NEA-1340 INVENT-STUDSVIK.
INVENT-STUDSVIK, Fission Products Abundances in U235, U238, Pu239 Samples
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
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| INVENT-STUDSVIK | NEA-1340/01 | Tested | 18-MAY-1993 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1340/01 | DEC VAX 8200 | DEC VAX 6000 |
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4. METHOD OF SOLUTION
The code takes into account transfer between mass chains not only by neutron capture but also the emission of delayed neutrons, which is an important mode of decay far from stability. In recent years the code has been improved, notably by using double precision for many of the variables.
The code takes into account transfer between mass chains not only by neutron capture but also the emission of delayed neutrons, which is an important mode of decay far from stability. In recent years the code has been improved, notably by using double precision for many of the variables.
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6. TYPICAL RUNNING TIME
95 s for one case on a VAX-8200 computer (if print-out of individual nuclides is not required).
95 s for one case on a VAX-8200 computer (if print-out of individual nuclides is not required).
NEA-1340/01
NEA-DB ran the test case of FPCONV+INVENT on a DEC VAX 6000-510 computer in 40 seconds of CPU time.[ top ]
7. UNUSUAL FEATURES OF THE PROGRAM
The program carries out a comprehensive error analysis. The abundance of each nuclide, and its uncertainty, is evaluated. An analysis of the origin of the error (initial amounts, yields, half-lives, delayed-neutron branching ratios, capture cross sections) is performed.
The program carries out a comprehensive error analysis. The abundance of each nuclide, and its uncertainty, is evaluated. An analysis of the origin of the error (initial amounts, yields, half-lives, delayed-neutron branching ratios, capture cross sections) is performed.
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NEA-1340/01, included references:
- B. Duchemin and C. Nordborg:Decay Heat Calculation - An International Nuclear Code Comparison
NEACRP-319 "L", NEANDC-275 "U" (April 1990).
- G. Rudstam:
Uncertainty of Decay Heat Calculations Originating from Errors in
the Nuclear Data and the Yields of Individual Fission Products
Reprint from "Journal of Radioanalytical Chemistry" Vol. 55 No. 1
pp. 79-99 (1980).
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NEA-1340/01
| File name | File description | Records |
|---|---|---|
| NEA1340_01.001 | Information file | 49 |
| NEA1340_01.002 | Command file to run FPCONV and INVENT | 9 |
| NEA1340_01.003 | FPCONV.FOR FORTRAN source program | 774 |
| NEA1340_01.004 | FPINDATA.DAT Steering parameters | 3 |
| NEA1340_01.005 | FPLIBIN.DAT Formatted library | 4173 |
| NEA1340_01.006 | FPUTDATA.DAT Results file from FPCONV | 1000 |
| NEA1340_01.007 | INVENT.FOR FORTRAN source program | 3340 |
| NEA1340_01.008 | INVCOMMON.FOR Common statements for INVENT | 49 |
| NEA1340_01.009 | INVINDATA.DAT Steering parameters | 9 |
| NEA1340_01.010 | INVUTDATA.DAT Results file | 3045 |
Keywords: fission products, plutonium 239, uranium 235, uranium 238.