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Title: Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR)

Abstract

A conceptual design study on Very Small Pb-Bi No-Onsite Refueling Cooled Nuclear Reactor (VSPINNOR) with Uranium nitride fuel using MCNPX program has been performed. In this design the reactor core is divided into three regions with different enrichment. At the center of the core is laid fuel without enrichment (internal blanket). While for the outer region using fuel enrichment variations. VSPINNOR fast reactor was operated for 10 years without refueling. Neutronic analysis shows optimized result of VSPINNOR has a core of 50 cm radius and 100 cm height with 300 MWth thermal power output at 60% fuel fraction that can be operated 18 years without refueling or fuel shuffling.

Authors:
 [1];  [2];  [3]
  1. Laboratory of Nuclear and Biophysics, Department of Physics, Bandung Institute of Technology, Jl. Ganesha 10, Bandung 40132, Indonesia and Laboratory of Atom and Nuclear, Department of Physics, Diponegoro University, Jl. Prof. Soedarto, S.H., Tembala (Indonesia)
  2. Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology (Ganesha 10 Bandung, Indonesia) (Indonesia)
  3. Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency, Kawasan Puspiptek, Gedung No. 80, Serpong, Tangerang 15310 (Indonesia)
Publication Date:
OSTI Identifier:
22307874
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1615; Journal Issue: 1; Conference: ICANSE 2013: 4. international conference on advances in nuclear science and engineering, Denpasar, Bali (Indonesia), 16-19 Sep 2013; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BREEDING BLANKETS; COMPUTER CALCULATIONS; DESIGN; FAST REACTORS; LIQUID METAL COOLED REACTORS; M CODES; REACTOR CORES; VARIATIONS

Citation Formats

Arianto, Fajar, E-mail: ariantofajar@gmail.com, Su'ud, Zaki, E-mail: szaki@fi.itba.c.id, and Zuhair. Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR). United States: N. p., 2014. Web. doi:10.1063/1.4895865.
Arianto, Fajar, E-mail: ariantofajar@gmail.com, Su'ud, Zaki, E-mail: szaki@fi.itba.c.id, & Zuhair. Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR). United States. doi:10.1063/1.4895865.
Arianto, Fajar, E-mail: ariantofajar@gmail.com, Su'ud, Zaki, E-mail: szaki@fi.itba.c.id, and Zuhair. Tue . "Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR)". United States. doi:10.1063/1.4895865.
@article{osti_22307874,
title = {Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR)},
author = {Arianto, Fajar, E-mail: ariantofajar@gmail.com and Su'ud, Zaki, E-mail: szaki@fi.itba.c.id and Zuhair},
abstractNote = {A conceptual design study on Very Small Pb-Bi No-Onsite Refueling Cooled Nuclear Reactor (VSPINNOR) with Uranium nitride fuel using MCNPX program has been performed. In this design the reactor core is divided into three regions with different enrichment. At the center of the core is laid fuel without enrichment (internal blanket). While for the outer region using fuel enrichment variations. VSPINNOR fast reactor was operated for 10 years without refueling. Neutronic analysis shows optimized result of VSPINNOR has a core of 50 cm radius and 100 cm height with 300 MWth thermal power output at 60% fuel fraction that can be operated 18 years without refueling or fuel shuffling.},
doi = {10.1063/1.4895865},
journal = {AIP Conference Proceedings},
number = 1,
volume = 1615,
place = {United States},
year = {Tue Sep 30 00:00:00 EDT 2014},
month = {Tue Sep 30 00:00:00 EDT 2014}
}
  • In this study application of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Reactors for small long life reactors with natural Uranium as Fuel Cycle Input has been performed. The reactor cores are subdivided into several parts with the same volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2, and 10 years after that it is shifted to region 3. This concept is applied to all regions, i.e. shifted the core of I'th region into I+1 region after themore » end of 10 years burn-up cycle. The first region 1 is filled by fresh natural uranium fuel. Compared to the previous works, in a smaller reactor core the criticality need to be considered more carefully especially at the beginning of life. As an optimized design, a core of 85 cm radius and 150 cm height with 300 MWt power are selected. This core can be operated 10 years without refueling or fuel shuffling. The average discharge burn-up is 350 GWd/ton HM.« less
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