LAHET Code System/CINDER`90 validation calculations and comparison with experimental data
Abstract
The authors use the Los Alamos LAHET Code System (LCS)/CINDER`90 suite of codes in a variety of spallation neutron source applications to predict neutronic performance and as a basis for making engineering decisions. They have broadened their usage of the suite from designing LANSCE and the next generation of spallation neutron sources for materials science and nuclear physics research to designing a target system for Accelerator Production of Tritium and Accelerator Transmutation of Waste. While designing, they continue to validate the LCS/CINDER`90 code suite against experimental data whenever possible. In the following, they discuss comparisons between calculations and measurements for: integral neutron yields from a bare-target of lead; fertile-to-fissile conversion yields for thorium and depleted uranium targets; dose rates from the LANSCE tungsten target; energy deposition in a variety of light and heavy materials; and neutron spectra from LANSCE water and liquid hydrogen moderators. The accuracy with which the calculations reproduce experimental results is an indication of their confidence in the validity of their design calculations.
- Authors:
- Publication Date:
- Research Org.:
- Los Alamos National Lab., NM (United States)
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 10120458
- Report Number(s):
- LA-UR-94-269; CONF-9305177-15
ON: DE94006239; TRN: 94:003581
- DOE Contract Number:
- W-7405-ENG-36
- Resource Type:
- Technical Report
- Resource Relation:
- Conference: 12. International collaboration of advanced neutron sources meeting (ICANS),Abingdon (United Kingdom),24-28 May 1993; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 07 ISOTOPES AND RADIATION SOURCES; 43 PARTICLE ACCELERATORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; NEUTRON TRANSPORT; COMPUTER CODES; NUCLEON REACTIONS; NEUTRON SOURCES; DESIGN; ACCELERATORS; USES; NUCLEAR FUEL CONVERSION; ISOTOPE PRODUCTION; NEUTRON LEAKAGE; NEUTRON SPECTRA; THEORETICAL DATA; RADIOACTIVE WASTE PROCESSING; 663610; 663430; 070201; 430100; 990200; NEUTRON PHYSICS; NUCLEON-INDUCED REACTIONS AND SCATTERING; DESIGN, FABRICATION, AND OPERATION; DESIGN, DEVELOPMENT, AND OPERATION; MATHEMATICS AND COMPUTERS
Citation Formats
Brun, T O, Beard, C A, Daemen, L L, Pitcher, E J, Russell, G J, and Wilson, W B. LAHET Code System/CINDER`90 validation calculations and comparison with experimental data. United States: N. p., 1994.
Web. doi:10.2172/10120458.
Brun, T O, Beard, C A, Daemen, L L, Pitcher, E J, Russell, G J, & Wilson, W B. LAHET Code System/CINDER`90 validation calculations and comparison with experimental data. United States. https://doi.org/10.2172/10120458
Brun, T O, Beard, C A, Daemen, L L, Pitcher, E J, Russell, G J, and Wilson, W B. Tue .
"LAHET Code System/CINDER`90 validation calculations and comparison with experimental data". United States. https://doi.org/10.2172/10120458. https://www.osti.gov/servlets/purl/10120458.
@article{osti_10120458,
title = {LAHET Code System/CINDER`90 validation calculations and comparison with experimental data},
author = {Brun, T O and Beard, C A and Daemen, L L and Pitcher, E J and Russell, G J and Wilson, W B},
abstractNote = {The authors use the Los Alamos LAHET Code System (LCS)/CINDER`90 suite of codes in a variety of spallation neutron source applications to predict neutronic performance and as a basis for making engineering decisions. They have broadened their usage of the suite from designing LANSCE and the next generation of spallation neutron sources for materials science and nuclear physics research to designing a target system for Accelerator Production of Tritium and Accelerator Transmutation of Waste. While designing, they continue to validate the LCS/CINDER`90 code suite against experimental data whenever possible. In the following, they discuss comparisons between calculations and measurements for: integral neutron yields from a bare-target of lead; fertile-to-fissile conversion yields for thorium and depleted uranium targets; dose rates from the LANSCE tungsten target; energy deposition in a variety of light and heavy materials; and neutron spectra from LANSCE water and liquid hydrogen moderators. The accuracy with which the calculations reproduce experimental results is an indication of their confidence in the validity of their design calculations.},
doi = {10.2172/10120458},
url = {https://www.osti.gov/biblio/10120458},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {2}
}