Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code

Cui, Shijie; Zhang, Dalin; Tian, Wenxi; Su, G.H.; Qiu, Suizheng

doi:10.1016/j.fusengdes.2018.01.014

Cited by 8 publications

(13 citation statements)

References 27 publications

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“…In our previous work, 14,29 NTCOC, a Nuclear‐Thermal Coupling Code has been developed for optimizing the radial structure layout of HCCB blanket. It has been applied on optimizing the radial structure layout of the typical outboard CFETR phase I HCCB blanket with P f = 200 MW, 14,15 which verifies the feasibility of this code and the integrated optimization method. However, as the final core design parameters of CFETR phase II have been just determined, and both the dimensions and the NWL of CFETR phase II HCCB blanket are much bigger than phase I, the radial structure layout optimization work for phase II blanket should be initialized.…”

Section: Coupling Optimization Design Of No 9 Blanket Module With Thmentioning

confidence: 99%

“…This change is not obvious in CFETR phase I blanket, the neutron flux density in which is relatively low. Therefore, the average temperatures of the BUs in CFETR Phase I blanket are still relatively high, which are beneficial for the tritium release 14,15 . However, the fusion power of Phase II is quintuple to phase I, which makes the neutron flux density in the blanket also much higher than the previous phase I blanket.…”

Section: Coupling Optimization Design Of No 9 Blanket Module With Thmentioning

confidence: 99%

“…Until now, there are many research institutes which have performed conceptual design, comprehensive analyses, and optimizations work for phase I HCCB blanket in detail 8,9,13‐19 . However, the operational stage of CFETR has transformed from Phase I to Phase II, and the latest core design parameters have been just determined (major radius equals to 7.2 m, minor radius equals to 2.2 m) 20 .…”

Section: Introductionmentioning

confidence: 99%

“…Therefore, 23 only focuses on the optimization of CP He thickness for satisfying the pressure drop limit, while the temperature distributions of BUs, which have great influence on the tritium breeding and releasing performance, are not taken into consideration temporarily. In this work, based on the original integrated optimization method 14,15 and the optimum CP He thickness, 23 the radial structure layout optimization of the outboard equatorial phase II HCCB blanket module is conducted by NTCOC firstly 14 . However, the calculation results show that the original optimization method provides inadequately optimized tritium breeding performance and insufficient tritium releasing ability under the condition of high fusion power.…”

Section: Introductionmentioning

confidence: 99%

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A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket

et al. 2020

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China Fusion Engineering Test Reactor (CFETR) is a brand new Tokamak reactor which is currently being designed to fill the intervals between ITER and future DEMO fusion reactor. It has two operation phases: phase I with P f = 200 MW is to demonstrate steady-state operation; phase II with P f = 1000 MW to validate DEMO technology. Helium-cooled ceramic breeder (HCCB) blanket is one of the candidate blanket concepts for CFETR. Until now, there are many research institutes which have performed conceptual designs and comprehensive analyses works for phase I HCCB blanket in detail.However, lately, the operational stage of CFETR has transformed from phase I to phase II, and the latest core design parameters have been just determined (major radius equals to 7.2 m, minor radius equals to 2.2 m). Therefore, the design and analyses work for HCCB blanket should also be initialized. In this work, based on the original integrated optimization method, the radial structure layout optimization of the outboard equatorial phase II HCCB blanket module is conducted by NTCOC. However, the calculation results show that the original optimization method provides inadequately optimized tritium breeding performance and insufficient tritium releasing ability under the condition of high fusion power. To solve these problems, a dynamic feedback is incorporated into the original optimization method for the first time, and then the calculation results show that the problem has been solved well after revision. This work can supply worthy guidance and reference for the conceptual design and comprehensive analyses of CFETR phase II HCCB blanket. K E Y W O R D S CFETR phase II, coupling optimization, dynamic feedback, HCCB blanket, high fusion power 1 | INTRODUCTION China Fusion Engineering Test Reactor (CFETR) is a brand new Tokamak reactor which is currently being designed to play a transitional role between ITER and DEMO. [1][2][3][4][5] According to the Chinese magnetic fusion energy development strategy, 4,5 the operation stage of CFETR can be divided into two parts: phase I with P f = 200 MW is to demonstrate steady-state operation with duty factor ≥0.3 to 0.5, and tritium self-sustaining

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Section: Coupling Optimization Design Of No 9 Blanket Module With Thmentioning

confidence: 99%

Section: Coupling Optimization Design Of No 9 Blanket Module With Thmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket

et al. 2020

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“…The code system was applied in the water-cooled lithium lead blanket (WCLL) and the helium-cooled pebble bed blanket (HCPB) for the European DEMO project. Jiang [17] and Cui [18,19] developed multi-physics integrated optimization and design platforms based on MCNP and ANSYS for the water-cooled ceramic breeder blanket (WCCB) and the helium-cooled solid breeder blanket (HCSB) of CFETR, respectively. In their work, they focus the most attention on the individual neutronics calculation or thermal-hydraulics calculation, thus the one-way coupling method was adopted.…”

Section: Introductionmentioning

confidence: 99%

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Dai

Cao

et al. 2020

Energies

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The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the fusion reactor. Neutronics/thermal-hydraulics (N/TH) coupling effect is significant in the numerical analysis of the fission reactor. However, in the numerical analysis of the fusion reactor, the existing coupling code system mostly adopts the one-way coupling method. The ignorance of the two-way N/TH coupling effect would lead to inaccurate results. In this paper, the MCNP/FLUENT code system is developed based on the 3D-1D-2D hybrid coupling method. The one-way and two-way N/TH coupling calculations for two typical blanket concepts, the helium-cooled solid breeder (HCSB) blanket and the water-cooled ceramic breeder (WCCB) blanket, are carried out to study the two-way N/TH coupling effect in CFETR. The numerical results show that, compared with the results from the one-way N/TH coupling calculation, the tritium breeding ration (TBR) calculated with the two-way N/TH calculation decreases by −0.11% and increases by 4.45% for the HCSB and WCCB blankets, respectively. The maximum temperature increases by 1 °C and 29 °C for the HCSB and WCCB blankets, respectively.

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Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

et al. 2020

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Summary China Fusion Engineering Test Reactor (CFETR) has two operation phases: Phase I with Pf = 200 MW is to demonstrate the steady‐state operation; Phase II with Pf = 1 GW is to validate the DEMO technology. Helium Cooled Ceramic Breeder (HCCB) blanket is one blanket candidate for CFETR, and several research institutes have conducted extensive conceptual designs and comprehensive analysis works for Phase I HCCB blanket. However, because the operation phase of CFETR has transformed from Phase I to Phase II and the latest physical design parameters have been just determined, the design and analysis works for HCCB blanket should be initialized. In this work, first, the basic structure design of CFETR Phase II HCCB blanket is performed and a design scheme is proposed according to the design principles and requirements of blanket. Besides, the material selection of each blanket component has been determined. Second, based on the global neutronics model of CFETR Phase II, the neutron wall loadings (NWL) on different blanket modules are calculated. Afterwards, the radial structure layout optimizations of all poloidal blanket modules arranged in a 22.5° toroidal sector are conducted by NTCOC. As for Phase II blanket, which operates under the high fusion power condition, it should be noted that a dynamic feedback is incorporated into the original one‐way optimization method for solving the problems of inadequately optimized tritium breeding performance and insufficient tritium releasing ability. Finally, the radial structure layout parameters of all blanket modules in CFETR Phase II neutronics model are set as the obtained final optimal schemes. The calculation results show that the global TBR of CFETR Phase II is 1.182, which can well meet the tritium self‐sustaining requirement. This work can provide worthy guidance and reference for further conceptual design, comprehensive analyses and optimizations of the CFETR Phase II HCCB blanket.

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Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code

Cited by 8 publications

References 27 publications

A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket

A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

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