last modified: 11-JUN-1982 | catalog | categories | new | search |

NEA-0703 STEADY-ACE.

STEADY-ACE, 3-D Neutronics and Multichannel Thermohydraulics Analysis of BWR

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1. NAME OR DESIGNATION OF PROGRAM:  STEADY-ACE.
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2. COMPUTERS
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Program name Package id Status Status date
STEADY-ACE NEA-0703/01 Tested 11-JUN-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0703/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

Three-dimensional nuclear and thermal-hydraulic core performance of a BWR.
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4. METHOD OF SOLUTION

The program consists of two subprograms: i.e. the few-group three-dimensional diffusion subprogram DIFFUSION- ACE and the multichannel thermal-hydraulic subprogram HYDRO-ACE.
The two subprograms are combined in an iterative way so that the interdependency of the power distribution and the void fraction dis- tribution can be treated consistently.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Number of energy groups is fixed to be 2 or 3.
Number of control rods is less than 16.
Options for the calculation geometry are available only to "full core", "half core" and "quarter core".
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6. TYPICAL RUNNING TIME

The computation time of the example case of JPDR quarter core (72/4 assemblies) is 7 CPU minutes on the FACOM 230-75.
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7. UNUSUAL FEATURES OF THE PROGRAM

In this program, three-dimensional neutron diffusion calculation code with finite difference method and multichannel thermo-hydraulics calculation code are combined direct- ly. Thus, much more computer running time and core memory are re- quired than for commonly used BWR simulators such as FLARE, but the  accuracy of the computed results is expected to be logically better  than that by common simulators.
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8. RELATED AND AUXILIARY PROGRAMS

DIFFUSION-ACE:  Three dimensional diffusion program.
HYDRO-ACE: Analysis program of thermo-hydraulic phenomena in a                 BWR core.
CELL-ACE: Burnup dependent cell constants calculation program                 in LWR.
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9. STATUS
Package ID Status date Status
NEA-0703/01 11-JUN-1982 Tested at NEADB
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10. REFERENCES

- Y. Naito, K. Abe and M. Maekawa:
  "STEADY-ACE: A Computer Program for Three-Dimensional Nuclear and
   Thermal-Hydraulic Analysis of BWR Core"
  JAERI 1264 (1980).
- Y. Naito, M. Maekawa and K. Shibuya:
  "A Three-Dimensional Neutron Diffusion Calculation Code:
   DIFFUSION-ACE"
  JAERI 1262 (1979).
- K. Abe and Y. Naito:
  "Computer Code HYDRO-ACE for Analyzing Thermo-Hydraulic Phenomena
   in the BWR core"
  JAERI-M 8442 (1979).
- Y. Naito, M. Maekawa and M. Toba:
  "Computer Code System CELL-ACE for Burnup Dependent Averaged Few
   Group Constants Over the Cell in LWR"
  JAERI-M 7544 (1978).
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0703/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
MONITOR-VII (FACOM 230-75).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The present system is on approximately 12 k source cards. Overlay facilities are employed throughout.
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Yoshitaka Naito and Kiyoharu Abe
          Division of JPDR Tokai Research Establishment
          Japan Atomic Energy Research Institute
          Tokai-mura
          Naka-gun
          Ibaraki-ken
          Japan
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16. MATERIAL AVAILABLE
NEA-0703/01
File name File description Records
NEA0703_01.003 STEADY-ACE INFORMATION FILE 44
NEA0703_01.004 STEADY-ACE, SOURCE CARD IMAGES (FORTRAN-4) 7606
NEA0703_01.006 STEADY-ACE, OVERLAY CARDS 17
NEA0703_01.007 STEADY-ACE, INPUT DATA FOR SAMPLE CASE 396
NEA0703_01.008 STEADY-ACE, OUTPUT OF SAMPLE CASE 14480
NEA0703_01.009 STEADY-ACE, JCL TO RUN SAMPLE CASE 86
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17. CATEGORIES
  • C. Static Design Studies
  • H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, diffusion, diffusion equations, few-group, hydraulics, power distribution, thermodynamics, three-dimensional, voids.