Fuel, Core Design and Subchannel Analysis of a Superfast Reactor

CAO, Liangzhi; Oka, Yoshiaki; Ishiwatari, Yuki; Shang, Zhi

doi:10.1080/18811248.2008.9711423

Cited by 40 publications

(16 citation statements)

References 11 publications

(15 reference statements)

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“…[6][7][8] Since the enthalpy rise in the core is relatively small and the heat capacity of the core outlet coolant is relatively large in the SCFR, the change in the main steam temperature was within 5 C against various perturbations anticipated in normal operation. 6) Since the moderator in the large water rods mitigates the change in the coolant temperature in the Super LWR core, the change in the main steam temperature is still small (within 8 C) although the enthalpy rise is larger and, hence, the heat capacity of the core outlet coolant is smaller than those of the SCFR.…”

Section: Introductionmentioning

confidence: 99%

Improvements of Feedwater Controller for the Super Fast Reactor

Ishiwatari

Peng

Ikejiri

et al. 2010

J. Nucl. Sci. Technol.

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The main steam temperature of SCWRs sensitively changes with the power-to-flow ratio. In this article, the feedwater controller of the Super FR (fast-spectrum SCWR) is modified from that of the Super LWR (thermal-spectrum SCWR) for suppressing the variation of the main steam temperature. A plant system analysis code SPRAT-F is used. One of three feedback terms is added to the original feedwater controller that took only the deviation of the main steam temperature into consideration. In the feedwater controller (A), the deviation of the power-to-flow ratio is considered. In the feedwater controller (B), the deviation of the power is considered. In the feedwater controller (C), the time derivative of the power is considered. All the modified feedwater controllers keep the variation of the main steam temperature within 2 C, which has been achieved in recent supercritical coal-fired power plants, against typical load change. In order to further confirm the performance of the modified feedwater controllers, five typical perturbations are analyzed. All the feedwater controllers including the original one stably control the Super FR against all the perturbations without a significant oscillation or offset. Among them, the feedwater controller (B) gives a smaller or at least not larger variation of the main steam temperature compared with the original one at all the perturbations, while the feedwater controllers (A) and (C) give a larger variation in particular cases. From these results, it is concluded that the original feedwater controller is successfully improved as the feedwater controller (B).

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Section: Introductionmentioning

confidence: 99%

Improvements of Feedwater Controller for the Super Fast Reactor

Ishiwatari

Peng

Ikejiri

et al. 2010

J. Nucl. Sci. Technol.

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“…The CSR1000 core uses rod-type fuel, and the 310S stainless steel is chosen as the fuel cladding and core structure material. Currently, it is widely acknowledged that the core design criteria [7,8] are as follows: ‹ Under normal condition, maximum cladding surface temperature (MCST) 650 C, maximum linear heat generation rate (MLHGR) 39 kW/m; › When the control rod with the maximum rod worth stuck, the k-eff of the core is no bigger than 0.99. Based on these criteria and the FA Transactions of the ASME mentioned earlier, this paper has studied the optimization core design for a longer refueling cycle.…”

Section: Optimization Of Core Designmentioning

confidence: 99%

Study on Optimization Design for CSR1000 Core

Wang

Yang

et al. 2017

Journal of Nuclear Engineering and Radiation Science

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An optimization design of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MW e (CSR1000) conceptual core is proposed. Steady-state performance of the proposed core is then studied with the SCWR core steady-state analysis code system SNTA. These key parameters such as burnup performance, reactivity control capability, power distribution, maximum fuel cladding temperature, and maximum linear power density are analyzed. The relative coolant flow rate of the second flow path, which is suited with assembly power, is also presented. The study shows that the refueling cycle of CSR1000 core can be extended effectively under the optimization design.

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“…However, the coolant void reactivity coefficient of the core is positive. A tight lattice of the MOX fuel assembly in hexagonal geometry has been proposed with some blanket loaded in SCFR core design [15] [19]. The blanket assembly is to convert fertile nuclide and comprised of depleted UO 2 fuel and ZrH 1.7 layer as solid moderator.…”

Section: Introductionmentioning

confidence: 99%

Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

Liu¹,

Xie²,

He³

2015

WJNST

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The purpose of the study is to analyze the breeding ratio of a supercritical water cooled fast reactor (SCFR) and to increase the breeding core of SCFR. The sensitivities of assembly parameters, core arrangements and fuel nuclide components to the breeding ratio are analyzed. In assembly parameters, the seed fuel rod diameter has higher sensitivities to the conversion ratio (CR) than the coolant tube diameter in blanket. Increasing heavy metal fraction is good to CR improvement. The CR of SCFR also increases with a reasonable core arrangement and Pu isotope mass fraction reduction in fuel, which can achieve more negative coolant void reactivity coefficient at the same time. The breeding ratio of SCFR is 1.03128 with a new core arrangement. And the coolant void reactivity coefficient is negative, which achieves a fuel breeding in initial fuel cycle.

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Fuel, Core Design and Subchannel Analysis of a Superfast Reactor

Cited by 40 publications

References 11 publications

Improvements of Feedwater Controller for the Super Fast Reactor

Improvements of Feedwater Controller for the Super Fast Reactor

Study on Optimization Design for CSR1000 Core

Primary Breeding Ratio Analysis of an Improved Supercritical Water Cooled Fast Reactor

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