Innovative nuclear technology based on modular multi-purpose lead–bismuth cooled fast reactors

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

doi:10.1016/j.pnucene.2007.10.025

Cited by 38 publications

(14 citation statements)

References 3 publications

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“…More recently, a once‐for‐life fast breeder core encapsulated nuclear heat source (ENHS) has been designed by the University of California at Berkeley with 125 MW (thermal) power, a lead or lead‐bismuth coolant, and nearly zero burnup reactivity swing throughout 20 years of full‐power operations . Another lead‐bismuth fast reactor is SVBR‐100 developed by AKME Engineering, Russian Federation, which can achieve 7 to 8 years of fuel cycle . When comparing small modular liquid‐metal fast reactor (SMLFR) to those reactors, the SMLFR has a smaller thermal power of 37.5 MW, leading to a cycle length of a possible maximum of 30 years—up to 10 years longer than other reactors.…”

Section: Introductionmentioning

confidence: 99%

“…9 Another lead-bismuth fast reactor is SVBR-100 developed by AKME Engineering, Russian Federation, which can achieve 7 to 8 years of fuel cycle. 10 When comparing small modular liquid-metal fast reactor (SMLFR) to those reactors, the SMLFR has a smaller thermal power of 37.5 MW, leading to a cycle length of a possible maximum of 30 years-up to 10 years longer than other reactors. Another possibility is the small modular reactor (SMR) [11][12][13] which has been developed as one of the most distinctive options for LFR design.…”

Section: Introductionmentioning

confidence: 99%

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Core design of long‐cycle small modular lead‐cooled fast reactor

et al. 2018

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Summary A core design of small modular liquid‐metal fast reactor (SMLFR) cooled by lead‐bismuth eutectic (LBE) was developed for power reactors. The main design constraint on this reactor is a size constraint: The core needs to be small enough so that (1) it can be transported in a spent nuclear fuel (SNF) cask to meet the electricity demands in remote areas and off‐grid locations or so that (2) it can be used as a power source on board of nuclear icebreaker ships. To satisfy this design requirement, the active core of the reactor is 1 m in height and 1.45 m in diameter. The reactor is fueled with natural and 13.86% low‐enriched uranium nitride (UN), as determined through an optimization study. The reactor was designed to achieve a thermal power of 37.5 MW with an assumption of 40% thermal efficiency by employing an advanced energy conversion system based on supercritical carbon dioxide (S‐CO2) as working fluid, in which the Brayton cycle can achieve higher conversion efficiencies and lower costs compared to the Rankine cycle. The outer region of the core with low‐enriched uranium (LEU) performs the function of core ignition. The center region plays the role of a breeding blanket to increase the core lifetime for long cycle operation. The core working fluid inlet and outlet temperatures are 300°C and 422°C, respectively. The primary coolant circulation is driven by an electromagnetic pump. Core performance characteristics were analyzed for isotopic inventory, criticality, radial and axial power profiles, shutdown margins (SDM), reactivity feedback coefficients, and integral reactivity parameters of the quasi‐static reactivity balance. It is confirmed through depletion calculations with the fast reactor analysis code system Argonne Reactor Computation (ARC) that the designed reactor can be operated for 30 years without refueling. Preliminary thermal‐hydraulic analysis at normal operation is also performed and confirms that the fuel and cladding temperatures are within normal operation range. The safety analysis performed with the ARC code system and the UNIST Monte Carlo code MCS shows that the conceptual core is favorable in terms of self‐controllability, which is the first step towards inherent safety.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Core design of long‐cycle small modular lead‐cooled fast reactor

et al. 2018

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“…The LFR shows great potential for industrial development due to the excellent transmutation capacity and inherent safety [1]. Motived by the properties, a lot of research has been performed on the design and application of the LFR, such as SSTAR [2] and SUPERSTAR [3] launched by USA, SVBR-100 [4], and BREST [5] in Russia, MYRRHA [6], and ALFRED [7] designed by the EU, etc. Meanwhile, an engineering project has been launched to develop ADS in China, which consists of the neutron source, the spallation target and the subcritical LFR ( < 1).…”

Section: Introductionmentioning

confidence: 99%

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Mao

Song

Liu

et al. 2018

Science and Technology of Nuclear Installations

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This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR). The motivation of this research is to improve the inherent safety of the LFR based on the China Accelerator Driven System (ADS) engineering project. Usually the plant is damaged due to the failure of the main pumps and the main heat exchangers under the Station Blackout (SBO). To prevent this accident, we proposed the DHRS based on the diathermic oil cooling for the LFR. The behavior of the DHRS and the plant was simulated using the CFD code STAR CCM+ using LFR with DHRS. The purpose of this analysis is to evaluate the heat exchange capacity of the DHRS and is to provide the reference for structural improvement and experimental design. The results show that the stable natural circulations are established in both the main vessel and the DHRS. During the decay process, the heat exchange power is above the core decay heat power. In addition, in-core decay heat and heat storage inside the main vessel are efficiently removed. All the thermal-hydraulics parameters are within a safe range. Moreover, the highest temperature occurs at the upper surface of the core. A swirl occurs at the corner of the lateral core surface and some improvements should be considered. And the natural circulation driving force can be further increased by reducing the loop resistance or increasing the natural circulation height based on the present design scenario to enhance the heat exchange effect.

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“…In the course of designing and operating the LBC cooled RFs at NSs a package of principal scientific and engineering problems on mastering of LBC technologies was solved [6], namely: assurance of corrosion resistance of structural materials; control of LBC quality and control of mass-transfer processes in the reactor circuit; assurance of personnel's radiation safety while carrying out works with the equipment contaminated with polonium-210 radionuclide; multiple LBC "freezing-unfreezing" in the RF.…”

Section: Introductionmentioning

confidence: 99%

Safety of Future NPPs Must Not Be in Conflict with Economics

Petrochenko¹,

Toshinsky²,

Komlev³

2016

WJNST

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The conflict between safety and economics requirements is peculiar to the present nuclear power (NP). The main point of the conflict is that for traditional type reactors the increase of requirements to safety of nuclear power plants (NPP) worsens their economical characteristics. This is caused by large potential energy accumulated in reactor coolant. In the presented paper the opportunity and expediency of changeover to reactors with heavy liquid-metal coolants (HLMC) in future NP is grounded. First of all, this refers to lead-bismuth coolant (LBC) mastered in the process of operating nuclear submarines (NS) reactors. The reactor facilities (RFs) of that type cannot cause destruction of defense barriers and make possible deterministic elimination of severe accidents with catastrophic radioactivity release. So it will make possible to eliminate the highlighted conflict and reasons for existence of population's radiophobia. Lead-bismuth fast reactor SVBR-100 with electric power of 100 MWe is the reactor facility of that type. The effect of accumulated in coolant potential energy on safety and economics is considered. Main specific features of SVBR-100 technology providing a high level of inherent self-protection and passive safety are presented.

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Innovative nuclear technology based on modular multi-purpose lead–bismuth cooled fast reactors

Cited by 38 publications

References 3 publications

Core design of long‐cycle small modular lead‐cooled fast reactor

Core design of long‐cycle small modular lead‐cooled fast reactor

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

Safety of Future NPPs Must Not Be in Conflict with Economics

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