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IAEA0892 MURLI-CLUSTER.

MURLI-CLUSTER, Lattice Calculation of PHWR with Rod Clustered Fuel

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1. NAME OR DESIGNATION OF PROGRAM:  MURLI-CLUSTER.
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2. COMPUTERS
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Program name Package id Status Status date
MURLI-CLUSTER IAEA0892/01 Tested 02-JUL-1985

Machines used:

Package ID Orig. computer Test computer
IAEA0892/01 PRIME DEC VAX 11/780
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MURLI-CLUSTER is an integral transport theory code to obtain the physics characteristics (fluxes, reaction rates, etc.) of PHWR lattices which use rod clustered fuel  assemblies. The actual cell is replaced by an equivalent cylindrical cell for the purpose of computation of fluxes. For a specified buckling, it computes the effective multiplication factor using few-group diffusion theory and a few-group collapsed set of cross sections.

The code can optionally be used to obtain the number densities of fissile, fertile and fission product nuclides as a function of exposure and to recalculate fluxes, reaction rates and k-effective at specified burnup steps.

A 27-group library is included. It is obtained by collapsing the 69-group WIMS library over a typical PHWR lattice spectrum. There are four pseudo fission products associated with the decay chains of uranium and plutonium in addition to Xe-135, Rh-105, Np-239, U-236,  Am-241, Am-242, and Am-243. There is one lumped pseudo fission production also.
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4. METHOD OF SOLUTION

The cluster is homogenized ring-wise and then the interface current formalism is used to obtain the fluxes by integral transport theory. However, the heterogeneity corrections in the fast and resonance regions are obtained by exact collision probability calculation in explicit cluster geometry.

The burnup equations are solved by either fourth-order Runge-Kutta mathod or the trapezoidal rule.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

There is a maximum of 40 elements that can be used, out of which there can be up to 8
fissionable and/or resonant elements; one can use up to 30 spatial regions and 8 different material mixtures, with a maximum of 5
burnable mixtures.
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6. TYPICAL RUNNING TIME

On PRIME-450 it takes a little less than one  minute of CPU time for the initial (zero-burnup) step and about half this time at further burnup steps. The test case takes approximately 20 seconds of execution time on PRIME-450.
IAEA0892/01
NEA-DB executed the test case included in this package  on VAX-11/780. The total CPU time for compilation, linkage and execution was about 3.5 minutes.
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7. UNUSUAL FEATURES OF THE PROGRAM:  None.
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8. RELATED AND AUXILIARY PROGRAMS:  None.
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9. STATUS
Package ID Status date Status
IAEA0892/01 02-JUL-1985 Tested at NEADB
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10. REFERENCES

- H.C. Huria:
  MURLI - A Multigroup Integral Transport Theory Code for Thermal
          Reactor Lattice Investigations
  Atomkernenergie 31,77 (1978)
- I. Carlvik:
  A Method for Calculating Collision Probabilities in General
Geometry and Applications to Flux Distribution and Dancoff Factors    PICG, 2, 225 (1965)
IAEA0892/01, included references:
- H.C. Huria:
  Manager's Manual for the Code MURLI-CLUSTER.
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
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11. MACHINE REQUIREMENTS

On PRIME-450 32K main storage with temporary  disc storage for scratch files.
IAEA0892/01
The test case included in the package was run on VAX-11/780 in 170K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0892/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  PRIMOS (PRIME).
IAEA0892/01
VMS-V3.4 (VAX-11/780).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

This code system has been included in the Coordinated Research Programme (CRP) on  "Codes Adaptable  to Small and  Medium-Size
Computers Available in Developing Countries for In-Core Fuel
Management" of the International Atomic Energy Agency.

      H.C. Huria
      Theoretical Physics Division
      5th Floor, Central Complex
      Bhabha Atomic Research Centre
      BOMBAY - 400 085 (India)
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16. MATERIAL AVAILABLE
IAEA0892/01
File name File description Records
IAEA0892_01.003 INFORMATION FILE 57
IAEA0892_01.004 MURLI MAIN PROGRAM SOURCE 2762
IAEA0892_01.005 TOBINA SOURCE PROGRAM 71
IAEA0892_01.006 COMMAND PROCEDURE 29
IAEA0892_01.007 X-SEC LIBRARY (FORMATTED, EBCDIC) 5348
IAEA0892_01.008 RESONANCE LIBRARY (FORMATTED, EBCDIC) 620
IAEA0892_01.009 MURLI TEST CASE INPUT DATA 45
IAEA0892_01.010 MURLI TEST CASE PRINTED OUTPUT 560
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • C. Static Design Studies

Keywords: burnup, cylindrical configuration, diffusion equations, integral equations, multiplication factors, neutron flux, reaction rates, reactor lattices, rod bundles, thermal reactors.