Published June 1981
| Version v1
Journal article
Analysis of pressurized water reactor primary circuit processes and fuel rod heatup in the case of separated coolant
Description
Some disturbances in nuclear reactor operation can result in the separation of primary coolant into two phases, thus establishing a water level so that the cladding is cooled only with steam. A calculation model was developed to examine such cases. In comparing the calculation results with the measurement results, the measurements confirmed the calculations. 5 refs
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 53
- Journal Issue
- 3
- Series
- Nucl. Technol.
- Journal Page Range
- 381-387
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14728015
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLING; FUEL RODS; HEAT TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; STEAM; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; FLUID FLOW; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS