Dl. Moses et al., PLUTONIUM DISPOSITION IN THE BN-600 FAST-NEUTRON REACTOR AT THE BELOYARSK NUCLEAR-POWER-PLANT, Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 414(1), 1998, pp. 28-35
In 1996, the United States and the Russian Federation completed an ini
tial joint study that evaluated the candidate options for the disposit
ion of surplus weapons-derived plutonium in both countries. While Russ
ia advocates building new reactors for converting weapons-derived plut
onium to spent Fuel, the cost is high, and the continuing joint study
of the Russian options is considering only the use of the existing VVE
R-1000 LWRs in Russia land possibly in Ukraine) and the existing BN-60
0 fast-neutron reactor at the Beloyarsk Nuclear Power Plant in Russia.
The BN-600 reactor, which currently uses enriched uranium fuel, is ca
pable with certain design modifications of converting up to 1.3 metric
tons (MT) of surplus weapons-derived plutonium to spent fuel each yea
r. The steps needed to convert BN-600 to a plutonium-burner core will
be discussed. The step involving the hybrid core allows an early and t
imely start that takes advantage of the limited capacity for fabricati
ng uranium-plutonium mixed-oxide Fuel early in the disposition program
. The design lifetime of BN-600 must safely and reliably be extended b
y 10 yr to at least 2020 so that a sufficient amount of plutonium (sim
ilar to 20 MT) can be converted to spent fuel. Published by Elsevier S
cience B.V.