last modified: 21-JUN-2012 | catalog | categories | new | search |

NEA-0705 ALARM-P1.

ALARM-P1, PWR Thermohydraulics for ECCS During Blowdown

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ALARM-P1.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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
top ]
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.
top ]
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.
top ]
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).
top ]
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.
NEA-0705/01
NEA-DB ran the sample case on IBM 3033 in 480 seconds.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

Auxiliary routines:
    PREEDIT  An editing program for ALARM-P1 plot data file
    PLOT 4   A plotting program for RELAP 4
top ]
9. STATUS
Package ID Status date Status
NEA-0705/01 22-OCT-1982 Tested at NEADB
top ]
10. REFERENCES:
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).
top ]
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
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0705/01 FORTRAN-IV
top ]
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.
OS370/033 (IBM 3033).
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

          Division of Reactor Safety Evaluation
          Tokai Research Establishment
          Japan Atomic Energy Research Institute
          Japan
top ]
16. MATERIAL AVAILABLE
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
top ]
17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: ECCS, blowdown, hydraulics, loss-of-coolant accident, pwr reactors, reactor safety, thermodynamics.