SIMULATION OF THE HEAT-TRANSFER CHARACTERISTICS OF THE FUEL PINS IN A NUCLEAR REACTOR
A simple simulation of the heat-transfer characteristics of the fuel pins in a pressurized-water reactor was made in which heat-transfer equations describing the average pin were written using finite-differences techniques. The pin was simulated using eight, five, two, and one sections of UO2 successively. From this study the therman-time constant of the fuel pins was determined. An average fuel-temperature simulation using one section of UO2 was designed. The constants of this simulation were established so that its transient response matched the response of the previous five-section fuel-pin simulation. The constants of the fuel-temperature simulation were then altered to produce simulation of the fuel temperature in the two active passes through the reactor core. The final simulations of the fuel temperature in the second and third pass each consists of one section of UO2, one section of helium, and one section of stainless steel. The simulations are acceptable both for transient response and for economical utilization of equipment.
- This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number BMI-B&W-634.
Battelle Memorial Institute505 King Avenue
Columbus, OH USA 43201
Babcock and Wilcox CompanyAtomic Energy Division
Lynchburg, VA USA 24504
- Boyd, R S
- Gordon, B B
- Publication Date: 1957-9-27
- Features: Appendices; Figures; References; Tables;
- Pagination: 37 p.
- TRT Terms: Fuel elements; Fuel systems; Heat transfer
- Old TRIS Terms: Nuclear reactor fuel elements
- Subject Areas: Marine Transportation; Vehicles and Equipment;
- Accession Number: 00026019
- Record Type: Publication
- Source Agency: Maritime Administration
- Report/Paper Numbers: BMI-B&W-634
- Contract Numbers: AT(30-3)-274
- Files: TRIS, USDOT
- Created Date: Feb 6 1973 12:00AM