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 • …
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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
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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 …
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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): >[email protected], CW, Eff.= 95~97%,δE/E ~1.9% (FWHM) June 30, 2014 ECR+RFQ+TCM1 >[email protected], 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
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
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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
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