An ORNL code for gas-cooled reactor simulations
Conference
·
OSTI ID:555356
- Oak Ridge National Lab., TN (United States)
An interactive workstation-based simulation code for studying postulated severe accidents in gas-cooled reactors has been developed to accommodate user-generated plant design input with {open_quotes}smart front-end{close_quotes} checking. New code features include on- and off-line plotting, on-line help and documentation, and an automated sensitivity study option. The code and its predecessors have been validated using comparisons with a variety of experimental data and similar codes. 4 refs.
- Research Organization:
- American Nuclear Society (ANS), La Grange Park, IL (United States)
- OSTI ID:
- 555356
- Report Number(s):
- CONF-970607-Vol.2; TRN: 98:001536
- Resource Relation:
- Conference: ARS `97: American Nuclear Society (ANS) international meeting on advanced reactors safety, Orlando, FL (United States), 1-5 Jun 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the international topical meeting on advanced reactors safety: Volume 2; PB: 715 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
GRSAC Users Manual
Interactive simulations of gas-turbine modular HTGR transients and heatup accidents
MORECA-2: Interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options
Technical Report
·
Mon Feb 01 00:00:00 EST 1999
·
OSTI ID:555356
Interactive simulations of gas-turbine modular HTGR transients and heatup accidents
Conference
·
Wed Jun 01 00:00:00 EDT 1994
·
OSTI ID:555356
MORECA-2: Interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options
Technical Report
·
Tue Dec 01 00:00:00 EST 1992
·
OSTI ID:555356