Wenlong Zhan CAS

RRW2016 JAEA

Feb. 17, 2016

2

I. Introduction Motivation Roadmap of ADS/ADANES New Site, New Research Center

II. Progress of ADS/ADANES Configuration of C-ADS Accelerator System Spallation Target Subcritical Core Fuel Recycle Material R&D …

3

MOX+LWR

?

Res

ourc

e U

tiliz

atio

n**（

%）

Radiotoxicity Reduction （%）

Fuel ~ 100yr, Waste Live 10000 yr

Fuel ~ 10000yr，Waste < 5%，radioactive live <500yr

LWR, Once Through

**Fuel Supply 1000GWe

235U0.72% 238U99.3%

235U0.72%

239Pu99.3%

238U99.3%

n

MOX+FR

FRs

?

Ideal System : ADANES

ADS Transmutation

Higher Utilization Breeding Minimization Radiotoxicity Transmutation

Fast Neutron

Scale Demo./ Commercial

4

Main difficulties of P&T: Extract high purity U，Pu & MA ≠ Residuals

remain MA<1% (long lifetime in waste)

more Toxicity @ Complexes few generations later

High purity Pu, MA fuels is ：

Burning Unstable & High risk of proliferation !!

Low feasibility(final solution?), low cost effective

New Approach: (optimizing SNF resources & radiotoxicity)

Remove part of FPs (~50%RE’s) from SNF, Convert

Residuals as recycle fuel (short lifetime in waste)

Transmuting, Breeding & Energy Amplify by fast

neutron burning recycle fuel (higher cost effective)

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Accelerator Driven System was proposed for: Nuclear waste transmutation (ADS) Isotopes production (ex. Breed, ISOL, APT) ADANES Burner Energy Amplifier (ADTR)…

ADS consists of high power proton accelerator, spallation target & subcritical core mainly

ADS and FR in Advanced Nuclear Fuel Cycles — A Comparative Study, NEA/OECD, 2002

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ADANES Burner: Transmutation**(3~12) + Breeding > 1.1 + Energy Amplifier ~ LWR in Situ

ADANES Fuel Recycles: Remove >50% FP from SNF by HT Dry (Ext. AIROX), further Remove >90% Ln’s by REs extract, MA<1% than Origin

MA TRU NU DU Th LEU… >96%UNF

SNF

Waste:<4%SNF； FP’s: Volatile FP’s, <1%gas, <1% Ln’s; MA<1% than SNF

**Burning： SNF > 3 MA 12

Convert SNF into Recycle Fuel, Waste <4% SNF @ MA<1%, τ<500Y, Sustain NE > 10000yr

Energy

~50%FP

7

Remove >50% FP’s, Waste<4% SNF, with MA<1% than SNF’s, τ <500y

Volatile FP’s+ <1%Gas FP’s

HT-Dry Process Remove FP’s, eff.>50%

Oxide Convert to Carbide Grain Burner Fuel

SiCf/SiC or SIMP Cladding

ADANES Burner

<1%Lns FP’s, MA<1% than that in SNF and Dry Storage

(1-x

%) S

NF，

<50%

FP

Pulverize SNF, Convert to Oxide

SNF from LWR

>(x-2)%SNP

High purity REs Extract Process to remove Lns FPs, eff.>2/3 (no water solution)

x%SNF

Ene

rgy

>96%SNF

X ?

<50%FP

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SC-LINAC

Safety, Flexibility Close fuel Cycle, “Raw Fuel”, Higher cost effective Higher Resource Utilization, Minimization Radiotoxicity：

>3 PWR SNF (33GWd/T) / ADANES (>500MWt) Accelerator Driven Subcritical Time: 10% ~ < 15% Depend power density, temperature, cladding & core material performances, number of reactors and …

。。。

。。。

R2

R1

R4

R3 R2n-1

R2n

SC-LINAC

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Inject I

Inject II

2014 ~2.5 MeV &10mA

2016 ~25 MeV &~10mA

2022 >250 MeV &~10mA

<2030 ~1.0 GeV &<15mA

~203x ~1.0 GeV &>15mA

>10 MWt >500 MWt ≥1 GWt 10 MeV

￥1.78 B Phase I 2011--2016

>￥1.8 B Phase II 2016--2022

Key Tech. R&D : Acc., Target, Blanket… Prototype Initial Facility Demo. Facility

Phase III Phase IV

Indust. Facility

<2021 ~1MW Close Fuel Recycle

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ECR RFQ CM1 + …… + CMn

LEBT MEBT

SC_LINAC (~5mA@~200MeV d+Be)

Granular Target

Blanket

Fuel Recycle Compact Neutron Source： 1, Verify Recycle Fuel

• UC Pellet Fuel Properties • 238U239Pu Breeding rate • Optimization of Fuel Distribution

2，Irradiation of Materials • Cladding（SIMP、SiCf/SiC、SiC/Ti3SiC2…） • Core (...same as above...) • Window between Accelerator and Target • …

11

Reactivity Control Subcritical core with AD Good design reactor controller (∆k--5% ) without AD

Decay Heat Removing Smaller decay heat (<10% LWR at discharge, <1/3 ~ 10yr UNF) Neutrons, photons < 1/3 of LWR at discharge Fuel cladding material (>1500℃) for air removing heat in accident

Radioactive material confinement Two shell of cladding to shield against radioactive releases Cladding material ( > 1500℃ & > 50MPa) to limitation of

radioactive release during accident

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Close Fuel Cycle Waste <4% & <500yr

Resources Recycle (transmutation, breed, burning)，no need to add LEU in ≥ 2nd generation ADANES UNF treatment simplified ---<1/3 of P/T Schema

Deep (~30yr) burnup core

Modular Reactor ( Blanket )

Higher Top higher ηe

Part time (10%~15%) AD

Optimize the AD power

< 15MW/1GW sub-core

……

Nea3109 (OECD) 3a: FR + TRU 4: ADS+MA

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Researches Based on High Intensity Ion Beam: I. Nuclear Physics Low energy Nuclear Structure & Nuclear Astrophysics Hadron Nuclear Physics

II. High Energy Density matter Physics(+electron) III. Nuclear Energy ADSADANES Burner Fusion?

IV. Irradiative Material Compact, High Flux Neutron Source/electron

V. Neutrino Experiment VI. Convert SNF Recycle Fuel

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230 km 1500 km

ADS+HIAF Jiangmen

C-DUSEL Ningde

CAS: IMP, IHEP, HIPS,USTC, UCAS, … GNC, CNNC, Universities, Other Inst.…

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Progress HIAF, ADS R&D in Time Schedule Conception Design of HIAF, CIADS Projectiles have been

approved by Gov. before end of last year High Flux Compact Neutron Source Received 1st Fund, for

Deuteron Injector & Target R&D Jiangmen Neutrino experiment started Infrastructure

Construction and Key Component R&D on going New Site of burner in Huizhou, Guangdong Province has Fixed ADANES Fuel Recycle R&D, Remove FP from SNF, intensively New Site of Fuel Recycle in Ningde, Fujian Province has fixed

16

I. Introduction Motivation Roadmap New Site, New Research Center

II. Progress of ADS/ADANES Configuration of C-ADS Accelerator System Spallation Target Subcritical Core Fuel Recycle Material R&D …

17

Main Linac Tasks of IMP

Tasks of IHEP

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ECR Commission： >25 mA & 35 keV Improve on Reliability, Stability, maintaining in >2000hr ~8 short (<1sec.) beam trip in CW operation in >100hr

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ECR+RFQ (>1000 hrs)： >10mA@2.15MeV, CW， Eff.= 95~97%，δE/E ~1.9% (FWHM) June 30, 2014 ECR+RFQ+TCM1 >11mA@2.55MeV, CW Eff.=95~97%, δE/E ~1.5% >Feb. 13, 2015

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Beam energy: 5.2±0.1MeV I=~10.2mA

5.2 MeV&10.2 mA, 10% duty factor beam in June 8th，

5.3MeV&2.7mA CW beam in June 23 2015

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No obvious temperature rising and vacuum abnormal were observed in whole beam line. Arcing of ECR 3 times, RFQ shut down last time due to high reflection from beam loading.

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162.5 MHz Taper HWR

Beta=0.1

Beta=0.15

Beta=0.21

IMP & IHEP in 2016

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Ball

Beam

Pip

e

Out

let

Gra

nula

r Fl

uid

by G

ravi

ty

Principle of Granular Fluid Spallation Target

Science China Tech. Sci. 58(10) July 2015

Spallation neutron

• Granular fluid operate stable as sand clock

• Target heat removing off line and grain update on line simply

• Higher target power capacity: 10~100 MW

• Dissipation the shock wave induced by beam trip

• Relieve short beam trip (<10s) requirement as discrete medium in target

• Dust handling require • High cost effective

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Parameters

Granular material Tungsten / Tungsten alloy /…

Structure material TZM/SiC

Granular size 10±5mm

Inlet temperature of

granular

250 oC

Proton beam 1GeV@10mA=10MW

Intensity of beam >100 μA/cm2

Diameter of beam spot 10cm

Average temperature increase

Average velocity

400 ~0.8m/s

500 ~0.5m/s

600 ~0.35m/s

800 ~0.25m/s

Mass parallel Simulation: Contact mechanism + MD + MC transport K20GPU 2500ALU * 32 Number of Ball: 0.5 M

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Large scale loop & HT test Granular target test bench

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Lift Setup

Heat Exchanger

Beam-Target

Exp. of E-Beam on W Granular Target

<20mA@2.5MeV e

Identify Target Power Density of proton beam 1.0GeV@10~20mA on W

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Designed flow rate in a 100MW core (ΔTcoolant=150℃):

Coolant Heat Capacity (J/ml·K)

Flow Rate （L/sec.）

Water ~4 ~170 *Na ~1 ~670 *LBE ~1.6 ~410 **Molten Salt ~4 ~170 **Helium ~0.04 ~17745（550~850oC&8MPa) **He + SiC (Grain) ~1.4 ~470

**Water + Steam ~1855（250~550oC&8MPa） *ΔTcoolant could be higher than 250 ℃ **ΔTcoolant could be higher than 350℃

Fast Reactor Top： Dry Steam (overheat) Core： Wet Steam Bottom：Water

• Neutron modulate∝ ∑𝝆 ∗ 𝝈s (density of wet steam~1/30 water)

• H~1500kJ/kg (enthalpy, 8 MPa, 295oC) • Lower corrosion rate as lower density of

overheat steam far from supercritical water

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T distribution in tube

External Heating Pressure：4 MPa Rate：1.34 W/m2

Vcoolant：2~1.5 m/s

Internal Heating Pressure：2.8MPa Rate：1.64 W/m2

Vcoolant：4~5.5 m/s

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Neutron Spectrum

Power Distribution (55MW/m3)

Burnup Thermal Dynamic

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900 1000 1100 1200 1300 1400 1500 1600 1700 1800

0.0

0.1

0.2

0.3

0.4

0.5

0.6

f

Temperature (℃)

U3O8 1700oC 6h

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4 6 8 10 12 14

0

1000

2000

3000

4000

5000

Before After

Counts

Engery/KeV

Nd

U

XRF Spectrum of Nd & U from original sample and that after separation （ 5.15% 1.46%，remove 71.65% Nd2O3 from original sample）

Separated by Centifuge from Solution of Ion Liquid + Organic Liquid

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80um

300um

600um

U Fuel Pellet SiCf/SiC Cladding L>30cm

δ=0.5mm, PIP coating

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Material R&D : SIMP Steel (Martensite)

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GPU irradiation effects (GIR)

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Blanket

ECR RFQ CM1 + …… + CMn

LEBT MEBT

Superconductor Linac (~1GWth ~15mA&1GeV p+W…)

Window Between Acc.&Tar. Granular Target Reactor Core

Efficiency of Nuclear Electricity Generator: PWR: ~33% ADANES: >31%~~36% with AD >35~~40% without AD

Item Present Design Future Developing Beam Trip Demo Require Industry Require Window Lifetime 2~3 Month >6Month Target Power ≤15MW ≤10MW Cladding Material HT9//SiCf/SiC SIMP/MAX//SiCf/SiC Cladding Temp./Life ~550 oC / 5 yr 600~750 oC / 10 yr Inlet/Outlet T 250oC/<530 oC 250oC/<700 oC GEM [Pe/(Pb/ηacc)] >6.5 >13

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ADANES Conception Proposed, Approaches Optimizing

Accelerator System 162.5MHz Injector >2.55MeV&11mA CW (5.3MeV&2.7mA) proton beam

Spallation Target (new, simplify) Granular flow target is Proposed and testing with e-beam

Subcritical Fast Core (new, simplify) Water + Stream coolant core R&D intensively

Fuel Recycle (partial new, simplify) HT-Dry + REs Removing Processes R&D intensively

ADANES Material R&D (W, Be2C, SIMP, MAX, SiCf/SiC…): SIMP Steel (similar HT9) produced and Improving in 5 Tone Scale SiCf/SiC, SiC/Ti3SiC2 & other HT used in core and cladding，R&D intensively

GPU based S-Computing used for optimization of System Design

37 37

Welcome to Collaboration !

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P&T ADANES Close Fuel Cycle

Refine/Extract PUROX，Chemistry with water，Pyro-Process

Ext. AIROX (OREOX) + RE Extraction without water

Waste MA<1% MA in UNF

Difficult，Extract pure MA ≠ <1% MA in waste

Simple, Remove >50%FPs: volatile+RE, <1%MA in waste

Fuel Recycle No final solution, the more toxicity and complexes with higher generation

Remove >50% FPs, Residual transmuting, breeding & energy amplify in Burner

Transmutation Fuel MA：higher radioactive UNF: medium radioactive

Burning Stability Unstable More stable Proliferation Enrich Actinide, high risk No enrichment, low risk Start up fuel (LEU)

Every Generation

LEU in 1st gen., Converted Pu in 2nd generation and later

Feasibility Low / Complexes High / simple, safety Cost Effective Low High

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Corrosion Test in SC Water(600℃、25Mpa、1000h)

Testing Steel Chemical Component (wt%) Steel C Si Cr Mn W Ta V Nb Ni Mo S/ppm P/ppm

SIMP 0.22 1.22 10.24 0.52 1.45 0.12 0.18 0.01 － － 43 40 CLAM 0.091 0.04 8.93 0.49 1.51 0.15 0.15 － － － 18 30

P91 0.1 0.26 8.5 0.46 － － 0.20 0.04 0.17 0.92 20 30 P92 0.1 0.38 8.63 0.42 1.59 － 0.164 0.053 0.15 0.37 10 14

TP347 0.08 0.6 18 1.6 － － － 0.8 10 － <30 <40 304 0.09 <0.03 18 <1.0 － － － 0.05 9.7 － <10 <40

0

200

400

600

800

1000

1200

SIMP 、P91、 P92、 CLAM：

CLAM

P92P91

SIMPTP347

Weig

ht g

ain/

mg•

dm-2

Steel

304

304 、TP347： 奥氏体不 锈钢