RESEND, Infinitely Dilute Point Cross-Sections Calculation from ENDF/B Resonance Parameter. ADLER, ENDF/B Adler-Adler Resonance Parameter to Point Cross-Sections with Doppler Broadening
Creators
- 1. National Nuclear Data Center, Brookhaven National Laboratory, Upton, Long Island, New York 11973 (United States)
Description
1 - Description of problem or function: RESEND generates infinitely- dilute, un-broadened, point cross sections in the ENDF format by combining ENDF File 3 background cross sections with points calculated from ENDF File 2 resonance parameter data. ADLER calculates total, capture, and fission cross sections from the corresponding Adler-Adler parameters in the ENDF/B File 2 Version II data and also Doppler-broadens cross sections. 2 - Method of solution: RESEND calculations are done in two steps by two separate sections of the program. The first section does the resonance calculation and stores the results on a scratch file. The second section combines the data from the scratch file with background cross sections and prints the results. ADLER uses the Adler-Adler formalism. 3 - Restrictions on the complexity of the problem: RESEND expects its input to be a standard mode BCD ENDF file (Version II/III). Since the output is also a standard mode BCD ENDF file, the program is limited by the six significant figure accuracy inherent in the ENDF formats. (If the cross section has been calculated at two points so close in energy that only their least significant figures differ, that interval is assumed to have converged, even if other convergence criteria may not be satisfied.) In the unresolved range the cross sections have been averaged over a Porter-Thomas distribution. In some regions the calculated resonance cross sections may be negative. In such cases the standard convergence criterion would cause an unnecessarily large number of points to be produced in the region where the cross section becomes zero. For this reason an additional input convergence criterion (AVERR) may be used. If the absolute value of the cross section at both ends of an interval is determined to be less than AVERR then the interval is assumed to have converged. There are no limitations on the total number of points generated. The present ENDF (Version II/III) formats restrict the total number of points that can be given for a reaction type to 5000. ADLER can handle resonance data up to a maximum of 10 isotopes with a total number of 500 resonances. The code assumes that the resolved resonance parameters are given for one energy range which is the same for all the isotopes of an element. The mesh points at which the cross sections are calculated can be varied. Since the calculated data are not stored, an increase in the number of mesh points does not conflict with any storage requirement
Availability note (English)
Available on-line: http://www.nea.fr/abs/html/nesc0465.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41037642
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Computer Program Description, Non-conventional Literature
- Descriptors DEI
- A CODES; BREIT-WIGNER FORMULA; CAPTURE; COMPUTER PROGRAM DOCUMENTATION; CONVERGENCE; CROSS SECTIONS; DOPPLER BROADENING; ENERGY RANGE; FISSION; MULTILEVEL ANALYSIS; NUCLEAR DATA COLLECTIONS; PORTER-THOMAS DISTRIBUTION; R CODES; RESONANCE; SCATTERING; WEBSITES
- Descriptors DEC
- COMPUTER CODES; DOCUMENT TYPES; LINE BROADENING; NUCLEAR REACTIONS
Optional Information
- Notes
- 4 refs.