A comparative physics study for an innovative sodium-cooled fast reactor (iSFR)

Hartanto, Donny; Kim, Chihyung; Kim, Yong Hee

doi:10.1002/er.3612

Cited by 12 publications

(9 citation statements)

References 10 publications

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“…Basic terminology definition (alphabetical order): Cognitive-The memory of a single particle to its bestobtained solution up until the current iteration, c 1 in Equation 3.…”

Section: Discussionmentioning

confidence: 99%

“…Inertia-The impact of the previous motion direction of the particle on the subsequent iteration, ω in Equation 3. Particle-An individual in the optimization process.…”

Section: Discussionmentioning

confidence: 99%

“…Social-The memory of the entire swarm to its bestobtained solution up until the current iteration, c 2 in Equation 3.…”

Section: Discussionmentioning

confidence: 99%

“…3. Loss of coolantleads to neutron spectrum hardening and increase in the neutron leakage (usually a negative reactivity effect).…”

Section: Introductionmentioning

confidence: 99%

“…Structural material redistributioncould lead to variation in streaming effects and change the direct and adjoint fluxes (could be a positive effect by increasing scattering to high importance regions). 3. Accumulation of molten fuel in certain regions of the corecould potentially alter the high importance region location and lead to reactivity excursion.…”

Section: Introductionmentioning

confidence: 99%

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Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR fast/thermal coupled ZPRs. Part I-Assembly level

2018

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Summary The comprehension of severe criticality accident is a key issue in Gen‐IV neutronics and safety. Within the future zero‐power experimental physics reactor (ZEPHYR), to be built in Cadarache in the next decade, innovative approaches to reproduce high temperature partially degraded Gen‐IV cores into a critical facility is being investigated. This work presents the first attempt to represent a fuel assembly of sodium‐cooled fast reactor severe criticality accident based on surrogate models. One identified way to construct such representative configuration is to use MASURCA plates stockpile (MOX, UOx, Na, U, and Pu metal) in a fast/thermal coupled core to model a stratified molten assembly. The present study is the first step in a more global approach to full core analysis. The approach is based on a nature‐inspired metaheuristic algorithm, the particle swarm optimization algorithm, to find relevant ZEPHYR configuration at 20°C that exhibits characteristics of (2000‐3000°C) molten MOX assembly in a stratified metal arrangement in a reference sodium‐cooled fast reactor core. Thus, the underlying research question of this study is whether it is possible to represent temperature‐related reactivity effects occurring at fuel meltdown temperatures in a power reactor as density‐related reactivity effects at the operation temperature of a zero‐power reactor, and if so, how should it be done? The calculations are based on a Serpent‐2 Monte Carlo sensitivity and representativity analysis using the Cadarache's cross sections covariance data (COMAC). The single fuel assembly studies show that it is possible to represent the multiplication factor with a representativity factor greater than 0.98. As for reactivity variations, it is possible to achieve a satisfactory representativity factor of above 0.85 in all the presented cases. The representativity process demonstrates that temperature effects could be translated into density effects with good confidence. A complementary analysis on modified nuclear data covariance matrix demonstrates the importance of selecting consistent and robust uncertainties in the particle swarm optimization algorithm. This work provides insights on the behavior of the representativity scheme in different core states and shades some light on the problem in hand.

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“…Basic terminology definition (alphabetical order): Cognitive-The memory of a single particle to its bestobtained solution up until the current iteration, c 1 in Equation 3.…”

Section: Discussionmentioning

confidence: 99%

“…Inertia-The impact of the previous motion direction of the particle on the subsequent iteration, ω in Equation 3. Particle-An individual in the optimization process.…”

Section: Discussionmentioning

confidence: 99%

“…Social-The memory of the entire swarm to its bestobtained solution up until the current iteration, c 2 in Equation 3.…”

Section: Discussionmentioning

confidence: 99%

“…3. Loss of coolantleads to neutron spectrum hardening and increase in the neutron leakage (usually a negative reactivity effect).…”

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR fast/thermal coupled ZPRs. Part I-Assembly level

2018

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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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SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept

Zhou

Cao

et al. 2019

Annals of Nuclear Energy

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A comparative physics study for an innovative sodium-cooled fast reactor (iSFR)

Cited by 12 publications

References 10 publications

Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR fast/thermal coupled ZPRs. Part I-Assembly level

Modeling representative Gen-IV molten fuel reactivity effects in the ZEPHYR fast/thermal coupled ZPRs. Part I-Assembly level

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

SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept

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