NATBWR: a steady-state model for natural circulation in boiling-water reactors
Description
This report documents the NATBWR steady-state BWR natural-circulation model and activities under EPRI Project RP1561-1 to gather data and predict the natural-circulation operation of the BWR. The report is organized into two parts, with the first part describing the NATBWR model and applications of the model to available BWR natural-circulation data and the second part providing user and programming information about the model. Five different operating BWR's were selected to demonstrate the application of the NATBWR model, one of each type from BWR/1 through BWR/4. For each operating plant, the available natural circulation data has been compared to model predictions. In addition to the data predictions, the behavior of the BWR system at reduced inventory, where the system is isolated and scrammed, and cooling provided by natural circulation has been analyzed. Finally, included as an appendix to Part 1 of this report is a discussion of the stability of the BWR system at natural-circulation conditions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A07/MF A01; 1 as DE83901828.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 148 p.
- Report number
- EPRI-NP--2856-CCM
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14771885
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; MATHEMATICAL MODELS; NATURAL CONVECTION; REACTOR CORES; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS