International Conference on Advances in Nuclear Science and Engineering in Conjunction with LKSTN 2007 (217-219) Design Study and Analysis of Pb-Bi Cooled Fast Reactor for Hydrogen Production Epung Saepul Bahrum 1 *, Zaki Su’ud 1 , Abdul Waris 1 , Bambang Ari Wahjoedi 2 1 Laboratory of Nuclear Reactor, Department of Physics, Institut Teknologi Bandung Jl. Ganesa 10 Bandung 40132, Indonesia 2 Department of Mechanical Engineering, Universiti Teknologi PETRONAS Bandar Seri Iskandar, Tronoh 31750,Perak Darul Ridzuan, Malaysia *E-mail: epung.saepul.bahrum@students.itb.ac.id Abstract DESIGN STUDY AND ANALYSIS OF PB-BI COOLED FAST REACTOR FOR HYDROGEN PRODUCTION. The capability of 200 MWt Pb-Bi cooled fast reactor to operate at average coolant outlet temperature 550 0 C and satisfy safety requirement give an opportunity this reactor as a heat source for hydrogen production. In this study 200 MWt Pb-Bi cooled fast reactor for hydrogen production have been designed. The reactor designed by ULLFR design concept. Neutronic and Thermal hydraulic analysis performed by FI-ITB- CHI software packed. In twenty years reactor operation time, the reactivity swings less than one dollar. The average and maximum coolant outlet temperature are 550 0 C and 621 0 C. The steam membrane reforming process has been implemented in this study. Base on simulation showed that hydrogen production unit thermal power is 7.1 MWt and produce gas hydrogen 310.03 kmol/h. The surplus reactor power could be utilized for generating electricity. Keywords: Pb-Bi Cooled Fast Reactor, Steam Membrane Reforming, Hydrogen Production 1. Introduction Pb-Bi cooled small reactor has been developed intensively by Su’ud et all [1-3]. Ones of the interesting result of Su’ud et all research is the reactor which power is 150 MWt, Pb-Bi cooled, UN- PuN fueled could operate at average coolant outlet temperature 550 0 C. At that condition reactor satisfied safety requirement [1]. Average coolant outlet temperature 550 0 C is corresponding to reaction temperature of steam membrane reforming hydrogen production process. Steam membrane reforming process has great attention because this process could produce pure H 2 and also reaction temperature could take place at temperature 550 0 C [4,5]. Chikazawa has been design sodium cooled fast reactor for hydrogen production using steam membrane reforming process [6]. Design and analysis of Pb-Bi Cooled Fast Reactor for hydrogen production using steam membrane reforming process have been performed in this study. 2. Nuclear reactor and hydrogen production unit configuration Nuclear reactor hydrogen production configuration consists of nuclear reactor, intermediate heat exchanger and hydrogen production unit. This configuration illustrated by figure 1. Design reactor based on ULLFR (Ultra Long Life Fast Reactor) design [7]. Reactor power is 200 MWt, cooled by Pb-Bi and reactor designed to operate until twenty years without refueling and fuel shuffling. Neutronic analysis showed that reactivity swing less than one dollar in whole reactor operation time [8]. The reactor is designed as heat source for hydrogen production so the average coolant outlet temperature designed around chemical reaction temperature of hydrogen production. Thermo hydraulic analysis showed that average and maximum coolant temperature are 550 0 C and 621 0 C [8]. In that condition reactor could be as energy source for hydrogen production using steam membrane reforming process and the Pb-Bi corrosion could be reduced. Neutronic and thermal hydrolic analysis performed by FI-ITB-CHI software packed [9]. 217 Table of Contents