IAEA0892 MURLI-CLUSTER.
MURLI-CLUSTER, Lattice Calculation of PHWR with Rod Clustered Fuel
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
[ top ]
[ top ]
To submit a request, click below on the link of the version you wish to order.
Only liaison officers are authorised to submit online requests. Rules for requesters are
available here.
| 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 |
[ top ]
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.
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.
[ top ]
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.
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.
[ top ]
[ top ]
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.
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.[ top ]
[ top ]
[ top ]
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)
- 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)
[ top ]
11. MACHINE REQUIREMENTS
On PRIME-450 32K main storage with temporary disc storage for scratch files.
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.[ top ]
IAEA0892/01
VMS-V3.4 (VAX-11/780).[ top ]
[ top ]
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)
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)
[ top ]
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 |
[ top ]
- 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.