Assessment Of The Performance Of Intermediate Heat Exchanger On VHTR Reactor Cogeneration System

ASSESSMENT OF THE PERFORMANCE OF INTERMEDIATE HEAT EXCHANGER ON VHTR REACTOR COGENERATION SYSTEM

Ign. Djoko Irianto
Center for Reactor Technology and Nuclear Safety – BATAN
Kompleks Puspiptek Serpong, Tangerang Selatan
ABSTRACT
ASSESSMENT OF THE PERFORMANCE OF INTERMEDIATE HEAT EXCHANGER ON VHTR REACTOR COGENERATION SYSTEM. Very High Temperature Reactor (VHTR) is 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 7 MPa and 1000oC 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. The success of VHTR design is affected by many factors, one of which is the performance of IHX. This paper describes the results of the assessment of IHX performance in VHTR cogeneration system. The performance of IHX is influenced by some parameters such as: effectiveness of IHX, efficiency of IHX, and the configuration of IHX in the cogeneration system. There are three configuration systems assessed: direct cycle with secondary heat exchanger (SHX), direct cycle without SHX, and indirect cycle. The assessment are performed by comparing the parameter of IHX performance in the three configuration systems. The results of the assessment show that the highest efficiency is given by the direct cycle with SHX and the IHX is set in parallel with PHX. Despite its low efficiency, the third configuration obtains the highest effectiveness. This configuration in which electricity is generated indirectly has possibility to be used for a compact system design.

Key words : VHTR cogeneration system, intermediate heat exchanger (IHX), IHX system configuration, IHX efficiency, IHX effectiveness
Published : Prosiding Seminar Nasional Ke-15 "TEKNOLOGI DAN KESELAMATAN PLTN SERTA FASILITAS NUKLIR", Surakarta, 17 Oktober 2009