DRACS thermal performance evaluation for FHR. (March 2015)
- Record Type:
- Journal Article
- Title:
- DRACS thermal performance evaluation for FHR. (March 2015)
- Main Title:
- DRACS thermal performance evaluation for FHR
- Authors:
- Lv, Q.
Lin, H.C.
Kim, I.H.
Sun, X.
Christensen, R.N.
Blue, T.E.
Yoder, G.L.
Wilson, D.F.
Sabharwall, P. - Abstract:
- Highlights: A computer code for DRACS thermal performance evaluation for FHR is developed. The code is validated using available experimental data from the literature. The code is applied to a High-Temperature DRACS Test Facility (HTDF) at the OSU. Abstract: Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines coated particle fuel and a graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three coupled natural circulation/convection loops, relying completely on buoyancy as the driving force. These loops are coupled through two heat exchangers, namely, the DRACS Heat Exchanger and the Natural Draft Heat Exchanger. In addition, a fluidic diode is employed to minimize the parasitic flow into the DRACS primary loop and correspondingly the heat loss to the DRACS during normal operation of the reactor, and to keep the DRACS ready for activation, if needed, during accidents. To help with the design and thermal performance evaluation of the DRACS, a computer code using MATLAB has been developed. This code is based on a one-dimensional formulation and its principle is to solve the energy balance and integral momentum equations. By discretizing the DRACS system in the axial direction, a bulk mean temperature is assumed for each mesh cell. The temperatures of all the cells, as well as the mass flow rates in the DRACS loops, are predicted byHighlights: A computer code for DRACS thermal performance evaluation for FHR is developed. The code is validated using available experimental data from the literature. The code is applied to a High-Temperature DRACS Test Facility (HTDF) at the OSU. Abstract: Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines coated particle fuel and a graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three coupled natural circulation/convection loops, relying completely on buoyancy as the driving force. These loops are coupled through two heat exchangers, namely, the DRACS Heat Exchanger and the Natural Draft Heat Exchanger. In addition, a fluidic diode is employed to minimize the parasitic flow into the DRACS primary loop and correspondingly the heat loss to the DRACS during normal operation of the reactor, and to keep the DRACS ready for activation, if needed, during accidents. To help with the design and thermal performance evaluation of the DRACS, a computer code using MATLAB has been developed. This code is based on a one-dimensional formulation and its principle is to solve the energy balance and integral momentum equations. By discretizing the DRACS system in the axial direction, a bulk mean temperature is assumed for each mesh cell. The temperatures of all the cells, as well as the mass flow rates in the DRACS loops, are predicted by solving the governing equations that are obtained by integrating the energy conservation equation over each cell and integrating the momentum conservation equation over each of the DRACS loops. In addition, an intermediate heat transfer loop equipped with a pump has also been modeled in the code. This enables the study of flow reversal phenomenon in the DRACS primary loop, associated with the pump trip process. Experimental data from a High-Temperature DRACS Test Facility (HTDF) are not available yet to benchmark the code. A preliminary code validation is performed by using natural circulation experimental data available in the literature, which are as closely relevant as possible. The code is subsequently applied to the HTDF that is under construction at the Ohio State University. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 77(2015:Mar.)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 77(2015:Mar.)
- Issue Display:
- Volume 77 (2015)
- Year:
- 2015
- Volume:
- 77
- Issue Sort Value:
- 2015-0077-0000-0000
- Page Start:
- 115
- Page End:
- 128
- Publication Date:
- 2015-03
- Subjects:
- FHR -- DRACS -- Passive safety -- Natural circulation -- Numerical simulation -- One-dimensional
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2014.10.032 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 9016.xml