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PSR-0190 ADENA. (Abstract last modified 28-APR-1994)
1.
NAME OR DESIGNATION OF PROGRAM - ADENA. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
PSR-0190/01 CDC CYBER 740 CDC CYBER 740
PSR-0190/02 IBM 3033 DEC VAX 6000
3.
DESCRIPTION OF PROBLEM OR FUNCTION - ADENA calculates approximately fission-product beta and gamma decay energies and spectra in 19 or fewer energy groups from a mixture of U-235 and Pu-239 fuels. The calculation uses aggregate, adjusted data derived from a combination of several experiments and summation results based on the ENDF/B-V fission product file.
4.
METHOD OF SOLUTION - An absorption correction for U-235 and Pu-239 fuel mixtures is applied in the spectra calculation. The energies are calculated for finite, user-defined irradiation times. For long irradiation times, the effect of neutron absorption is accounted for.
5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - 6.
TYPICAL RUNNING TIME - 14 CPU seconds on CDC CYBER 740 for test case execution. 7.
UNUSUAL FEATURES OF THE PROGRAM - 8.
RELATED AND AUXILIARY PROGRAMS - 9.
STATUS 10.
REFERENCES - 11.
MACHINE REQUIREMENTS - 65,200 octal words of CDC CYBER 740 main storage. 12.
PROGRAMMING LANGUAGE(S) USED - 13.
OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - NOS 1.4(CYB740). 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHOR - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: BETA SPECTRA, FISSION PRODUCTS, FISSION SPECTRA, GAMMA SPECTRA, PLUTONIUM 239, SPECTRA, URANIUM 235
Program-name Package-ID Status
ADENA PSR-0190/01 Tested
ADENA PSR-0190/02 Tested
PSR-0190/01: 18-MAY-1984 Tested at NEADB
PSR-0190/02: 28-APR-1994 Tested at NEADB
PSR-0190/01:
- D.C. George, R.J. LaBauve and T.R. England:
Application of Adjusted Data in Calculating Fission Product Decay
Energies and Spectra
LA-9362-MS (June 1982).
PSR-0190/02:
- D.C. George, R.J. LaBauve and T.R. England:
Application of Adjusted Data in Calculating Fission Product Decay
Energies and Spectra
LA-9362-MS (June 1982).
PSR-0190/02:
NEA-DB implemented the program on a DEC VAX-6000 computer.
PSR-0190/01: FORTRAN-IV
PSR-0190/02: FORTRAN-IV
PSR-0190/02:
For the test implementation at NEA-DB, the VAX ran under VMS V.5.5-2. The source code was compiled with the FORTRAN-77 compiler V.5.5-98.
Contributed by: Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.
PSR-0190/01:
PSR0190_01.002 ADENA INFORMATION 48 records
PSR0190_01.004 ADENA SOURCE (COMPILER READY FORM) 1291 records
PSR0190_01.005 ADENA TEST CASE INPUT DATA 4 records
PSR0190_01.006 ADENA TEST CASE PRINTED OUTPUT 46 records
PSR-0190/02:
PSR0190_02.001 Information file 103 records
PSR0190_02.002 Source code ADENA for IBM computers 1429 records
PSR0190_02.003 JCL file for IBM version 14 records
PSR0190_02.004 Source code for CDC machines 1288 records
PSR0190_02.005 Source code for VAX 1430 records
PSR0190_02.006 Input file 4 records
PSR0190_02.007 Output file 50 records
- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
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