLOCK DATA (ADDITIONAL) 30 records
NEA0705_01.005 SETB99 (REPLACING ENCODE) (ASSEMBLER) 100 records
NEA0705_01.006 ALARM-P1 INPUT FOR TEST CASE 1 128 records
NEA0705_01.007 ALARM-P1 OUTPUT OF TEST CASE 1 2799 records
NEA0705_01.008 ALARM-P1 INPUT FOR TEST CASE 2 30 records
NEA0705_01.009 ALARM-P1 OUTPUT OF TEST CASE 2 459 records
NEA0705_01.010 PREEDIT SOURCE (FORTRAN-4) 610 records
NEA0705_01.011 PREEDIT INPUT FOR TEST CASE 4 records
NEA0705_01.012 PREEDIT OUTPUT OF TEST CASE 40 records
NEA0705_01.013 ALPPLOT SOURCE (FORTRAN-4) 1686 records
NEA0705_01.014 ALPPLOT INPUT FOR TEST CASE 25 records
NEA0705_01.015 ALPPLOT OUTPUT OF TEST CASE 61 records
NEA0705_01.016 STEAM TABLE LIBRARY CONVERTER (FORTRAN-4) 14 records
NEA0705_01.017 STEAM TABLE LIBRARY (BCD) 1908 records
NEA0705_01.018 ALARM-P1 JCL FOR TEST CASE 80 records
NEA0705_01.019 STEAM TABLE LIBRARY (BIN) 79 records
- G. Radiological Safety, Hazard and Accident Analysis
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