Sodium cooled small fast long-life reactor “4S”

Ueda, Naonori; Kinoshita, Izumi; Minato, Akihiko; Kasai, Shigeo; Yokoyama, Tsugio; Maruyama, Satoshi

doi:10.1016/j.pnucene.2005.05.022

Cited by 43 publications

(13 citation statements)

References 4 publications

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“…Unlike thermal reactors, the excess reactivity cannot be effectively managed by the burnable absorbers in fast reactors due to the hard spectrum and low capture cross sections. In the current work, to deal with the high excess reactivity, a concept of removable neutron absorber similar to the one in the Toshiba 4S [21] is introduced, which is called "replaceable fixed absorber (RFA)". In Figure 8, the schematic concept of the RFA is depicted, i.e., a hexagonal absorber material is loaded into the central guide structure of the secondary shutdown system and the absorber section is designed to be replaceable, if necessary.…”

Section: Neutronics Analysis and Characterization Of The Micro Modulamentioning

confidence: 99%

A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor

Hartanto

Moon

et al. 2015

Energies

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A neutronics conceptual study of a supercritical CO 2 -cooled micro modular reactor (MMR) has been performed in this work. The suggested MMR is an extremely compact and truck-transportable nuclear reactor. The thermal power of the MMR is 36.2 MWth and it is designed to have a 20-year lifetime without refueling. A salient feature of the MMR is that all the components including the generator are integrated in a small reactor vessel. For a minimal volume and long lifetime of the MMR core, a fast neutron spectrum is utilized in this work. To enhance neutron economy and maximize the fuel volume fraction in the core, a high-density uranium mono-nitride U 15 N fuel is used in the fast-spectrum MMR. Unlike the conventional supercritical CO 2 -cooled fast reactors, a replaceable fixed absorber (RFA) is introduced in a unique way to minimize the excess reactivity and the power peaking factor of the core. For a compact core design, the drum-type control absorber is adopted as the primary reactivity control mechanism. In this study, the neutronics analyses and depletions have been performed by using the continuous energy Monte Carlo Serpent code with the evaluated nuclear data file ENDF/B-VII.1 Library. The MMR core is characterized in view of several important safety parameters such as control system worth, fuel temperature coefficient (FTC) and coolant void reactivity (CVR), etc. In addition, a preliminary thermal-hydraulic analysis has also been performed for the hottest channel of the Korea Advanced Institute of Science and Technology (KAIST) MMR.

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Section: Neutronics Analysis and Characterization Of The Micro Modulamentioning

confidence: 99%

A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor

Hartanto

Moon

et al. 2015

Energies

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“…The 2600 MW ultralong‐cycle fast reactor (UCFR‐1000) proposed by Tak et al can operate for 60 years without refueling and also adopts the B&B strategy . The 4S (super‐safe, small, and simple) reactor was conceptually developed by Toshiba Corporation and Central Research Institute of Electric Power Industry (CRIEPI) to achieve a core lifetime of 30 years with negative temperature and void reactivity feedbacks . TerraPower, LLC has developed the traveling wave reactor (TWR) that aims at 40‐year core life by allowing fuel shuffling every 495 effective full power days (EFPDs) .…”

Section: Introductionmentioning

confidence: 99%

“…6 The 4S (super-safe, small, and simple) reactor was conceptually developed by Toshiba Corporation and Central Research Institute of Electric Power Industry (CRIEPI) to achieve a core lifetime of 30 years with negative temperature and void reactivity feedbacks. 7 TerraPower, LLC has developed the traveling wave reactor (TWR) that aims at 40-year core life by allowing fuel shuffling every 495 effective full power days (EFPDs). 8 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.…”

Section: Introductionmentioning

confidence: 99%

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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“…Constant axial shape of neutron flux, nuclide densities and power shape during life of energy (CANDLE) was designed as an ultra-long-life fast reactor concept by stacking the different fuel material along the axial direction [7]. A conceptual design of a super-safe, small, and simple (4S) reactor was proposed by Toshiba Corp. and CRIEPI to meet design criteria such as negative temperature feedback reactivity coefficients including sodium void worth and a core lifetime longer than 10 years [9]. A conceptual design of a super-safe, small, and simple (4S) reactor was proposed by Toshiba Corp. and CRIEPI to meet design criteria such as negative temperature feedback reactivity coefficients including sodium void worth and a core lifetime longer than 10 years [9].…”

Section: Introductionmentioning

confidence: 99%

“…The SFR is one of the Generation IV reactor concepts [1][2][3][4][5]. Many SFR concepts have been proposed to achieve a long-life core by adopting a fast spectrum [6][7][8][9][10]. Tak et al proposed the 2600 MW ultra-long cycle fast reactor (UCFR-1000) for a 60-year operation without refueling and adopting the breed-andburn (B&B) strategy [6].…”

Section: Introductionmentioning

confidence: 99%

Design study of long-life small modular sodium-cooled fast reactor

Park

Tak

Kim

et al. 2016

Int. J. Energy Res.

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Summary This paper presents a new design for a small modular sodium‐cooled fast reactor core with an optimized lifetime and reactivity swing through the analysis of various breed‐and‐burn strategies and its neutronic analyses in terms of active core movements, isotopic mass balance, kinetic parameters, and inherent safety. The new core design aims at a power level of 260 MW with a long lifetime of 30 years without refueling and a reactivity swing smaller than 1000 pcm. Starting from five initial candidate cores with various breed‐and‐burn strategies, an optimum core was selected from a combination of the two candidates that shows a proper breeding behavior with the optimized uranium enrichment in the low‐enriched uranium region and the optimized size of the blanket region. The depletion analysis of the new core provides various reactor design parameters such as the core multiplication factor, breeding ratio, heavy metal mass change, power distribution, and summary of neutron balance. In addition, the perturbation analysis provides the reactor kinetic parameters and reactivity feedback coefficients for the inherent safety analysis of the core. The integral reactivity parameters of the quasi‐static reactivity balance analysis demonstrate that the new core is inherently safe in cases of unprotected loss of flow, unprotected loss of heat sink, and unprotected transient over power. Copyright © 2016 John Wiley & Sons, Ltd.

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Sodium cooled small fast long-life reactor “4S”

Cited by 43 publications

References 4 publications

A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor

A Conceptual Study of a Supercritical CO2-Cooled Micro Modular Reactor

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

Design study of long-life small modular sodium-cooled fast reactor

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