Design of Ultralong-Cycle Fast Reactor Employing Breed-and-Burn Strategy

Tak, Taewoo; Lee, Deokjung; Kim, T. K.

doi:10.13182/nt13-a19430

Cited by 16 publications

(9 citation statements)

References 10 publications

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“…Realistic TWR designs using DU as fertile fuel require a minimum peak fast neutron fluence of at least 2.5 Â 10 24 n/cm 2 (E > 0.1 MeV) (Tak et al, 2012), which corresponds to around $1200 DPA -six times above the currently accepted limit. In other estimates, the peak TWR discharge fluence is as high as 4.2 Â 10 24 n/cm 2 (E > 0.1 MeV) (Kim and Taiwo, 2010).…”

Section: Introductionmentioning

confidence: 99%

Design and performance of 2D and 3D-shuffled breed-and-burn cores

Qvist

Hou

Greenspan

2015

Annals of Nuclear Energy

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Section: Introductionmentioning

confidence: 99%

Design and performance of 2D and 3D-shuffled breed-and-burn cores

Qvist

Hou

Greenspan

2015

Annals of Nuclear Energy

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“…As a result of previous sensitivity analyses, two types of core were selected, with different numbers of driver and reflector assemblies. The core configuration was selected as the best performance for the breed and burn concept and for achieving an active core diameter less than the maximum value of 1.7 m. The radial and the axial fuel arrangements of the two core candidates (TYPE I and TYPE II, referred with modification from Park et al 260 MW SMSFR and UCFR‐1000 proposed by Tak et al) are shown in Figure , and Table summarizes the core parameters of the two core candidates proposed for optimization study. The two candidates are analyzed in the next section in terms of k eff and core breeding ratio trends during depletion for different values of enrichment in the LEU region.…”

Section: The Design Strategy Of the Conceptual Corementioning

confidence: 99%

“…Park et al has proposed the 260 MW long‐life fast reactor for a 28.5‐year operation without refueling and a small burnup reactivity swing by utilizing the breed and burn (B&B) concept . 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 .…”

Section: Introductionmentioning

confidence: 99%

“…5 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. 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).…”

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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“…The SFR is one of the Generation IV reactor concepts [1][2][3][4][5]. 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]. 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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Design of Ultralong-Cycle Fast Reactor Employing Breed-and-Burn Strategy

Cited by 16 publications

References 10 publications

Design and performance of 2D and 3D-shuffled breed-and-burn cores

Design and performance of 2D and 3D-shuffled breed-and-burn cores

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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