Evaluation of nanofluids for enhancing critical heat flux for in-vessel retention during sever reactor accidents
- 1. Toshiba Energy Systems & Solutions Corporation, Energy Systems Research and Development Center, Yokohama, Kanagawa (Japan)
- 2. Toshiba Energy Systems & Solutions Corporation, Isogo Nuclear Engineering Center, Yokohama, Kanagawa (Japan)
- 3. Kansai Electric Power Co., Inc., Office of Human Resources and Safety Management, Osaka (Japan)
Description
In-vessel retention (IVR) of a molten core through external cooling of the reactor vessel is a severe accident management strategy at nuclear power plants. The enhancement of critical heat flux (CHF) is one of the measures to improve the success probability of IVR. A nanofluid, in which nanoparticles are dispersed in a liquid, is known to reliably enhance CHF, mainly under pool boiling conditions. However, to apply nanofluids to IVR, it is necessary to clarify the effect of CHF enhancement under convection boiling similar to that in an actual IVR event. Therefore, CHF tests were conducted using a rectangular test section 50 mm wide × 50 mm deep × 600 mm long under conditions simulating severe accidents. From the CHF data obtained for various nanofluid parameters under typical severe accident conditions, each parameter's effect on CHF enhancement was clarified. It was found that CHF was improved by 50% or more by a nanofluid as compared with deionized water. Furthermore, the CHF of nanofluid obtained in the tests simulating the actual severe accident conditions increased from 30% to 50% compared with that of deionized water, suggesting that CHF can be enhanced by nanofluids even in an actual plant. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/00223131.2021.1983482Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 59
- Journal Issue
- 4
- Journal Page Range
- p. 499-509
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53110287
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FORCED CONVECTION; IN-VESSEL RETENTION; MELTDOWN; NANOFLUIDS; NANOPARTICLES; NUCLEAR POWER PLANTS; POOL BOILING; REACTOR MAINTENANCE; REACTOR VESSELS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BOILING; CONTAINERS; CONVECTION; DISPERSIONS; ENERGY TRANSFER; FLUID FLOW; FLUIDS; HEAT FLUX; HEAT TRANSFER; MAINTENANCE; MASS TRANSFER; NUCLEAR FACILITIES; NUCLEATE BOILING; OPERATION; PARTICLES; PHASE TRANSFORMATIONS; POWER PLANTS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR OPERATION; SEVERE ACCIDENTS; SUSPENSIONS; THERMAL POWER PLANTS
Optional Information
- Notes
- 17 refs., 13 figs., 5 tabs.