Intermediate Heat Exchanger (IHX) Effectiveness Calculation Of The Cogeneration System Of High Temperature Gas-Cooled Reactor (HTGR)
Ign. Djoko Irianto
Center For Reactor Technology and Nuclear Safety - BATAN
Kompleks Puspiptek Serpong, Tangerang Selatan
ABSTRACT
INTERMEDIATE HEAT EXCHANGER (IHX) EFFECTIVENESS CALCULATION OF THE COGENERATION SYSTEM OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR). Very High Temperature Reactor (VHTR) is a high temperature gas-cooled reactor (HTGR) which be a one of Generation IV reactors which is conceptually designed using cogeneration configuration for electric generation and for hydrogen production. VHTR employs a helium-coolant with operating pressure 5,0 MPa and 950oC outlet temperature. The main energy conversion component in VHTR cogeneration is intermediate heat exchanger (IHX). Thermal energy passes the IHX from the reactor system to the cogeneration system for electric generation and for hydrogen production or another application. The success of VHTR design is affected by many factors, one of which is the performance of IHX. To support the conceptual design, many factors which affect the IHX performance particularly high temperature IHX have to be examined, calculated and analyzed. Many factors which affect the IHX performance is namely effectiveness, total heat transfer, etc. In this research, the effectiveness of the conceptually designed of IHX which refer to IHX in GTHTR300C and the total heat transfer of IHX for the cogeneration systems have been calculated using variant of inlet temperature. Total IHX heat transfer and the effectiveness are calculated using ε-NTU (Number of Transfer Unit) method. With assumption of a helium-coolant used in the both side of IHX, the optimal effectiveness IHX is 0.95. Conceptually, it can be concluded that this IHX is effective to be used in the HTGR cogeneration based on VHTR.
Keywords: High temperature gas-cooled reactor (HTGR), cogeneration, IHX, effectiveness, efektivitas, metode number of transfer units (NTU method)
Published : Prosiding Seminar Nasional Ke-16 "TEKNOLOGI DAN KESELAMATAN PLTN SERTA FASILITAS NUKLIR", Surabaya, 28 Juli 2010
0 comments:
Post a Comment