SVBR-100 module-type fast reactor of the IV generation for regional power industry

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

doi:10.1016/j.jnucmat.2011.04.038

Cited by 82 publications

(20 citation statements)

References 6 publications

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“…A global market assessment has predicted that the magnitude of the potential market for SMRs is about 65-85 GWe by the year 2035, provided the economics are competitive [2]. The SMR design concepts that have been proposed can be classified into numerous types such as the pressurized water reactor (PWR) [3][4][5], the boiling water reactor (BWR) [6], the liquid metal cooled fast reactor (LMFR) [7][8][9][10][11][12][13], the gas cooled fast reactor (GFR) [14,15] and the molten salt reactor (MSR) technologies [16,17]. Among these concepts, the liquid metal type lead or lead-bismuth eutectic (LBE) is generally chosen as the coolant for SMRs owing to its superior properties including a low melting point, high boiling point and chemical inertness with air and water.…”

Section: Introductionmentioning

confidence: 99%

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

et al. 2020

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In this study, a conceptual design was developed for a lead-bismuth-cooled small modular fast reactor SPARK-NC with natural circulation and load following capabilities. The nominal rated power was set to 10 MWe, and the power can be manipulated from 5 MWe to 10 MWe during the whole core lifetime. The core of the SPARK-NC can be operated for eight effective full power years (EFPYs) without refueling. The core neutronics and thermal-hydraulics design calculations were performed using the SARAX code and the natural circulation capability of the SPARK-NC was investigated by employing the energy conservation equation, pressure drop equation and quasi-static reactivity balance equation. In order to flatten the radial power distribution, three radial zones were constructed by employing different fuel enrichments and fuel pin diameters. To provide an adequate shutdown margin, two independent systems, i.e., a control system and a scram system, were introduced in the core. The control assemblies were further classified into two types: primary control assemblies used for reactivity control and power flattening and secondary control assemblies (with relatively smaller reactivity worth) used for power regulation. The load following capability of SPARK-NC was assessed using the quasi-static reactivity balance method. By comparing three possible approaches for adjusting the reactor power output, it was shown that the method of adjusting the coolant inlet temperature was viable, practically easy to implement and favored for the load following operation.

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Section: Introductionmentioning

confidence: 99%

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

et al. 2020

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“…The attractive features of SMRs include lower absolute overnight capital costs, fitness for small electricity grids, reduced infrastructure and staff requirements, possibility to incremental capacity increase, and possible non‐electric applications (potable water production, district heating, or hydrogen production) . Various design concepts of SMRs have been proposed based on the pressurized water reactor, the boiling water reactor, the liquid metal cooled fast reactor (LMFR), the gas cooled fast reactor, and the molten salt reactor technologies . Among all the SMR design concepts, the LMFR‐type SMR is considered as a competitive technology for the following advantages: the easy‐to‐implement long time operation, enhanced passive safety due to the operation of coolant near the atmospheric pressure and the negative reactivity feedback from fuel and core structure expansion, and simple reactivity control without concerns of fission products poisoning …”

Section: Introductionmentioning

confidence: 99%

“…Based on the nuclear power technology developed for the reactors of nuclear submarines, the SVBR‐100 reactor design was proposed at the Institute for Physics and Power Engineering in Russia . SVBR‐100 is a 280 MWth LBE‐cooled small modular fast reactor with 8 years operation without refueling, which incorporates a core, 2 main circulation pumps and steam generator modules in a reactor monoblock vessel.…”

Section: Introductionmentioning

confidence: 99%

“…Integral arrangement of the primary circuit equipment eliminates the primary circuit pipelines and valves. The combination of a reactor vessel and a guard vessel excludes the loss of coolant accidents . To enhance the transportability and passive safety of SPARK, selection of reflector material, detailed fuel assembly design, radial core power flattening, and a liquid absorber control system were investigated to achieve a compact and light‐weight core design for a long‐time operation without refueling.…”

Section: Introductionmentioning

confidence: 99%

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Conceptual core design study of an innovative small transportable lead-bismuth cooled fast reactor (SPARK) for remote power supply

Zhou

Chen

Shao³

et al. 2018

Int J Energy Res

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Summary An innovative small transportable lead‐bismuth cooled fast reactor, named SPARK, with rated power of 20 MWth is proposed to operate for 20 years without refueling as a remote power supply. The SPARK core neutronics and thermal‐hydraulics design and preliminary safety analysis were performed in the current study. In order to achieve a compact and light‐weight core design with enhanced transportability and passive safety, the selection of reflector materials, the optimization of fuel assembly design and radial core zoning loading, and the reactivity control system design were accomplished. MgO was selected as the optimal reflector material due to its good neutron reflecting characteristics and low density. The fuel assembly design was optimized to obtain a long lifetime of core and low peak cladding surface temperature. To flatten radial power distribution, 3 radial zones were designed with different fuel pin diameters. A liquid absorber control system was implemented using 6Li‐enriched liquid lithium as the neutron absorber, which significantly reduces the core height. To reduce the initial excess reactivity, fixed absorbers were installed in the scram assemblies for the first half life and then replaced by fixed reflectors for the second half life. Based on the parametric study, the optimized core design was determined, and the core neutronics and thermal‐hydraulics performances were evaluated. The objective core lifetime of 18 effective full power years was fulfilled with the compact and light‐weight core design, and the thermal design constraints were satisfied during the whole life. Both the control and scram systems proved to independently provide sufficient shutdown margins. Using the quasi‐static reactivity balance method, the passive safety characteristics of the optimized core design were analyzed based on 5 anticipated transients without scram. Passive shutdown was achieved due to the negative reactivity feedback. The critical design constraint of the peak cladding surface temperature was satisfied for all transients.

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“…During this project, the developments of a European Lead-cooled fast reactor (ELFR) and an Advanced Lead-cooled Fast Reactor European Demonstrator were underway (Alemberti and Frogheri, 2013). A smallscale modular LBE-cooled fast reactor SVBR and a lead-cooled fast reactor BREST were developed by Russia (Zrodnikov et al, 2006(Zrodnikov et al, , 2011. On account of the nice natural circulation performances of lead or LBE, some natural circulation lead-or LBEcooled fast reactors have been researched and developed.…”

Section: Introductionmentioning

confidence: 99%

Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor

Wang

et al. 2015

Progress in Nuclear Energy

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SVBR-100 module-type fast reactor of the IV generation for regional power industry

Cited by 82 publications

References 6 publications

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities

Conceptual core design study of an innovative small transportable lead-bismuth cooled fast reactor (SPARK) for remote power supply

Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor

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