核工程计算物理实验室Nuclear Engineering Computational Physics

23/4/19

The Neutronics Studies of Fusion Fission Hybrid Power Reactor

Youqi Zheng Ph. D

Nuclear Engineering Computational Physics Lab. Xi’an Jiaotong University

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Contents

Background

Fusion Source and Blanket Design

Neutronics Design and Sensitivity Analysis

Conclusions

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NOW 2018 2030

2050

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A long way for the pure fusion energy, butA short way for the application of fusion source

Background(1/3)

It is well recognized thatthe fusion fission hybrid power reactor is an important early use of fusion source

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After 2000

1991-2000

1986-1990

1980-1985

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Background(2/3)

R&D of hybrid reactor in China

Re-evaluation for Producing Energy, Breeding and Transmutation

R&D of Hybrid Power Reactor (National Magnetic Confinement Fusion Science Program, 2010)

Background(3/3)

The target—A hybrid power reactor• 1000MWe Power Output for 5 years• Tritium self-sustaining considering 5% loss• Applying the existing fission technology as much as possible• Sufficient energy multiplication of blanket for different fusion power

The first step• Determining the outline of reactor• Determining the candidate fuel • Evaluating the feasibility

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Contents

Background

Fusion Source and Blanket Design

Neutronics Design and Sensitivity Analysis

Conclusions

The referred fusion reactor• Citing from the works on FDS-I by ASIPP (under the cooperation in

National Magnetic Confinement Fusion Science Program )

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Fusion Source and Blanket Design (1/4)

Parameters Reference ValueMajor radius/m 4Minor radius/m 1Aspect ratio 4Plasma elongation 1.78Triangularity 0.4

Fusion Source and Blanket Design (2/4)

Preliminary evaluation of water cooling blanket

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200mm is required for the FW based on the press analysis (Referring: for a PWR vessel 43mm is required , but the practical one is >200mm)

For the fuel pins and pressurized water coolant with 15.5MPa

Fusion Source and Blanket Design (3/4)

The modular-type pressure tube blanket

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60cm

Tri tium Breeding Zone

Fuel Zone

35.5cm

24.5cm

135cm

120cm

Pressuri zed Tube

Hel ium Tube

LiO2

Graphi te & RAFM

Refl ector&

Shielding Layer

Fusion Source and Blanket Design (4/4)

The simplified evaluation model

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*467.2*784.4*200 76

S

TTM f

V

V s

dVdEdErs

dVdEdErTBR

4 0

0 Li76Li

),,(

),,()(

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Contents

Background

Fusion Source and Blanket Design

Neutronics Design and Sensitivity Analysis

Conclusions

Neutronics Design and Sensitivity Analysis (1/4)

Energy multiplication requirements of the fission blanket

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1000fuP M

For the 50MW fusion power Keff >0.9

For the 100~200MW fusion power Keff~0.8

For the 500MW fusion power Keff~0.6

Neutronics Design and Sensitivity Analysis (2/4)

Keff varying in the lifetime of different fuels

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Reprocessed fuel for high energy multiplicationSpent fuel for middle energy multiplicationNatural uranium fuel for low energy multiplication

High energy multiplication blanket

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Neutronics Design and Sensitivity Analysis (3/4)

14.3%w/o PuModerator-fuel ratio 1.0Gd2O3 0.85%w/o

4.5%w/o PuMore plutonium contentFlattened burn-up process

Burnable poison is another choice

Low energy multiplication blanket• Higher fusion power and released blanket

performance

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Neutronics Design and Sensitivity Analysis (4/4)

Moderator-fuel ratio 0.5Modified blanket

Moderator-fuel ratio 1.0The same blanket

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Contents

Background

Fusion Source and Blanket Design

Neutronics Design and Sensitivity Analysis

Conclusions

The reprocessed fuel containing existing plutonium from PWRs makes the hybrid power reactor feasible in the coming future

Progress of fusion technology may encourage the more easier fuels like the natural uranium fuel and directly burning the spent fuel from PWRs

Advanced work can and should be boosted based on the analysis

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Conclusions (1/2)

Discussions• High energy multiplication

Fuel support of the reactors– ~40tons plutonium will be loaded every 5 years

Control of the reactors– 90 times multiplication down to 60 times

• Low energy multiplication For the natural uranium fuel, the required small moderator-

fuel ratio is very difficult to achieve for the pressure tubes For the spent fuel, the fuel processing before loading

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Conclusions (2/2)

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