Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100

Zrodnikov, A. V.; Toshinsky, G.I.; Komlev, O.G.; Dragunov, Yu. G.; Степанов, В. А.; Klimov, Nikolai N.; Kopytov, I. I.; Krushelnitsky, V.N.

doi:10.1016/j.nucengdes.2006.04.005

Cited by 48 publications

(15 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…RF SVBR-100 has been designed as a standardized reactor facility of equivalent power of ~100 MWe for multi-purpose usage as a component of modular nuclear plants or as autonomous power-sources for regional nuclear power [15].…”

Section: Reactor Facility Svbr-100mentioning

confidence: 99%

Modular Lead-Bismuth Fast Reactors in Nuclear Power

Toshinsky

Petrochenko²

2012

Sustainability

View full text Add to dashboard Cite

Abstract:On the basis of the unique experience of operating reactors with heavy liquid metal coolant-eutectic lead-bismuth alloy in nuclear submarines, the concept of modular small fast reactors SVBR-100 for civilian nuclear power has been developed and validated. The features of this innovative technology are as follows: a monoblock (integral) design of the reactor with fast neutron spectrum, which can operate using different types of fuel in various fuel cycles including MOX fuel in a self-providing mode. The reactor is distinct in that it has a high level of self-protection and passive safety, it is factory manufactured and the assembled reactor can be transported by railway. Multipurpose application of the reactor is presumed, primarily, it can be used for regional power to produce electricity, heat and for water desalination. The Project is being realized within the framework of state-private partnership with joint venture OJSC "AKME-Engineering" established on a parity basis by the State Atomic Energy Corporation "Rosatom" and the Limited Liability Company "EuroSibEnergo".

show abstract

Section: Reactor Facility Svbr-100mentioning

confidence: 99%

Modular Lead-Bismuth Fast Reactors in Nuclear Power

Toshinsky

Petrochenko²

2012

Sustainability

View full text Add to dashboard Cite

show abstract

“…This reactor presents primary and secondary cooling loops with liquid sodium at 653 K in the inlet stream and 788 K in the outlet stream respectively. The average reactor efficiency is estimated at 44.9% (Srinivasan et al, 2006, Zrodnikov et al, 2006 with an annual availability close to 80%. The water mass flow in the third circuit is 19.45 kg/s and the generated steam reaches a temperature of 753 K and a pressure close to 12 MPa.…”

Section: Operating Conditions Of the Reactormentioning

confidence: 99%

“…Moreover, this drawing off of 1% of the steam flow in a larger size reactor, such as sodium reactor BN-1800 (Zrodnikov et al, 2006), would allow an annual hydrogen production of 5.08 ǂ10 7 kg, which represents ~1% of the European hydrogen production (E4Tech, 2005). A drawing off at 2 MPa could be a feasible choice to obtain steam at ~483 K and to avoid steam condensation.…”

Section: Water Steam Drawing Off In the Turbinementioning

confidence: 99%

Hydrogen production by high temperature electrolysis coupled with an EPR, SFR or HTR: techno-economic study and coupling possibilities

Rivera-Tinoco

Mansilla

Bouallou

et al. 2008

IJNHPA

View full text Add to dashboard Cite

International audienceHydrogen production by high temperature electrolysis coupled with three nuclear reactors (the European pressurised reactor, the sodium-cooled fast reactor and the very high temperature reactor) was studied in terms of perspectives and hydrogen production costs. Firstly, we present the features of producing water steam by using the three nuclear reactors. Secondly, we present the hydrogen production cost for the HTE process coupled with each type of nuclear reactor. These costs are optimal values of the hydrogen production cost for the mentioned couplings and they were estimated by using a genetic algorithm procedure. High potentiality for these HTE couplings was assessed and contrary to steam source temperatures, the electricity price appeared to be a key parameter for low hydrogen production costs

show abstract

“…It can be expected that at the nearest first stage of implementation of fast reactors (FR) in the nuclear power (NP) in conditions of low costs of natural uranium and services on its enrichment, the operation of reactor SVBR-100 with use of oxide uranium fuel in an open NFC with postponed reprocessing of SNF will be more economically expedient than that in the closed NFC despite the fact of significantly higher (approximately by a factor of 2 -2.5 as compared with that of VVER-1000 reactors) specific (per 1 kWh) consumption of natural uranium. As an example, it was demonstrated by the results of conceptual project of the modular NPP with reactors SVBR-75/100 cooled by heavy liquid-metal coolant (HLMC) lead-bismuth alloy (2002) [2]. Use of that fuel enriched in less than 20% with postponed reprocessing of SNF is also the most expedient for the reasons of nonproliferation that is important when those reactors are exported to developing countries.…”

Section: Introductionmentioning

confidence: 99%

Safe Controlled Storage of SVBR-100 Spent Nuclear Fuel in the Extended-Range Future

Toshinsky¹,

Grigoriev²,

Dedul³

et al. 2019

WJNST

View full text Add to dashboard Cite

Experience of operating reactor facilities (RF) with lead-bismuth coolant (LBC) has revealed that it is possible to perform safe refueling in short terms if the whole core is replaced and a kit of the special refueling equipment is used. However, comparing with RFs of nuclear submarines (NS), in which at the moment of performance of refueling the residual heat release is small, at RF SVBR-100 in a month after the reactor has been shut down, at the moment of performance of refueling the residual heat release is about 500 kW. Therefore, it is required to place the spent removable unit (SRU) with spent fuel subassemblies (SFSA) into the temporal storage tank (TST) filled with liquid LBC, in which the conditions for coolant natural circulation (NC) and heat removal via the tank vessel to the water cooling system are provided. After the residual heat release has been lowered to the level allowing transportation of the TST with SRU in the transporting-package container (TPC), it is proposed to consider a variant of TPCs transportation to the special site. On that site after the SRU has been reloaded into the long storage tank (LST) filled with quickly solidifying liquid lead, the TPCs can be stored during the necessary period. Thus, the controlled storage of LSTs is realized during several decades untill the time when SNF reprocessing and NFC closing are becoming economically expedient. On that storage, the four safety barriers are formed on the way of the release of radioactive products into the environment, namely: fuel matrix, fuel element cladding, solid lead and steel casing of the LST.

show abstract

Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100

Cited by 48 publications

References 1 publication

Modular Lead-Bismuth Fast Reactors in Nuclear Power

Modular Lead-Bismuth Fast Reactors in Nuclear Power

Hydrogen production by high temperature electrolysis coupled with an EPR, SFR or HTR: techno-economic study and coupling possibilities

Safe Controlled Storage of SVBR-100 Spent Nuclear Fuel in the Extended-Range Future

Contact Info

Product

Resources

About