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NEA-0447 EUREKA.

EUREKA, Reactivity Transients in LWR from Control Rod, Coolant Flow, Temperature

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1. NAME OR DESIGNATION OF PROGRAM:  EUREKA.
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2. COMPUTERS
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Program name Package id Status Status date
EUREKA NEA-0447/01 Tested 01-JUL-1976

Machines used:

Package ID Orig. computer Test computer
NEA-0447/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

This program can analyze the transient response of the core against the reactivity change caused  by control rod drop (or withdrawal), coolant flow change and/or coolant temperature change in a light water power reactor.
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4. METHOD OF SOLUTION

Coupled neutronic and thermal-hydrodynamic response is calculated for multi-regions in the core through one-point neutron kinetics. The core considered in the model can be  divided into up to five regions (channels) radially and 20 regions (21 nodes) axially. Each subdivision gives its own power generation  rate and reactivity feedback weighting factor for an application to  point kinetics calculation. Each channel is represented by a fuel rod which contains three materials (fuel meat, gas gap and cladding) and associated coolant and is subdivided into up to 25 nodes in radial direction. There are provisions to calculate thermal hydrodynamics of channels and temperature profiles in fuels. The transient power is determined by a numerical solution of the one point kinetics equation. The temperature distributions in each fuel  are computed on the basis of a one-dimensional heat conduction equation. Local heat generation is determined from reactor power and specified weighting factors. Heat transfer correlations at the clad-coolant interface are employed in each of the various heat transfer regimes, such as convection, nucleate, transition and film  boiling. The hydrodynamics in each coolant channel are solved through a one-dimensional conservation equation of mass, moment and energy.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The thermal hydrodynamics model used has caused numerical instability in certain situations, i.e. transient boiling occurred seriously in coolant channels. There are also many uncertainties in the areas of transient heat transfer correlations and void volume production.
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6. TYPICAL RUNNING TIME

The sample problem requires less than 29 seconds CPU time to process 2081 time steps on 4 channels.
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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-0447/01 01-JUL-1976 Tested at NEADB
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10. REFERENCES

- M. Ishikawa, Y. Kuge, N. Ohnishi, E. Takeuchi and Y. Kanbayashi:
  'EUREKA, A Computer Code  for Uranium-Oxide Fuelled, Water Cooled Reactor Kinetics Analysis.'
  JAERI 1235 (September 1974).
- M. Ishikawa et al.:
  'Fast Transient Analysis for Light Water Power Reactor by EUREKA, Coupled Nuclear Thermal Hydrodynamic Kinetic Code'
  JAERI 1201 (January 1971).
- M. Ishikawa, N. Ohnishi, Y. Kuge, E. Takeuchi and Y. Kanbayashi:
  'Analysis of Moderator Feedback Effects on Rapid Power Burst by EUREKA'
  NEA Computer Program Library Newsletter no. 19 (June 1975).
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11. MACHINE REQUIREMENTS:  77k words plus 3 magnetic tapes or disks.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0447/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  M 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 AUTHOR

  M. Ishikawa
  Reactivity Accident Laboratory
  Division of Reactor Safety
  Reactor Safety Research Center
  Japan Atomic Energy Research Institute
  Tokai-Mura, Ibaraki-Ken
  Japan.
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16. MATERIAL AVAILABLE
NEA-0447/01
File name File description Records
NEA0447_01.001 SOURCE PROGRAM (F4) EBCDIC 5134
NEA0447_01.002 ASSEMBLER ROUTINE EBCDIC 81
NEA0447_01.003 SAMPLE PROBLEM INPUT DATA 60
NEA0447_01.004 SAMPLE PROBLEM PRINTED OUTPUT 5084
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: LWR reactors, accidents, control elements, coolants, hydrodynamics, kinetics, reactivity, temperature distribution, thermodynamics.