Authors & Affiliations
Blokhin D.А., Zemskov E.A., Khorasanov G.L.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Abstract
In the paper neutron spectra of fast reactor cooled with lead–
bismuth or lead-208 are given. It is shown that in changing the coolant from lead-bismuth to
lead-208 the core neutron spectra of the FR RBEC-M are hardening in whole on several percents
while a little share of low energy neutrons (5 eV – 50 keV) is slightly increasing. Neutron
spectra hardening and low neutron absorption in the coolant permit to increase the effective
neutron multiplication factor, Kef, while the increased share of low energy neutrons provides
more effective conversion of uranium-238 or technetium-99 due to peculiarity of their neutron
capture cross sections.
Keywords
lead-208, coolant, lead-bismuth, neutron fluxes, effective
neutron multiplication factor, neutrons, range, intermediate-energy neutrons, thermal neutrons, fast neutrons
Article Text (in Russian, PDF)
References
1. Horasanov G.L., Korobejnikov V.V., Ivanov A.P., Blohin A.I. Minimizacija uran-plutonievoj
zagruzki bystrogo reaktora putem ispol'zovanija v kachestve teplonositelja malo pogloshhajushhego nejtrony obogashhennogo svinca-208. Sbornik dokladov XII-j Mezhdunarodnoj nauchnoj konferencii «Fiziko-himicheskie processy pri selekcii atomov i molekul i v lazernyh, plazmennyh i nanotehnologijah», 31 marta – 4 aprelja 2008, Zvenigorod, Russia. Pod redakciej V.E. Cherkovca. M.:CNIIatominform, Troick: GNC RF TRINITI, 2008, pp.384-391. [in Russian]
2. G.L. Khorasanov, V.V. Korobeynikov, A.P. Ivanov, A.I. Blokhin. Minimization of an initial fast reactor uranium-plutonium load by using enriched lead-208 as a coolant. Nuclear Engineering and Design,
2009, v. 239, No 9, pp. 1703-1707.
3. Horasanov G.L., Blohin A.I. Makroskopicheskie sechenija radiacionnogo zahvata nejtronov
teplonositelem, uranom-238 i tehneciem-99 v aktivnoj zone podkriticheskogo reaktora, ohlazhdaemogo prirodnym i obogashhennym svincom. Perspektivnye materialy, 2010, special'nyj vypusk No.8. pp. 361-365. [in Russian]
4. Alekseev P.N., Vasil'ev A.V., Mikitjuk K.O., Subbotin S.A., Fomichenko P.A., Shhepetina T.D.
Optimizacija konceptual'nyh reshenij dlja svincovo-vismutovogo bystrogo reaktora RBEC-M.
// Atomnaja jenergija, 2004, v. 97, No. 2, p. 115. [in Russian]
5. MCNP – A General Monte Carlo N-Particle Transport Code, Version 4C. LA-13709-M, J.F.
Briesmeister, Ed., Los Alamos National Laboratory, 2000.
6. R.E. Macfarlane and D.W. Muir. The NJOY Nuclear Data Processing Version 91. LA-12740-M, Los
Alamos National Laboatory, 1994.
UDC 621.039.546
Problems of Atomic Science and Technology. Series: Nuclear Constants, issue 1-2, 2010
