Institute for Physics and Power Engineering

During 1962 - 1997 a munber of NSs with lead-bismuth LMC in the primary circuit were in operation in the Russian Navy. Reactors of such NSs developed imder scientific management of the Russian Research Center Institute for Physics and Power Engineering (RRC IPPE, below IPPE), Obninsk, fall into the category of intermediate-neutron reactors [1]. Fuel composition of LMC reactors comprises intermetallic compoimd UBen with enrichment up to 90 % dispersed over beryllium matrix. Some characteristics of such-type NSs are demonstrated in Table 1. 

Ignatiev, C., Pankratov, D., Toshinskiy G., et al. (2004) Nuclear and Radiation Safety during Spent Nuclear Fuel Storage of Land-based Stands Prototypes of Naval Liquid-metal Coolant Power Reactor Installations - Final Report under the ISTC Project 2710p between the Russian Research Center Institute for Physics and Power Engineering (RRC IPPE) and the Brookhaven National Laboratory of the US Department of Energy, Obninsk (in Russian). 

Studies made at the Institute for Physics and Power Engineering have confirmed the possibility of achieving BR = BRcore= 1 with typical for LMFRs volumetric fraction of nitride fuel in the core of sodium cooled 800-1600 MW(e) reactor, its core overall dimensions being much lower than those of lead cooled reactor [2.31]. 

State Scientific Center of the Russian Federation (SSC RF) — Institute for Physics and Power Engineering (IPPE), Obninsk, Russian Federation... 

The Advisory Group Meeting (AGM) on Propulsion Reactor Technologies for Civilian Applications was held in Obninsk, Russian Federation, 20-24 July 1998. The AGM was convened by the International Atomic Energy Agency (IAEA) and was hosted by the Federal Scientific Centre, Institute of Physics and Power Engineering (IPPE). 

The IAEA would like to express its thanks to all those who took part in the AGM, and particularly to the Institute of Physics and Power Engineering (IPPE) for hosting the meeting. Special thanks go to V. Chitaykin (IPPE, Obninsk, Russian Federation) and to S. Kazakov (JSC Malaya Energetika, Moscow) for assisting in the preparation of this publication. 

Institute of Physics and Power Engineering, Russian Federation Indira Gandhi Center for Atomic Research, India China Institute of Atomic Energy, China... 

Although it is explicitly mentioned in conjunction with only two designs of small reactors described in this report — the SVBR-75/100 (ANNEX XIX) and the BN GT-300/100 (ANNEX XVIII), both coming from the Institute of Physics and Power Engineering (IPPE) of the Russian Federation — an option to use such reactors for the so-called renovation of decommissioned older power plants, i.e., after necessary checks, to use the remaining premises and infrastructure and balance of plant of these older plants to accommodate and plug-in certain number of small reactor modules for another decades of operation, should be mentioned as another market opportunity for small reactors without on-site refuelling. 

Bulkin, S.Yu, Lemekhov, V.V., Sila-Novitsky, A.G., et al., 2011. Research and development for demonstration of fuel performance in the BREST-OD-300 core. In IAEA Technical Meeting Design, Manufacture and In-pile Behaviour of Fast Reactor Fuel. Institute of Physics and Power Engineering, Obninsk, Russia. 

HeXe was the assumed coolant and working fluid for initial engineering work on the Project Prometheus Space Nuclear Power Plant (SNPP). The recommended method to calculate the viscosity and thermal conductivity of pure hehum and pure xenon is to use equations provided by the Design Institute for Physical Property Data (DIPPR) (Daubert et al., 1992). These equations are produced from curve fits of empirical data. The recommended method to calculate the viscosity and thermal conductivity of HeXe mixtures is the theoretical approach described by Hirschfelder (Hirschfelder, Curtiss, and Bird, 1954) with the addition of two higher order thermal conductivity correction factors described by Kestin (Kestin et al., 1984) and Singh (Singh, Dham, and Gupta, 1992). 

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