#TITLE_ALTERNATIVE#

• Main Author: WULANDARI (NIM: 10211041), CICI
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/19986
• Institution: Institut Teknologi Bandung

The development of nuclear reactors is currently done in terms of improving security, safety, reduction in the amount of waste and increasing protection on the issue of proliferation. One reactor which is currently being developed is Molten Salt Reactor (MSR) type Fuji-U1. This reactor has been developed in Japan. The fuel used in the form of molten salt with composition 71.76% of LiF, 16% of BeF2, 12% of ThF4 and 0.24% of 233UF4, and graphite as moderator. In this study, it was conducted the neutronic analysis, i.e. on the effective multiplication factor which states the critical parameter of the reactor. In addition, it was used also some combinations of the fuel composition in order to obtain the exact composition to reach the criticality of reactor in 20 years. The size of fuel lines was varied according to volume ratio of fuel/graphite from the core 1, core 2, and core 3. The used fuel was composed of two type, 233U and Plutonium (reactor grade Plutonium). <br /> <br /> <br /> Analysis was done by using SRAC (Ver.2002) and JENDL 3.2. Based on the calculation, using fuel 233U, reactor is in critical condition with fuel composition: 71.76% of LiF, 16% of BeF2, 11.81% of ThF4 and 0.43% of 233UF4 (core 1), 71.76% of LiF, 16% of BeF2, 11.88% of ThF4 and 0.36% of 233UF4 (core 2), and 71.76% of LiF, 16% of BeF2, 11.75% of ThF4 and 0.49% of 233UF4 (core 3). While using Plutonium (reactor grade plutonium), reactor is in critical condition with fuel composition: 71.76% of LiF, 16% of BeF2, 8.24% of ThF4 and 4.00% of *PuF4 (core 1), <br /> <br /> <br /> 71.76% of LiF, 16% of BeF2, 8.34% of ThF4 and 3.90% of *PuF4 (core 2), and 71.76% of LiF, 16% of BeF2, 8.30% of ThF4 and 3.94% of *PuF4 (core 3). The concentration of 233U is less than Plutonium, because the reactor grade Plutonium composed by fertile and fisil materials. Fertile material can absorb neutron in core reactor.