Advanced Thermionic Reactor Systems Design Code

Conference · Sun Jan 06 00:00:00 EST 1991 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.40043· OSTI ID:5604627

Lewis, B. R. ^[1]; Pawlowski, R. A. ^[1]; Greek, K. J. ^[1]; Klein, A. C. ^[1]

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1. Oregon State Univ., Corvallis, OR (United States). Department of Nuclear Engineering, Radiation Center

An overall systems design code is under development to model an advanced in-core thermionic nuclear reactor system for space applications at power levels of 10 to 50 kWe. The design code is written in an object-oriented programming environment that allows the use of a series of design modules, each of which is responsible for the determination of specific system parameters. The code modules include a neutronics and core criticality module, a core thermal hydraulics module, a thermionic fuel element performance module, a radiation shielding module, a module for waste heat transfer and rejection, and modules for power conditioning and control. The neutronics and core criticality module determines critical core size, core lifetime, and shutdown margins using the criticality calculation capability of the Monte Carlo Neutron and Photon Transport Code System (MCNP). The remaining modules utilize results of the MCNP analysis along with FORTRAN programming to predict the overall system performance.

• Research Organization: Oregon State Univ., Corvallis, OR (United States). Department of Nuclear Engineering, Radiation Center
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5604627
• Report Number(s): CONF-910116-; CODEN: APCPC
• Journal Information: AIP Conference Proceedings, Vol. 217, Issue 1; Conference: 8. Symposium on Space Nuclear Power Systems, Albuquerque, NM (United States), 6-10 Jan 1991; ISSN 0094-243X
• Publisher: American Institute of Physics (AIP)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
THERMIONIC REACTORS
DESIGN
COMPUTER CODES
MONTE CARLO METHOD
NEUTRON FLUX
REACTOR CORES
SHIELDING
SPACE POWER REACTORS
MOBILE REACTORS
POWER REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
Nuclear Criticality Safety Program (NCSP)
Monte Carlo Neutron and Photon Transport Code System (MCNP)
FORTRAN programming
210600* - Power Reactors
Auxiliary
Mobile Package
& Transportable