IAEA0890 MURLI.
MURLI, 1-D Flux, Reaction Rate in Cylindrical Geometry Thermal Reactor Lattice by Transport
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| MURLI | IAEA0890/02 | Tested | 05-JUL-1985 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA0890/02 | PRIME | DEC VAX 11/780 |
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3. DESCRIPTION OF PROBLEM OR FUNCTION
MURLI is an integral transport theory code to calculate fluxes and reaction rates in one- dimensional cylindrical geometry lattice cells of a thermal reactor. For a specified buckling, it computes k-effective using few-group diffusion theory and a few-group collapsed set of cross sections.
The code can optionally be used to solve a first order differential equation for the number density of fissile, fertile and fission product nuclei as a function of time, and to recalculate fluxes, reaction rates and k-effective at different stages of burnup.
A 27-group cross section data library is included. There are four pseudo-fission products each associated with the decay chains of plutonium and uranium isotopes in addition to Rh-105, Xe-135, Np-239, U-236, Am-241, Am-242 and Am-243. There is also data for one lumped pseudo-fission product.
MURLI is an integral transport theory code to calculate fluxes and reaction rates in one- dimensional cylindrical geometry lattice cells of a thermal reactor. For a specified buckling, it computes k-effective using few-group diffusion theory and a few-group collapsed set of cross sections.
The code can optionally be used to solve a first order differential equation for the number density of fissile, fertile and fission product nuclei as a function of time, and to recalculate fluxes, reaction rates and k-effective at different stages of burnup.
A 27-group cross section data library is included. There are four pseudo-fission products each associated with the decay chains of plutonium and uranium isotopes in addition to Rh-105, Xe-135, Np-239, U-236, Am-241, Am-242 and Am-243. There is also data for one lumped pseudo-fission product.
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4. METHOD OF SOLUTION
Multiple collision probabilities and escape probabilities are calculated for each cylidrical shell region assuming protons are born uniformly and isotropically over the entire region volume. The equations of integral transport theory can then be solved for neutron flux.
The first order differential burnup equation is solved by a fourth order Runge-Kutta method.
Multiple collision probabilities and escape probabilities are calculated for each cylidrical shell region assuming protons are born uniformly and isotropically over the entire region volume. The equations of integral transport theory can then be solved for neutron flux.
The first order differential burnup equation is solved by a fourth order Runge-Kutta method.
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IAEA0890/02
NEA-DB compiled and executed the test case included in the package on VAX-11/780. CPU times required were 85 seconds for compilation and linking, and 7.6 seconds for execution.[ top ]
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IAEA0890/02, included references:
- H.C. Huria:Manager's Manual for the Lattice Physics Code MURLI.
- Theory of the Lattice Physics Code MURLI.
- Users Manual for the Lattice Physics Code MURLI.
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IAEA0890/02
Storage requirements on VAX-11/780 are 224K bytes of core memory for the load module and 163K bytes of disc space for the cross section tables.[ top ]
IAEA0890/02
VAX/VMS with FORTRAN77 compiler V3.3-51.[ top ]
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15. NAME AND ESTABLISHMENT OF AUTHOR
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 Reactor Physics Section
Babha Atomic Research Centre
Trombay
Bombay 400 085, India.
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 Reactor Physics Section
Babha Atomic Research Centre
Trombay
Bombay 400 085, India.
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IAEA0890/02
| File name | File description | Records |
|---|---|---|
| IAEA0890_02.003 | INFORMATION FILE | 148 |
| IAEA0890_02.004 | COMMAND PROC. TO INSTALL MURLI AND RUN TEST | 43 |
| IAEA0890_02.005 | MURLI SOURCE PROGRAM (FORTRAN) | 1838 |
| IAEA0890_02.006 | X-SEC LIBRARY FILE 1 (FORMATTED EBCDIC) | 5301 |
| IAEA0890_02.007 | X-SEC LIBRARY FILE 2 (FORMATTED EBCDIC) | 620 |
| IAEA0890_02.008 | TOBINA SOURCE PROGRAM (FORTRAN) | 71 |
| IAEA0890_02.009 | MURLI TEST CASE INPUT DATA | 16 |
| IAEA0890_02.010 | PRINTOUT OF INSTALLATION RUN | 4582 |
| IAEA0890_02.011 | MURLI TEST CASE PRINTED OUTPUT | 214 |
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- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- C. Static Design Studies
Keywords: cylindrical configuration, diffusion equations, multiplication factors, neutron flux, one-dimensional, reaction rates, reactor lattices, thermal reactors, transport theory.