NEA-0703 STEADY-ACE.

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

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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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.