NEA-0159 BWCAL.

BWCAL, Void Distribution and Flow Velocity in BWR

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: BWCAL.

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2. COMPUTERS

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Program name	Package id	Status	Status date
BWCAL	NEA-0159/01	Tested	01-MAR-1967

Machines used:

Package ID	Orig. computer	Test computer
NEA-0159/01	IBM 7090	IBM 7090

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3. NATURE OF PHYSICAL PROBLEM SOLVED

A simulator programme for the BWR type reactor. Calculates the distribution of voids and flow velocities in the r-z geometry configuration of a BWR reactor at steady state.

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4. METHOD OF SOLUTION

Solves combined 2D(r-z) diff. eq. (STDE-3) with JP-HYDRO programme.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

3 groups
42 x 58 r-z meshes
6 x 13 r-z regions
10 compositions for 2d-diff. eq.
15 channels for hydrodynamics.

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6. TYPICAL RUNNING TIME: 15 - 20 minutes (IBM 7044).

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7. UNUSUAL FEATURES OF THE PROGRAM

There is an option specifying the natural or forced circulation. Having the simple calculation routines for Xe and Sm poisoning effects and the Doppler effect.

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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS

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9. STATUS

Package ID	Status date	Status
NEA-0159/01	01-MAR-1967	Tested at NEADB

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10. REFERENCES: - JAERI Report (to be published).

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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0159/01	FORTRAN-IV

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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED: IBM 7044 IBSYS.

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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 AUTHOR

       K. Moriguch, A. Kohsaka, Y. Naitoh                                          Tokai Research Establishment
       JAERI
       Tokai-Mura, Naka-Gun
       Ibaraki-Ken, Japan

       Y. Kuge
       Japan Atomic Power Co. Ltd.
       4, 1-Chome, Ohtemachi
       Chiyoda-Ku, Tokyo, Japan

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16. MATERIAL AVAILABLE

NEA-0159/01

File name	File description	Records
NEA0159_01.001	SOURCE&DATA	3114
NEA0159_01.002	OUTPUT	2668

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17. CATEGORIES

H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, Doppler coefficient, flow rate, hydrodynamics, poisoning, r-z, steady-state conditions, two-dimensional.