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CCC-0643 CITATION-LDI2.

CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC

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1. NAME OR DESIGNATION OF PROGRAM:  CITATION-LDI2
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2. COMPUTERS
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
CITATION-LDI2 CCC-0643/02 Arrived 21-AUG-2001

Machines used:

Package ID Orig. computer Test computer
CCC-0643/02 PC-80386
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3. DESCRIPTION OF PROGRAM OR FUNCTION

CITATION is designed to solve problems using the finite difference representation of neutron diffusion theory, treating up to three space dimensions with arbitrary group to group scattering. X-y-z, theta-r-z, hexagonal z,  and trigonal z geometries may be treated. Depletion problems may be  solved and fuel managed for multi-cycle analysis. Extensive first order perturbation results may be obtained given microscopic data and nuclide concentrations. Statics problems may be solved and perturbation results obtained with microscopic data. This version of CITATION was released by ORNL as CITATION - Rev. 2, Supplement 3 in July 1972 and ran on mainframes. It was first ported to PC by AECL in October 1988. CITATION-PC included in the March 1996 package involved minor changes including the removal of overlay statements introduced in 1988. CITALDI-PC is a new modified version with list-directed input. The codes in this package accept cross sections in CITATION format. Macroscopic data may be entered according to format specifications in Section 008 of the published report. Microscopic data format is specified in Section 105. There are no codes in RSIC's code collection to generate data in CITATION format.
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4. METHOD OF SOLUTION

Explicit, finite difference approximations in space and time have been implemented. The neutron-flux-eigenvalue problems are solved by direct iteration to determine the multiplication factor or the nuclide densities required for a critical system.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

Run time is 15 to 45 minutes for the included test cases on a 486 DX running at 50 MHz.
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7. UNUSUAL FEATURES OF THE PROGRAM

CITATION is considered unusual in  that it should be relatively easy to modify the contents or to add routines. Effective techniques are incorporated to determine a critical system. More than one set of microscopic cross sections may be used in a system and nuclide behaviour can be followed on a sub zone scale within depletion regions. The user has flexible control over the route of a calculation as well as the edit of results.
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8. RELATED AND AUXILIARY PROGRAMS:  CITALDI-PC: List-directed input version.
CCC-0643/02
CITAXSEC was  added  in  Dec 1997 to process an ISOTXS  binary cross section file to  make  an ASCII file which CITATION can use directly as part of the input data.
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9. STATUS
Package ID Status date Status
CCC-0643/02 21-AUG-2001 Masterfiled Arrived
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10. REFERENCES
CCC-0643/02, included references:
- README Files:
  CITATION-PC README File (February 1996)
  CITALDI-PC README File (LDI= List Directed Input) (March 1996)
- T.B. Fowler, D.R. Vondy and G.W. Cunningham:
  Nuclear Reactor Core Analysis Code: CITATION
  ORNL-TM-2496, Rev. 2, with Supplements 1, 2, and 3 (October 1971)
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11. MACHINE REQUIREMENTS

CITATION 2.0 runs on personal computers equipped with an 80386 processor or better. At least 578K RAM must be available (use NORTON SI if possible to check). There cannot be any other resident programs (including PRINT). If you are using the  shell command, make sure the e parameter does not exceed 800. This is necessary to allow the largest possible array size in the complied code. A numeric math coprocessor is required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0643/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The executables were created with the Lahey Fortran V5.1 and 5.2 compilers under DOS 6. They can be run in a DOS window of Windows95.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA

Developed by:   Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
CCC-0643/02
MISTPREADME.RSI RSICC distribution statement
LODTPCITA-PC.EXE Self-extracting executable
DATTPCITANNA.INP Sample problem input file
MISTPF77L3.EER Error message
DATTPCITSAMP.INP Sample problem input file
SRCTPCITATION.FOR Fortran Source
MISTPREADME Important information
LODTPCITATION.EXE executable
OUTTPCITANNA.OUT Sample problem output
OUTTPCITSAMP.OUT Sample problem output
MISTPREADME.RSI RSICC distribution statement
LODTPCITAI-PC.EXE Self-extracting executable
LODTPCITALDI.EXE Executable
SRCTPCITALDI.FOR Fortran source
MISTPF77L3.EER Error Message
DATTPSAMP1LDI.INP Sample problem 1 input
DATTPSAMP2LDI.INP Sample problem 2 input
DATTPSAMP3LDI.INP Sample problem 3 input
OUTTPSAMP1LDI.OUT Sample problem 1 output
OUTTPSAMP2LDI.OUT Sample problem 2 output
OUTTPSAMP3LDI.OUT Sample problem 3 output
OUTTPSAMP1LDI.CND Sample 1 Cond. output
OUTTPSAMP2LDI.CND Sample 2 Cond. output
OUTTPSAMP3LDI.CND Sample 3 Cond. output
MISTPREADME Important information
LODTPCITA-XS.EXE Self-extracting executable
MISTPREADME RSICC distribution statement
LODTPCITAXSEC.EXE Executable
SRCTPCITAXSEC.FOR Fortran source
OBJTPISOTXS.BIN Binary file
OUTTPTAPE8.OUT Output file
OUTTPCITAXSEC.OUT Output file
DATTPCITA.INP Input file
OUTTPCITA.OUT  Output file
MISTPOVISOTXS Binary Cross-Section
NOTPTCITATION-PC README File (February 1996)
NOTPTCITALDI-PC README File (March 1996)
REPPTORNL-TM-2496, Rev. 2, Supp. 1,2,3 (Oct. 71)
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • K. Reactor Systems Analysis

Keywords: buckling, burnup, criticality searches, depletion, diffusion, fuel management, hexagonal configuration, inelastic scattering, multigroup, neutron diffusion equation, one-dimensional, perturbation, r-theta, steady-state conditions, three-dimensional, two-dimensional, x-y-z.