A computer code, NATCON, for the analyses of steady-state thermal-hydraulics and safety margins in plate-type research reactors cooled by natural convection

Technical Report · Thu Dec 01 00:00:00 EST 1988

OSTI ID:6571231

Smith, R S; Woodruff, W L

The NATCON code provides a capability for the analysis of the thermal-hydraulics of plate-type research reactors cooled by natural convection. The code includes steady-state estimates of what are often considered safety margins. These estimates may include power peaking factors, hot channel factor components, and laminar flow entrance effects. A listing of the code and a description of the input are included, along with some sample results. The current version of the code has only properties data for light water. 4 refs., 3 figs., 11 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6571231
• Report Number(s): ANL/RERTR/TM-12; ON: DE89004509
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
N CODES
NATURAL CONVECTION
REACTOR COOLING SYSTEMS
RESEARCH REACTORS
COMPUTER PROGRAM DOCUMENTATION
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
STEADY-STATE CONDITIONS
COMPUTER CODES
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
MASS TRANSFER
MECHANICS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)
220900 - Nuclear Reactor Technology- Reactor Safety