Calculation of large leak sodium/water reaction in steam generator of LMFBR
Description
Two models were developed, one for calculating the leakage rate of water from heat transfer tubes due to one broken double-ended-guillotine tube in the steam generator of LMFBR using the one-dimensional method of characteristics, and another one for temperature, adiabatic spherical-to-columnar hydrogen bubble growth model in large sodium-water reaction. The hydrogen pressure transient in the break point and the compressibility of water/steam in the tubes are taken into account in the water leakage rate model. Pressure transient in the sodium-water reaction in case of large leakage is calculated and analyzed qualitatively for the leakage at the sections of subcooled water, superheated water and two-phase water in heat transfer tube, respectively. The result shows that the impact of leakage on the secondary loop varies from the break point on the heat transfer tube
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 20
- Journal Issue
- 2
- Journal Page Range
- p. 154-161
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 32003378
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUBBLE GROWTH; CALCULATION METHODS; FRACTURING; HEAT TRANSFER; LEAKS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; MOLTEN METAL-WATER REACTIONS; PIPES; SODIUM; STEAM GENERATORS; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- ALKALI METALS; BOILERS; BREEDER REACTORS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTORS; TUBES; VAPOR GENERATORS