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NESC9940 THERMIT2.

THERMIT, 3-D Thermo-Hydraulics of BWR and PWR

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1. NAME OR DESIGNATION OF PROGRAM:  THERMIT2.
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2. COMPUTERS
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Program name Package id Status Status date
THERMIT-2 NESC9940/01 Tested 20-JUL-1984

Machines used:

Package ID Orig. computer Test computer
NESC9940/01 IBM 370 series IBM 3081
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3. DESCRIPTION OF PROGRAM OR FUNCTION

THERMIT2, the most recent release of THERMIT, is intended for thermal-hydraulic analysis of both boiling and pressurized water reactor cores. It solves the three-dimensional, two-fluid equations describing the two-phase flow and heat transfer dynamics in rectangular coordinates. The two-fluid model uses separate partial differential equations expressing conservation of mass, momentum, and energy for each fluid. THERMIT2  offers the choice of either pressure or velocity boundary conditions at the top and bottom of the core. THERMIT2 includes a two-phase turbulent mixing model which provides subchannel analysis capability. THERMIT2 also solves the radial heat conduction equations for fuel pin temperatures, and calculates the heat flux from fuel pin to coolant with appropriate heat transfer models described by a boiling curve.
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4. METHOD OF SOLUTION

By expressing the exchange of mass, momentum, and energy between the fluids with physically-based mathematical models, the relative motion and thermal non-equilibrium between the  fluids can exist.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

THERMIT2 contains proprietary subroutines LEQT1B, UERTST, and UGETIO from the IMSL library. These  routines may not be removed from this software for use in other software.
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9. STATUS
Package ID Status date Status
NESC9940/01 20-JUL-1984 Tested at NEADB
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10. REFERENCES:
NESC9940/01, included references:
- J.E.Kelly, S.P.Kao and M.S.Kazimi:
User's Guide for THERMIT-2: AVersion of THERMIT for Both Core-Wide and
Subchannel Analysis of Light Water Reactor. MIT-EL-81-029  (August 1981)
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11. MACHINE REQUIREMENTS:  260K bytes main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC9940/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

      M.S. Kazimi, S.P. Kao, and J.E. Kelly
      Massachusetts Institute of Technology
      Department of Nuclear Engineering
      77 Massachusetts Avenue
      Cambridge, Massachusetts 02139
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16. MATERIAL AVAILABLE
NESC9940/01
File name File description Records
NESC9940_01.003 THERMIT-2 INFORMATION FILE 81
NESC9940_01.004 THERMIT-2 SOURCE (CARD-IMAGES) 5879
NESC9940_01.005 THERMIT-2 SOURCE (INPUT TO IEBUPDTE) 5944
NESC9940_01.006 JCL TO GENERATE LOAD MODULE 42
NESC9940_01.007 JCL FOR TEST CASE EXECUTION 30
NESC9940_01.008 THERMIT-2 INPUT DATA FOR TEST CASE 1 36
NESC9940_01.009 THERMIT-2 INPUT DATA FOR TEST CASE 2 36
NESC9940_01.010 THERMIT-2 INPUT DATA FOR TEST CASE 3 7
NESC9940_01.011 THERMIT-2 PRINTED OUTPUT OF TEST CASE 1 536
NESC9940_01.012 THERMIT-2 PRINTED OUTPUT OF TEST CASE 2 491
NESC9940_01.013 THERMIT-2 PRINTED OUTPUT OF TEST CASE 3 1179
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17. CATEGORIES
  • H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, fluid flow, heat transfer, pwr reactors, steady-state conditions, three-dimensional, transients, two-phase flow.