Plutonium and minor actinides utilization in thorium molten salt reactor

Abdul Waris; Indarta K. Aji; Novitrian; Rizal Kurniadi; Zaki Su'ud

doi:10.1063/1.4725445

Plutonium and minor actinides utilization in thorium molten salt reactor

Abdul Waris, Indarta K. Aji, Novitrian, Rizal Kurniadi, Zaki Su'ud

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

1 Citation (Scopus)

Abstract

FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/ ²³³U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA in FUJI-12. The reactor grade Pu was employed in the present study as a small effort of supporting THORIMS-NES scenario. The result shows that the reactor can achieve its criticality with the Pu & MA composition in the fuel of 5.96% or more.

Original language	English
Title of host publication	3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011
Pages	115-118
Number of pages	4
DOIs	https://doi.org/10.1063/1.4725445
Publication status	Published - 2012
Externally published	Yes
Event	3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011 - Bali, Indonesia Duration: Nov 14 2011 → Nov 17 2011

Publication series

Name	AIP Conference Proceedings
Volume	1448
ISSN (Print)	0094-243X
ISSN (Electronic)	1551-7616

Conference

Conference	3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011
Country/Territory	Indonesia
City	Bali
Period	11/14/11 → 11/17/11

All Science Journal Classification (ASJC) codes

Physics and Astronomy(all)

Access to Document

10.1063/1.4725445

Cite this

Waris, A, Aji, IK, Novitrian, Kurniadi, R & Su'ud, Z 2012, Plutonium and minor actinides utilization in thorium molten salt reactor. in 3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011. AIP Conference Proceedings, vol. 1448, pp. 115-118, 3rd International Conference on Advances in Nuclear Science and Engineering 2011, ICANSE 2011, Bali, Indonesia, 11/14/11. https://doi.org/10.1063/1.4725445

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abstract = "FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/ 233U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA in FUJI-12. The reactor grade Pu was employed in the present study as a small effort of supporting THORIMS-NES scenario. The result shows that the reactor can achieve its criticality with the Pu & MA composition in the fuel of 5.96% or more.",

author = "Abdul Waris and Aji, {Indarta K.} and Novitrian and Rizal Kurniadi and Zaki Su'ud",

year = "2012",

doi = "10.1063/1.4725445",

language = "English",

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series = "AIP Conference Proceedings",

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T1 - Plutonium and minor actinides utilization in thorium molten salt reactor

AU - Waris, Abdul

AU - Aji, Indarta K.

AU - Novitrian,

AU - Kurniadi, Rizal

AU - Su'ud, Zaki

PY - 2012

Y1 - 2012

N2 - FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/ 233U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA in FUJI-12. The reactor grade Pu was employed in the present study as a small effort of supporting THORIMS-NES scenario. The result shows that the reactor can achieve its criticality with the Pu & MA composition in the fuel of 5.96% or more.

AB - FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/ 233U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA in FUJI-12. The reactor grade Pu was employed in the present study as a small effort of supporting THORIMS-NES scenario. The result shows that the reactor can achieve its criticality with the Pu & MA composition in the fuel of 5.96% or more.

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DO - 10.1063/1.4725445

M3 - Conference contribution

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T3 - AIP Conference Proceedings

SP - 115

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ER -

Plutonium and minor actinides utilization in thorium molten salt reactor

Abstract

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Conference

All Science Journal Classification (ASJC) codes

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