CCC-0204 SWANLAKE.

1. NAME OR DESIGNATION OF PROGRAM:  SWANLAKE.

3. NATURE OF PHYSICAL PROBLEM SOLVED

Determination of the sensitivity  of a calculated quantity or result to microscopic cross section data utilized in the calculation.

The new version of SWANLAKE contains the following changes over the original version:
1. Fission contributions are considered with an option for a mini or maxi print edit of fission sensitivities.
2. The Shortlist feature was implemented for most I/O transfers which cut execution time considerably.
3. Plotting features were eliminated and replaced by a (punch/write) option.
4. For coupled neutron-gamma-ray problems, an output edit is printed which gives the group and zonewise contributions to the total response due to gamma-ray production.

4. METHOD OF SOLUTION

A particular sensitivity function, which represents an application of earlier perturbation approaches, is determined for the cross sections which were utilized in the discrete ordinates calculations.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The discrete ordinates calculations to be analyzed by this version of SWANLAKE must be time-independent and one-dimensional. The sensitivity function only allows for energy downscatter, does not include the effects of fission cross sections, and cannot evaluate the sensitivity of the calculated quantity or response to the response function itself.

6. TYPICAL RUNNING TIME

The infinite air sample problem included in the code package required 59 seconds for the ANISN forward calculation, 78 seconds for the ANISN adjoint calculation, and 16 seconds for the SWANLAKE calculation. Running time for both ANISN and SWANLAKE is highly problem dependent and is greatly affected by parameters such as the number of energy groups and the number of spatial intervals utilized.

7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM

8. RELATED AND AUXILIARY PROGRAMS

ANISN - input tape generator.
INTRIGUE-IIL - CALCOMP plotting package.

- D.E. Bartine, F.R. Mynatt and E.M. Oblow:
  SWANLAKE, A Computer Code Utilizing ANISN Radiation Transport
  Calculations for Cross Section Sensitivity Analysis.
  ORNL-TM-3809  (May 1973).

11. MACHINE REQUIREMENTS

Maximum core requirements for the sample problems discussed in the code manual is 848k bytes, minimum size is 290k bytes.
In the new version (CCC-0204/03), external storage devices are used  more extensively resulting in a factor of 3 reduction in the re- quired size of COMMON for most problems considered thus far. The corresponding increase in I/O apprears to be onlu about 30 % :
Auxiliary storage requirements, in addition to standard input and output devices, are 5 scratch devices and 2 storage devices. If cross sections are not read from cards, an additional tape or disk will be required.
the package is to be utilized, another tape is required.

13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED

The sample problem was run by NEA-DB on IBM 3081 using the system OS370/033 VS2 03.8G.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

15. NAME AND ESTABLISHMENT OF AUTHOR: Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.

File name	File description	Records
CCC0204_03.003	SWANLAKE INFORMATION FILE	62
CCC0204_03.004	SWANLAKE SOURCE PROGRAM (FORTRAN-4)	1754
CCC0204_03.005	SWANLAKE OVERLAY CONTROL CARDS	5
CCC0204_03.006	SWANLAKE JCL TO RUN TEST CASE	107
CCC0204_03.007	ANISN INPUT FOR FORWARD CASE	268
CCC0204_03.008	ANISN INPUT FOR ADJOINT CASE	271
CCC0204_03.009	SWANLAKE INPUT FOR TEST CASE	259
CCC0204_03.010	ANISN PRINTED OUTPUT OF FORWARD CASE	1979
CCC0204_03.011	ANISN PRINTED OUTPUT OF ADJOINT CASE	1986
CCC0204_03.012	SWANLAKE OUTPUT OF TEST CASE	1360