The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input

Su’ud, Zaki; Sekimoto, Hiroshi

doi:10.1016/j.anucene.2012.09.014

Cited by 45 publications

(31 citation statements)

References 15 publications

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“…MCANDLE (Modified CANDLE) concept is a modification of the CANDLE method by introducing discreet regions and modification of shuffling scheme. MCANDLE burn-up concept was first introduced in the following references [3,4]. In this research we adopted MCANDLE type B in which first and second regions are located near 10 th region [5].…”

Section: Power Flattening On Modified Candle Small Long Life Gas-coolmentioning

confidence: 99%

Power flattening on modified CANDLE small long life gas-cooled fast reactor

Monado¹,

Su’ud²,

Waris³

et al. 2014

AIP Conference Proceedings

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A gas-cooled reactor surface power system AIP Conf.A modular gas-cooled cermet reactor system for planetary base power AIP Conf.Abstract. Gas-cooled Fast Reactor (GFR) is one of the candidates of next generation Nuclear Power Plants (NPPs) that expected to be operated commercially after 2030. In this research conceptual design study of long life 350 MWt GFR with natural uranium metallic fuel as fuel cycle input has been performed. Modified CANDLE burn-up strategy with first and second regions located near the last region (type B) has been applied. This reactor can be operated for 10 years without refuelling and fuel shuffling. Power peaking reduction is conducted by arranging the core radial direction into three regions with respectively uses fuel volume fraction 62.5%, 64% and 67.5%. The average power density in the modified core is about 82 Watt/cc and the power peaking factor decreased from 4.03 to 3.43.

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Section: Power Flattening On Modified Candle Small Long Life Gas-coolmentioning

confidence: 99%

Power flattening on modified CANDLE small long life gas-cooled fast reactor

Monado¹,

Su’ud²,

Waris³

et al. 2014

AIP Conference Proceedings

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“…Recalling the volumetric reaction rate (reaction rate per unit time and volume) expressed by VIN (ON in case of decay) and making a balanced relation between the production and destruction rates of a target nuclide, the burn up equation can be given by the following equations, where nuclides are identified by a two-digit superscript indicating the last digit in the atomic number and the last digit in the mass number [3]. Eq.…”

Section: Design Concept and Calculation Methodsmentioning

confidence: 99%

“…Gas Cooled Fast Reactor (GFR), Lead Cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium Cooled Fast Reactor (SFR), Supercritical Water Cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR) [2]. Beforehand, neutronics analysis of GFR with SRAC Code and modified CANDLE burn up scheme with uranium natural has been analyzed [3,4,5,6].…”

Section: Introductionmentioning

confidence: 99%

Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

et al. 2016

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“…The calculation use hexagonal fuel pin calculation and R‐Z geometry core calculation with SRAC2006 code system and JENDL4.0 data libraries. Beforehand, neutronic analysis of GFR with SRAC2006 code system with modified CANDLE burnup scheme has been analyzed . And then the neutronic calculation of thorium fuel has been calculated before .…”

Section: Introductionmentioning

confidence: 99%

Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling

et al. 2017

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SummaryComparison of uranium plutonium nitride and thorium nitride fuel for 500 MWth gas-cooled fast reactor has been done. Gas-cooled fast reactor is one type of generation IV reactor that can be operated in high temperature. Due to the high temperature, it can be used in hydrogen production. In this study, we compare the neutronic analysis of two fuel types, ie, uranium nitride fuel (U,Pu)N and thorium nitride fuel (Th,U233)N. The neutronic calculation uses SRAC2006 code system, and the data libraries use JENDL4.0.First, the fuel pin calculation (PIJ calculation) has been done to take the macro data that are used in CITATION calculation. Both uranium and thorium fuel use heterogeneous configuration with 3 variation fuel in the core. F1 is located in the central core, F2 middle core, and F3 outer core.The variation of fuel fraction is 40% until 65%, cladding 10%, and coolant 25% until 40%. For (U,Pu)N fuel, the diameter of the active core is 220 cm, and the height of the active core is 110 cm. And for (Th,U233)N, the diameter of the active core is 250 cm and the height of the active core is 150 cm. The reflector radial-axial width is 50 cm. For uranium plutonium nitride fuel, the type of the fuel in one core is varied; ie, F1 is 8%, F2 is 10%, and F3 is 12%. For thorium nitride fuel, the type of the fuel in one core also varied; ie, F1 is 7.8%, F2 is 8%, and F3 is 8.8%. The optimum value of thorium nitride is when fuel fraction of region F1 = 60%, F2 = 57.5%, F3 = 60%, the burn up time up to 20 years without refueling, max k-eff value is 1.0109, and max excess reactivity value is 1.08%. Neutronic analysis shows that both uranium and thorium fuel have excess reactivity value less than 2% but thorium fuel has excess reactivity less than uranium nitride fuel.Uranium fuel has better breeding capability than thorium fuel. Therefore, it is better to use uranium fuel for fast reactor like GFR, which has high breeding capability.

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The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input

Cited by 45 publications

References 15 publications

Power flattening on modified CANDLE small long life gas-cooled fast reactor

Power flattening on modified CANDLE small long life gas-cooled fast reactor

Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling

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