LAHET Code System/CINDER'90 validation calculations and comparison with experimental data
Brun, TO; Beard, CA; Daemen, LL; Pitcher, EJ; Russell, GJ
| HERO ID | 1751690 |
|---|---|
| Year | 1994 |
| Title | LAHET Code System/CINDER'90 validation calculations and comparison with experimental data |
| Authors | Brun, TO; Beard, CA; Daemen, LL; Pitcher, EJ; Russell, GJ |
| Volume | GRA and I |
| 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. |
| Report Number | NTIS/02989208_2 |
| Is Certified Translation | No |
| Dupe Override | No |
| Comments | Journal: Govt Reports Announcements and Index ISSN: |
| Is Public | Yes |
| Keyword | <?xml version="1.0" encoding="UTF-8"?><kw>Accelerators</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>*Neutron Sources</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>*Neutron Transport</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>*Nucleon Reactions</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Computer Codes</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Design</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Isotope Production</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Neutron Leakage</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Neutron Spectra</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Nuclear Fuel Conversion</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Radioactive Waste Processing</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Theoretical Data</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Uses</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>Tables(data)</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>EDB/663610</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>EDB/663430</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>EDB/070201</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>EDB/430100</kw>; <?xml version="1.0" encoding="UTF-8"?><kw>EDB/990200</kw> |