SVBR

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. 

The principal technical parameters of RI SVBR-75 are presented in Table 1. 

RI SVBR-75 operates for eight years without core refueling. During this period there is no need in carrying out fuel works. At the initial stage the use of mastered oxide uranium fuel in the uranium... 

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

RI SVBR-75/100 is designed on the design base of RI SVBR-75 and distinguishes from it only by SG operating in one through regime and generating the superheated ste°am of 400°C temperature and 9 MPa pressure. Thus the electric power is ensured to be of about 100 MWe. 

SVBR-75 nominal power is chosen to be 75 MWe due to limited dimensions of NVNPP renovation units SG compartments which do not enable to install the large power module, necessity for ensuring the equalify of generated steam and feeding water consumption for SVBR-75 and RI... 

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. 

RI SVBR-75/100 meets these requirements the most completely. It has extremely high safety potential, lifetime duration needed, ensures the regime of non-proliferation due to the following ... 

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. 

The safety level needed will be ensured due to developed propertied of RI SVBR-75/100 inherent safety which have been mentioned above. 

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)... 

---