SIGACE Code for Generating High-Temperature ACE Files; Validation and Benchmarking
- Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat (India)
- Reactor Physics Design Division, Bhabha Atomic Research Center, Mumbai-400085 (India)
- Nuclear Data Section, International Atomic Energy Agency, Vienna (Austria)
A code named SIGACE has been developed as a tool for MCNP users within the scope of a research contract awarded by the Nuclear Data Section of the International Atomic Energy Agency (IAEA) (Ref: 302-F4-IND-11566 B5-IND-29641). A new recipe has been evolved for generating high-temperature ACE files for use with the MCNP code. Under this scheme the low-temperature ACE file is first converted to an ENDF formatted file using the ACELST code and then Doppler broadened, essentially limited to the data in the resolved resonance region, to any desired higher temperature using SIGMA1. The SIGACE code then generates a high-temperature ACE file for use with the MCNP code. A thinning routine has also been introduced in the SIGACE code for reducing the size of the ACE files. The SIGACE code and the recipe for generating ACE files at higher temperatures has been applied to the SEFOR fast reactor benchmark problem (sodium-cooled fast reactor benchmark described in ENDF-202/BNL-19302, 1974 document). The calculated Doppler coefficient is in good agreement with the experimental value. A similar calculation using ACE files generated directly with the NJOY system also agrees with our SIGACE computed results. The SIGACE code and the recipe is further applied to study the numerical benchmark configuration of selected idealized PWR pin cell configurations with five different fuel enrichments as reported by Mosteller and Eisenhart. The SIGACE code that has been tested with several FENDL/MC files will be available, free of cost, upon request, from the Nuclear Data Section of the IAEA.
- OSTI ID:
- 20722606
- Journal Information:
- AIP Conference Proceedings, Vol. 769, Issue 1; Conference: International conference on nuclear data for science and technology, Santa Fe, NM (United States), 26 Sep - 1 Oct 2004; Other Information: DOI: 10.1063/1.1945056; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors
A Verification of Flux Sensitivity Estimates Using the MCNP Tally Perturbation Tool
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
BNL
DOPPLER COEFFICIENT
FAST REACTORS
FISSION
MONTE CARLO METHOD
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
NUCLEAR ENGINEERING
PERFORMANCE
PWR TYPE REACTORS
RESONANCE
S CODES
SODIUM COOLED REACTORS
VALIDATION