NEA-0100 HYTHEST.

HYTHEST, Dependence of Fuel Fabrication Tolerances on Hydraulics of BWR, PWR

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

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1. NAME OR DESIGNATION OF PROGRAM: HYTHEST.

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2. COMPUTERS

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Program name	Package id	Status	Status date
HYTHEST	NEA-0100/01	Tested	01-SEP-1972

Machines used:

Package ID	Orig. computer	Test computer
NEA-0100/01	IBM 360 series	IBM 360 series

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3. NATURE OF PHYSICAL PROBLEM SOLVED

HYTHEST is a Monte Carlo programme. With this programme it is possible to study statistically the influence that the random variation of the independent parameters subjected to fabrication tolerances (fuel density and enrichment, geometric dimension) have on dependent thermal hydraulic variables (temperatures, vapour quality, pressure drop) in a PWR and BWR reactor core.

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4. METHOD OF SOLUTION

According to the spot model, a random core is built up, choosing in every region of core the values of the independent parameters with the aid of a random sampling routine.
Next with a detailed thermal hydraulic calculation routine the values of the dependent variables are calculated in this random sampled core. This procedure is repeated according to a Monte Carlo technique choosing as many random cores as necessary.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

  900 maximum number of Monte Carlo histories
  220 maximum number of intervals in the channel
   50 maximum number of points in which the interval Ymax-Ymin
      must be subdivided.

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6. TYPICAL RUNNING TIME: About 15-90 seconds.

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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM

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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-0100/01	01-SEP-1972	Tested at NEADB

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10. REFERENCES

- J.E. Meyer:
  ART-A. Program for the Treatment of Reactor Thermal Transients on  the IBM 704
   WAPD-TM-156.
- V.L. Businaro, G.P. Pozzi:
  A New Method for the Statistical Analysis of Engineering
  Correction Factors
- E. Cashwell, C. Everett:
  Monte Carlo Method for Random Walk Problems
- A. Borella, G. Di Cola, and G.Pozzi:
  EUR-1587.E.

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11. MACHINE REQUIREMENTS: A 32k memory is required.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0100/01	FORTRAN-IV

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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED

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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

    A. Borella, G. Di Cola, G. Pozzi
    CETIS
    EURATOM - C.C.R.
    Ispra (Varese)
    Italy

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16. MATERIAL AVAILABLE

NEA-0100/01

File name	File description	Records
NEA0100_01.001	SOURCE PROGRAMME+INPUT DATA	941
NEA0100_01.002	PRINTED OUTPUT	230

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17. CATEGORIES

D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, Monte Carlo method, enrichment, fuels, pressure dependence, pwr reactors, temperature dependence, thermal analysis, thermodynamics, transients, vapors.