Authors & Affiliations

Skobelev A.N., Nikolaev A.A., Soshnikov A.A., Stepanov V.S.
Experimental and Design Organization "GIDROPRESS", Podolsk, Russia

Skobelev A.N. – Design Engineer 2 grade, Experimental and Design Organization "GIDROPRESS". Contacts: 21, Ordzhonikidze st., Podolsk, Moscow region, Russia, 142103. Tel.: +7(495) 502-79-13 add. 1786; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nikolaev A.A. – Deputy of Department Chief, Cand. Sci. (Tech.), Experimental and Design Organization "GIDROPRESS".
Soshnikov A.A. – Head of Department, Experimental and Design Organization "GIDROPRESS".
Stepanov V.S. – Chief Designer-Deputy Director, Experimental and Design Organization "GIDROPRESS".

Abstract

At present for solution of prospective features in front of nuclear-power engineering, at EDO "GIDROPRESS" on a base of lead-bismuth reactor technologies the projects of low-power reactors alike LBFR (Lead-Bismuth fast reactor) are developing to creation a power-supplyer on a range of powers from ~6 till 100 MWe against customer requirements.

When a novel reactor facility with lead-bismuth coolant (FB with LBC) is putting into operation, on a first criticality phase must be realized experimental researches to definition fact values of core base neutron-physical characteristics (NPC) and providing to NP-082-07 demands. In case of getting negative results core must be assembling again with replacement some fuel assemblies or elements. Realization this actions after contacting fuel elements with coolant is expensive and potentially dan-gerous operation. Therefore, as may be necessary, preliminary physical measurements could be real-ized in reactor module without coolant or by using receiving-passing critical facility. In this case ab-sence of coolant between fuel elements will bring to discrepancy of measured and actual (projected) characteristics, which scale for range of powers facilities, developing in EDO "GIDROPRESS" is ap-preciated in this paper.

Among main results of this paper noted influence absence of coolant in core decrease in proportion as increasing of core dimensions. Also observed weak sensitivity of concerned functionals to pres-ence/absence of coolant for largest model (alike SVBR-100), i.e. opportunity of fact confirmation of projected NPC by realization core tests without coolant.

Keywords
reactor facility, experimental research, neutron-physical characteristics, fuel rod array, fuel element, lead-bismuth coolant, core, receiving-passing critical facility, absorbing rods, MCNP5, effective neutron multiplication factor, group spectrum

Article Text (PDF, in Russian)

References

UDC 004.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2017, issue 2, 2:2