UTILIZATION OF REACTOR GRADE PLUTONIUM AS ENERGY MULTIPLIER IN THE LIFE ENGINE

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Date

2012

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Amer Nuclear Soc

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Department of Mechanical Engineering
(2016)
The Mechanical Engineering Doctoral Program has started in 2016-2017 academic year. We have highly qualified teaching and research faculty members and strong research infrastructure in the department for graduate work. Research areas include computational and experimental research in fluid and solid mechanics, heat and mass transfer, advanced manufacturing, composites and other advanced materials. Our fundamental mission is to train engineers who are able to work with advanced technology, create innovative approaches and authentic designs, apply research methods effectively, conduct research and develop high quality methods and products in space, aviation, defense, medical and automotive industries, with a contemporary education and research infrastructure.

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Abstract

The accumulated reactor grade (RG)-plutonium as nuclear waste of conventional reactors is estimated to exceed 1700 tonnes. Laser Inertial Confinement Fusion Fission Energy (LIFE) engine is considered to incinerate RG-plutonium in stockpiles. Calculations have been conducted for a constant fusion driver power of 500 MWth in S-8-P-3 approximation using 238-neutron groups. RG-plutonium out of the nuclear waste of LWRs is used in form of fissile carbide fuel in TRISO particles with volume fractions of 2, 3, 4, 5 and 6 %, homogenously dispersed in the Flibe coolant. Respective tritium breeding ratio (TBR) values per incident fits ion neutron are calculated as TBR = 1.35, 1.52, 1.73, 2.02 and 2.47 at start-up. With the burn up of fissionable RG-Pu isotopes in the coolant, TBR decreases gradually. Similarly, blanket energy multiplications are calculated as M-0 = 3.8, 5.5, 7.7, 10.8 and 15.4 at start-up, respectively. Calculations have indicated prospects of achievability of very high burn up values (> 400 000 MD.D/MT).

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Turkish CoHE Thesis Center URL

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7

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Q4

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Source

15th International Conference on Emerging Nuclear Energy Systems -- MAY 15-19, 2011 -- San Francisco, CA

Volume

61

Issue

1T

Start Page

216

End Page

221

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