SVBR-100 reactor

The SVBR-100 reactor is a prototype system under active design development by a consortium of Russian organizations including OKB Gidropress, the Institute of Physics and Power Engineering, and Atomenergoproekt Moscow. It is the reactor system most... 

Figure 12.5 SVBR-100 reactor. http //www.akmeengineering.com/398.html.

It is possible to use the SVBR reactor as a sub-critical blanket of a proton accelerator driven system for transmutation of long-lived radioactive waste [XIX-10]. 

Gidropress, 2011. SVBR Reactor Plants. Podolsk, Russia. 

Lead-bismuth reactors [2.25-2.30]. Two design concepts have been studied SVBR-75 (Fig. 2.4) and ANGSTREM. SVBR-75 is designed to produce 75 MW(e). The study explores the feasibility of designing an SVBR-like reactor core to operate for 10 years without refuelling. A transportable version of the reactor called ANGSTREM can produce 30 MW(th) or 6 MW(e) or a combination of heat and electricity. A version producing up to 25 MW(e) has also been studied. 

The possibility and expediency of developing the NP based on unified small power reactor modules SVBR-75/100 with fast neutron reactors cooled by lead-bismuth eutectic coolant (LBC) is substantiated for the nearest decades in the paper. 

The design of RI SVBR-75 have two-circuit scheme of LBC heat removal for the primary circuit and steam-water for the secondary circuit. The integral design of the pool type is used for the RI primary circuit (see Fig. 2). It enables to mount die primary circuit equipment inside the one vessel. RI SVBR-75 includes the removable part with the core (the reactor itself), 12 SG modules with compulsory circulation over the primary circuit and natural circulation over the secondary circuit, 2 main circulation pumps (MCP) for LBC circulation over die primary circuit, devices for controlling the LBC quality, the in-vessel radiation protection qrstem and buffer reservoir which are the parts of the main circulation circuit (MCC). 

PeaicTopHbift MOflyjib CBBP-75. Reactor plant module SVBR-75. 

PeaKTopHan ycTanoBKa CBBP-75 Reactor plant SVBR-75... 

VVER-440 SG, possibility of reactor module complete plant fabrication and its transportation by the railway, as well as closeness of the scale factor to NS s RIs that enables to use some developed technical solutions and reduce R D. For replacing the power capacities of the 2-nd unit four SVBR-75 modules are installed in SG compartments, and six modules are installed for each of 3-rd and 4-th units. 

On the basis of commercially produced modules SVBR-75/100 it is expedient to develop the design of modular NPP of large power (1 GW and more at the same unit). The prospect for that principle of designing NPP is shown in conceptual design developed in the USA (PRISM) [24] and in Japan (4S) [25]. However, use of this principle for LBC cooled reactors is the most effective. 

Along with it, this task can be solved on the basis of already mastered technology. For example, during eight years one reactor module SVBR-75/100 can transmute about 1000 kg of Pu (weapon or reactor one) into the form protected against unauthorized proliferation ( spent fuel standard ) at reducing its quality as a weapon material compared to the weapon Pu. In terms of 1 GWe - year 1,25 tons of Pu will be utilized in those reactors. If minor actinides (first of all amerithium) is introduced into fuel, their transmutation into short-lived radioactive wastes will take place. 

We can see it from Table 3 where tiie ratio of EUU for the SVBR-600 reactor with equivalent electric power of 625 MWe which has been considered as an example of realizing the FR operating in the open NFC, to EUU for WER-1000 reactor has been presented. This ratio demonstrates the increase of the functioning time for NP using SVBR-600 reactors in comparison with that using... 

WER-1000 ones in the open NFC under the same NPP s total power maintmned and NU resources. If the enrichment of make-up fuel is taken to be 4,4%, as it concerns the VVER-1000 reactor, then EUU for the SVBR-600 reactor would be three times of that for the WER-1000 reactor even in the fourth campaign. As a result, the consumption of natural uranium would decrease three times, i.e. die possible term of existing the open NFC would increase three times. 

TABLE 3. THE COMPARATIVE EFFICIENCY OF NATURAL URANIUM ENERGY POTENTIAL UTILIZATION. (THE INCREASE OF OPERATION TIME FORNP USING SVBR-600 REACTORS IN THE OPEN NFC IN COMPARISON WITH VVER-1000 UNDER THE SAME POWER AND NATURE URANIUM RESOURCES)... 

SVBR-75/100 (Russian Federation) Svinetc-Vismuth Bystriy Reactor (Lead-Bismuth Fast Reactor)... 

ZRODNIKOV, A.V., et al, Multipurposed reactor module SVBR-75/100, Proc. ICONE 8, 2-6 April 2000, Baltimore, MD, USA. 

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. 

SVBR- 75/100 Russian Federation XIX Fast reactor 101.5/ 280 6-8.8 UO2 pellets 16.1 MOX UN UN-PuN Forced circulation Pb-Bi 320/482 Indirect Rankine 6-8 years incl. prototype plant construction 1000 0.0146... 

In addition to the Pb-Bi cooled SVBR-75/100, two sodium cooled reactor concepts with a potential for nearer-term deployment have adapted established fast reactor fuel, coolant, structures, and component technologies to small sized plants of long refuelling interval, see Table 7. 

The nearer-term sodium cooled reactor concepts — 4S Toshiba Design (14) and MBRU-12 (16) — and the Pb-Bi cooled SVBR-75/100 (18) employ conventional core outlet temperatures in the range from 480 to 510°C and drive superheated Rankine steam cycles attaining conversion efficiencies near 39%. The number of loops transporting heat to the balance of plant never exceeds two. 

Some concepts intend to reduce the number of safety-related functions of the balance of plant, e.g., the SVBR-75/100 (18), or even to release the balance of plant from any nuclear safety function whatsoever, e.g., the STAR-H2 (29). Then, the balance of plant could be preconstructed or constructed in parallel to reactor site assembly by local companies and local labour to local building standards, and can be financed in local currency. 

A more detailed approach to achieve multi-plant clustering has already been elaborated for the MASLWR (5), SVBR-75/100 (18), and STAR-H2 (29) concepts. As an example, one version of the SVBR-75/100 concept comprises a cluster of sixteen plants altogether producing 1600 MW(e), see Fig. 8. Another version with smaller number of modules is being suggested for the renovation of older nuclear power plants with decommissioned larger-capacity reactors (ANNEX XIX). 

There are 11 concepts of small reactors without on-site refuelling that are currently being developed at different stages in the Russian Federation. Six of them are light water cooled reactors the UNITHERM (ANNEX II), the ELENA (ANNEX III), the VBER-150 (ANNEX IV), the ABV (ANNEX V), the KLT-20 (ANNEX VI), and the VKR-MT (ANNEX X). In addition, there is one small gas cooled fast reactor concept which is the BGR-300 (ANNEX Xm) two sodium cooled reactor concepts the MBRU-12 (ANNEX XVI), and the BN GT-300 (ANNEX XVItl) and one lead-bismuth cooled small reactor design, the SVBR-75/100 (ANNEX XIX). Finally, there is one non-conventional reactor concept the MARS (ANNEX XXVIII). 

The SVBR-75/100 (ANNEX XIX) is a modular multi-purpose lead-bismuth cooled fast reactor of 75 to lOOMW(e), offering a refuelling interval of 6 to 9 years. The design is backed by the experience of 50 years in design and operation of reactor installations with lead-bismuth coolant for nuclear submarines, available in the Russian Federation. Specifically, the marine prototypes of the SVBR-75/100 have achieved a total of 80-years of operating experience. 

A list of basic R D and tests to be performed at the detailed design stage has been prepared, ANNEX XIX. In addition, in order to provide a more flexible supply of energy, IPPE and Gidropress also develop a smaller version of lead-bismuth cooled reactor — the SVBR-10 of lOMW(e). 

Being a small sized reactor plant, the BN GT-300 has certain similarities in the design philosophy, design approaches and certain technologies with other SMRs, such as VBER-300 [XVm-2, XVm-3] VK-300 [XVm-2, XVm-3] GT-MHR [XVm-3] KLT-40 [XVm-2] SVBR-75/100 [XVm-6, XVm-7] and others [XVIH-S, to XVIH-IO]. 

XVni-7] IGNATENKO, E.I., et al.. Use of SVBR-75 reactor plant in design of renovation of NPP units of the first generation after termination of their service life, Heavy-Liquid Metal Coolants in Nuclear Technology (Proc. of Conf), Vol. 2, Paper No. B.5, p. 366 (Obninsk, Russia, 1999). 

LEAD BISMUTH COOLED FAST REACTOR SVBR-75/100... 

The SVBR-75/100 is a modular multi-purpose lead-bismuth cooled fast reactor of the equivalent electric power between 75 and 100 MW(e), depending on steam parameters. 

In 2001, the abovementioned experts developed a conceptual design of the two-unit NPP based on thirty two SVBR-75/100 reactor modules the output of each of the units is 1600 MW(e) [XIX-6]. 

At the beginning of 2004, the development of multi-purpose nuclear power sources based on the SVBR-75/100 reactor modules has been being initiated by FSUE SSC RF IPPE, FSUE EDO Gidropress , and FSUE Atomenergoproekt . 

Standardized SVBR-75/100 reactor modules will incorporate many inherent safety features... 

The most economically effective area of SVBR-75 use could be the renovation of NPP units with thermal reactors after the expiration of their lifetime. Such renovation could be performed by installing the SVBR-75/100 modules in the steam-generator (SG) and the main circulation pump (MCP) compartments of these NPPs after the decommissioning and dismantling of the equipment installed previously. The results of technical feasibility study and economic evaluation of the renovation of the 2" , 3, and d " units of the Novovoronezhskaya NPP with the SVBR-75 reactor modules show that the specific capital costs can be reduced by a factor of two compared with the construction of new replacement power capacities [XIX-5] ... 

Currently, activities have been started to determine the possibility of using the SVBR type reactors as a power sources to produce synthetic motor fuel and oil from brown coal with a hydrogenation method ... 

The SVBR-75/100 project has been devised using a conservative approach. This presumes to use the primary and secondary circuit design and operation parameters already proven in practice, the mastered technologies of fuel and structural materials, and those principal engineering solutions regarding the equipment components and the reactor scheme that have been verified by operating experience. 

Such an approach is to assure that the technical solutions used in lead-bismuth cooled nuclear submarine reactors are to a great extent inherited by the SVBR-75/100 design. Adhering to this approach could reduce the implementation terms, the R D scope and the cost and the investment risk, and would favour the improved reliability and safety of the reactor installation. 

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