Analysis of fluid fuel flow to the neutron kinetics on molten salt reactor FUJI-12

Indarta Kuncoro Aji, Abdul Waris, Sidik Permana

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Molten Salt Reactor is a reactor are operating with molten salt fuel flowing. This condition interpret that the neutron kinetics of this reactor is affected by the flow rate of the fuel. This research analyze effect by the alteration velocity of the fuel by MSR type Fuji-12, with fuel composition LiF-BeF2-ThF4-233UF4 respectively 71.78%-16%-11.86%-0.36%. Calculation process in this study is performed numerically by SOR and finite difference method use C programming language. Data of reactivity, neutron flux, and the macroscopic fission cross section for calculation process obtain from SRAC-CITATION (Standard thermal Reactor Analysis Code) and JENDL-4.0 data library. SRAC system designed and developed by JAEA (Japan Atomic Energy Agency). This study aims to observe the effect of the velocity of fuel salt to the power generated from neutron precursors at fourth year of reactor operate (last critical condition) with number of multiplication effective; 1.0155.

Original languageEnglish
Title of host publication5th International Conference on Mathematics and Natural Sciences, ICMNS 2014
EditorsAcep Purqon, Reuben Jih-Ru Hwu, Taufiq Hidayat, Hidetaka Arimura
PublisherAmerican Institute of Physics Inc.
ISBN (Electronic)9780735413245
DOIs
Publication statusPublished - Sep 30 2015
Externally publishedYes
Event5th International Conference on Mathematics and Natural Sciences, ICMNS 2014 - Bandung, Indonesia
Duration: Nov 2 2014Nov 3 2014

Publication series

NameAIP Conference Proceedings
Volume1677
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616

Other

Other5th International Conference on Mathematics and Natural Sciences, ICMNS 2014
CountryIndonesia
CityBandung
Period11/2/1411/3/14

All Science Journal Classification (ASJC) codes

  • Physics and Astronomy(all)

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