Dynamics analyses of space power systems using the salt code
- Argonne National Lab., IL (USA)
The dynamic behavior of large space power systems has been identified as a significant technical issue. To date several analyses of reactor kinetics have been reported in the literature, but there have been few (if any) studies of the dynamic response of the entire space power system. The problem is complex and required analytical methods are not generally available. Furthermore, given the conceptual state of current MMW space power systems designs, dynamic models of components are not generally available. We have used the SALT code to perform preliminary analyses of the startup and shutdown transients of several proposed MMW system designs. In this paper we will provide a description of the code methodology and present results of the analyses performed for the NERVA derivative reactor (NDR) system. 3 refs., 3 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5319679
- Report Number(s):
- CONF-900109-12; ON: DE90002274
- Resource Relation:
- Conference: 7. symposium on space nuclear power systems, Albuquerque, NM (USA), 7-11 Jan 1990
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
SPACE POWER REACTORS
REACTOR KINETICS
COMPARATIVE EVALUATIONS
DATA ANALYSIS
DESIGN
DYNAMICS
ELECTRIC GENERATORS
FLUID FLOW
FUNCTIONAL MODELS
HEAT TRANSFER
MATHEMATICAL MODELS
POWER GENERATION
PRESSURE EFFECTS
PUMPS
REACTOR SHUTDOWN
REACTOR START-UP
S CODES
STEAM TURBINES
TEMPERATURE EFFECTS
VALVES
COMPUTER CODES
CONTROL EQUIPMENT
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
KINETICS
MACHINERY
MECHANICS
MOBILE REACTORS
OPERATION
POWER REACTORS
REACTOR OPERATION
REACTORS
SHUTDOWNS
START-UP
TURBINES
TURBOMACHINERY
NESDPS Office of Nuclear Energy Space and Defense Power Systems
210600* - Power Reactors
Auxiliary
Mobile Package
& Transportable
220100 - Nuclear Reactor Technology- Theory & Calculation
990200 - Mathematics & Computers