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NEA-0539 ASCOT-1.

ASCOT-1, Thermohydraulics of Axisymmetric PWR Core with Homogeneous Flow During LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  ASCOT-1.
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2. COMPUTERS
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Program name Package id Status Status date
ASCOT-1 NEA-0539/01 Tested 01-NOV-1978

Machines used:

Package ID Orig. computer Test computer
NEA-0539/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

ASCOT-1 is used to analyze the thermo-hydraulic behaviour in a PWR core during a loss-of-coolant accident.
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4. METHOD OF SOLUTION

The core is assumed to be axisymmetric two-dimensional and the conservation laws are solved by the method of characteristics. For the temperature response of fuel in the annular regions into which the core is divided, the heat conduction  equations are solved by an explicit method with averaged flow conditions.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Axi-symmetric
two-dimensional homogeneous flows.
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6. TYPICAL RUNNING TIME:  About 1.3 msec per mesh point per time step.
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7. UNUSUAL FEATURES OF THE PROGRAM

(1) Two-dimensional flow, namely, axial flow and radial flow can be      solved.
(2) The method of characteristics has the advantage of being  accurate and stable and of being able to give well-posed      boundary conditions.
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8. RELATED AND AUXILIARY PROGRAMS

The SPADE program is used to calculate the steam tables with pressure and density as independent  variables and the APLOT program is used to plot the result calculated by ASCOT-1.
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9. STATUS
Package ID Status date Status
NEA-0539/01 01-NOV-1978 Tested at NEADB
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10. REFERENCES

- K. Sato et al:
  SCOPE of the Code Development in JAERI for the LOCA-ECCS Evaluation of Light Water Reactors.
  Seminar on Reactor Safety, OECD, NEA
NEA-0539/01, included references:
- K. Kobayashi and K. Sato:
  ASCOT-1: A Computer Program for Analyzing the Thermo-Hydraulic
  Behaviour in a PWR Core during a LOCA
  JAERI-M 7917 (September 1978)
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11. MACHINE REQUIREMENTS:  About 160k words of memory.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0539/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  FACOM230-75 monitor 7.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS: NAME AND ESTABLISHMENT OF AUTHOR
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16. MATERIAL AVAILABLE
NEA-0539/01
File name File description Records
NEA0539_01.001 SOURCE PROGRAM (F4,EBCDIC) 7563
NEA0539_01.002 SAMPLE PROBLEM INPUT DATA 31
NEA0539_01.003 SAMPLE PROBLEM PRINTED OUTPUT 1405
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: flow rate, heat transfer, hydraulics, loss-of-coolant accident, pwr reactors, reactor safety, thermodynamics, two-dimensional.