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Slide 149th GIF PG and 43nd EG Meeting, 26-27 May, 2020
SCWR System Steering Committee
Y.P. Huang*, L. Walters, M. Krykova, A. Sedov and A. Yamaji
49th GIF PG and 43nd EG Meeting, 26-27 May, 2020
*SSC Chair
SuperCritical Water-cooled Reactors
Slide 249th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Contents
•Gen-IV SCWR System Members and Projects
•System Integration and Assessment Provisional Project
•Thermal-Hydraulics and Safety Project
•Materials and Chemistry Project
• Information Exchange and Dissemination
•Summary
Slide 349th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Gen-IV SCWR System Members and Projects
System Arrangement Signatory Representatives
Canada (2016) L. Walters, K. Huynh
China (2016) Y.P. Huang (Chair), L.F. Zhang
Euratom (2017) M. Krykova, R. Novotny
Japan (2016) A. Yamaji
Russian Federation (2016) A. Sedov, A. Churkin
Project Arrangement Signatories
Materials and Chemistry (2010)* Canada, China and Euratom
Thermal-Hydraulics and Safety (2009)* Canada, China and Euratom
System Integration and Assessment
(Provisional)
Managed under the System Steering
Committee (Project Plan in draft)
*Project Plans are being updated for extending the Project Arrangements
Slide 449th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Thermal-Hydraulics & Safety Project
Project Arrangement Signatory Representatives (Member, Substitute)
Canada (2009) A. Nava-Dominguez, Chukwudi Azih
China (2016) J.-G. Zang (Chair), X.-J. Liu
Euratom (2009) M. Guido, A. Kiss
Gen-IV SCWR System Members and Projects
Project Arrangement Signatory Representatives (Member, Substitute)
Canada (2016) L. Walters (Chair), J. Li
China (2016) L.-F. Zhang, B. Gong
Euratom (2017) A. Saez-Maderuelo (Co-Chair), R. Novotny
Materials & Chemistry Project
Slide 549th GIF PG and 43nd EG Meeting, 26-27 May, 2020
SCWR System Steering Committee Activities
• SCWR SSC&PMB Spring meeting in 2020
– originally scheduled in Shanghai, China, March 19-20, 2020
– First delayed to May; Now Cancelled
• GIF-IAEA IEM meeting in 2020
– Information Exchange bi-annually with GIF and IAEA member states
– A forum for research and developments between international
research organizations.
– Originally scheduled in Shanghai, China, March 16-18, 2020
– Now Cancelled
• SCWR SSC&PMB Autumn meeting in 2020
– planned in Vancouver, Canada, September, 2020
– Depending on the virus situation
• 10th International Symposium on SCWRs in 2021
– planned in Prague, Czech, March-2021
– The system steering committee has been setup
Slide 649th GIF PG and 43nd EG Meeting, 26-27 May, 2020
• China SCWR Project
– China SCWR Thermal Hydraulic & Safety R&D, ~¥8.33Millon RMBs,
2020~2022,
– China SCWR Materials and Chemistry R&D, ~¥ 7.73Millon RMBs,
2020~2022
– Kick-off meeting held in 10th-Jan-2020
» Complete the China SCWR design-CSR1000 international review
» Setup Several international benchmarks
• Joint project EU-Canada-China
– Assessing the feasibility and identification of safety features of an
intrinsically and passively safe small modular reactor cooled by
supercritical water (SCW-SMR)
– Starting date 1st September 2020
– Material testing, thermal hydraulice and safety, reactor physics,
Synthesis and Guidelines for Safety Standards.
– Total effort 965 person months
System Integration & Assessment ProvisionalProject
Slide 749th GIF PG and 43nd EG Meeting, 26-27 May, 2020
System Integration & Assessment ProvisionalProject
• Being managed under System Steering Committee
• Up to now, Four SCWR core concepts with thermal spectrum
and three other core concepts with mixed or fast spectrum have
been proposed,
•
Slide 849th GIF PG and 43nd EG Meeting, 26-27 May, 2020
System Integration & Assessment ProvisionalProject
Canada China EU Japan Russian
Federation
Type PT PV PV PV PV PV
Spectrum Thermal Thermal Thermal Thermal Fast Fast
Pressure (MPa) 25 25 25 25 25 24.5
Inlet Temp. (°C) 350 280 280 290 280 290
Outlet Temp. (°C) 625 500 500 560 501 540
Thermal Power (MW) 2540 2300 2300 3794 1602 3830
Efficiency (%) 48 43 43.5 46 44 45
Active Core Length (m) 5 4.2 4.2 4.2 2.4 4.07
Fuel Pu-Th (UO2) UO2 UO2 UO2 MOX MOX
Moderator D2O H2O H2O H2O -/ZrH -
# of Flow Passes 1 2 3 1/2 1/2 1/2
Slide 949th GIF PG and 43nd EG Meeting, 26-27 May, 2020
• R&D activities in China
– Heat transfer experiments of supercritical
and near-critical water flowing in a three-
rod bundle with spacer grids; Three heated
rods and three unheated rod-like elements
with an outer diameter of 15 mm and a
pitch to diameter ratio of 1.2
– Experiments of heat transfer to
supercritical Freon R134a flowing upward
and downward in a circular tube with inner
diameter of 10mm with heat fluxes of 20-
65kW/m2, mass fluxes of 400-1000kg/m2s,
bulk fluid temperature of 80-115℃ at
pressure condition of 4.2MPa
Thermal-Hydraulics and Safety Project Update
Slide 1049th GIF PG and 43nd EG Meeting, 26-27 May, 2020
• R&D activities in China
– Performed natural circulation numerical
analysis with SCP water and carbon
dioxide. For the supercritcal water NC
instability, the preliminary analysis work
has been done with the system analysis
code.
– Performed parallel pipes instability
numerical analysis with SCP water with
Relap5 code
– Performed the investigation of critical flow
model for supercritical pressure condition
based on isentropic flow and thermal
equilibrium assumptions
Thermal-Hydraulics and Safety Project Update
220 240 260 280 300 3200.010
0.015
0.020
0.025
Pipe 125mflow (kg/s)
Time (s)
z=0.0m z=1.0m z=2.0m z=3.0m
Φ11×2.5
L=
3000m
m350m
m200m
m
kin,1=5.4 kin,2=5.5
kout,1=4.93 kout,2=6.46
Inlet Plenum
Entrance Section
Riser Section
Outlet Plenum
Φ11×2.5
L=
3000m
m350m
m200m
m
kin,1=5.4 kin,2=5.5
kout,1=4.93 kout,2=6.46
Branch, 123
Branch 140
Inlet Plenum
Entrance Section
Riser Section
Outlet Plenum
TMDP 120
Pipe E1
124
Pipe E2
134
Pipe H1
125
Pipe H2
135
Pipe R1
126
Pipe R2
136
TMDPJUN injun 110
Jun J1
112
Jun J2
114
Jun J3
116
Jun J4
118
TMDP 142
Jun J5 119
Z=0.0m
Z=1.0m
Z=2.0m
Z=3.0m
Slide 1149th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Thermal-Hydraulics and Safety Project Update
• R&D activities in EU
– The thermal hydraulics of the fuel assembly design of Th-SCWR has
been simulated by the ANSYS CFX CFD
– Calculations have proved that the wrapped wire spacer improves the
heat transfer in most of the sub-channels within the fuel assembly
Slide 1249th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Thermal-Hydraulics and Safety Project Update
• R&D activities in EU
– RANS analyses of CO2 data by Kline (2017), making use of an algebraic
heat flux model (AHFM) developed in the STAR-CCM+ code
• remarkable capability
of the model to
correctly simulate heat
transfer phenomena at
relatively low flow rates
• the phenomenon of
deteriorated heat
transfer termination at
the transition to gas-
like fluid was observed
Slide 1349th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Thermal-Hydraulics and Safety Project Update
• R&D activities in Canada
– Enhanced flow instability analysis
under supercritical conditions using
the Canadian system code
CATHENA, results were compared
against experimental data and
numerical experiments.
– Commissioned and conducted
experiments in a passive heat
transfer loop. This loop will assist
us to design a passive low grade
heat removal system. The
experiments were modelled using
the thermalhydraulics system code
CATHENA.
HEXSH1~2
WD
OW
N2
VA
PU
P4
VA
PU
P1
EVPIN2
EV
PO
UT
EVPHD
TEE1
FIN
L
FIN
R
FIN
M
SU
RG
E1
SU
RG
E2
PS
V-1
FIN
RE
X
FIN
ME
X
FIN
LE
X
HXIN
HXOU
PIPEIN
PIPEOU
HXPASS1~4
VA
PU
P2
VA
PU
P3
VS
UR
GE
TEE2ELBOW1
T1P1T2P1
EL
BO
W2
T2
P2
T1
P2
WD
OW
N3
WD
OW
N4
WD
OW
N6
SU
RL
I2S
UR
LI1
PS
V-2
VS
UR
LI
EVPIN1SIGHTG
WDOWN1
WDOWN0
VAPUP5~7
WDOWN5
EVPIN3
PT-4
PT-1
MT-1
PT-2RTD-2
RTD-1
RTD-4
RTD-3
PT-3
RTD-7
Slide 1449th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Thermal-Hydraulics and Safety Project Update
• R&D activities in Canada
– A series of simulations were performed to evaluate the CANFLEX
variant 20 as a candidate fuel bundle for the Canadian Supercritical
water SMR. Steady-state and transient cases were assessed using
neutronics simulations.
– New model for chocking flow is ongoing in collaboration with the
École Polytechnique de Montréal.
– A review of flow-induced vibration of wire-wrapped fuel bundles was
conducted.
Slide 1549th GIF PG and 43nd EG Meeting, 26-27 May, 2020
• R&D activities in Canada
– Establishing a new collaboration with a Canadian
university to study advanced metallic insulators
using additive manufacturing.
– Completed the specifications of a neutronics
code-to-code exercise (on hold due to pandemics
– Measured the thermal conductivity of various fuel
channel components.
– Progress on cogeneration economics focused on
investigating the use of economics frameworks
to address depreciation and highlight the
connection to the to the economics of designing
advanced reactors.
– SCW cell design and construction for the next
phase of the neutron scattering experiments
under SCW conditions. All the requirements were
determined and various design options to meet
the requirements were thoroughly examined.
Thermal-Hydraulics and Safety Project Update
Slide 1649th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in China
– The SCC tests were conducted on 30% cold worked Alloy 690 in high
temperature pressurized water at temperatures between 360°C and
550°C. Creep induced cracking was measured at each testing
temperature in inert argon environment to study the effect of creep on
the overall crack growth behavior
Materials and Chemistry Project Update
– Experimental results showed
that creep contributed to more
than 80% of the overall crack
growth rate at temperatures
above 450 °C in supercritical
water, while only 8% at 360 °C
in sub-critical water
Slide 1749th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in China
• Two candidate alloys modified from 310S austenitic stainless steels
were subjected to ionic irradiation to see their radiation damage
effects. Proton radiation tests were performed on an ion accelerator
with implanting energy of 50keV, and temperature at 290 °C up to
doses of 0.1 and 0.3 dpa by proton, and at 550°C up to 5, 15 and
30dpa by Ar ion.
• The irradiation tests showed that minor alloy elements added to the
alloys played different roles after irradiation
Materials and Chemistry Project Update
Slide 1849th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in China
• Alumina forming austenitic (AFA) alloy is proposed as a new grade
SCWR cadidate alloy in view of the existing reported research works
• High Al, Cr content, but insufficient Ni content (25Ni20Cr5Al) will result
in the formation of duplex γ+α matrix, as Al is a strong ferrite
stabilization element. Therefore, the content of Ni should be carefully
designed based on the content of Al, Cr and other minor ferritic
forming elements to obtain a necessary single γ phase structure.
Materials and Chemistry Project Update
Slide 1949th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in EU
• Exposures in SCWL (395 C°, 25 MPa) for 150,
550, 1000 and cycling 150+1000, 150+550+1000
hours.
• Tested materials: IN 718, Alloy 800H, T505 (T91),
NIMONIC 91, NITRONIC 60, AISI 321H (X8CrNiTi18-
10).
• Chemical analysis by SEM/EDX, EBSD and XRD.
Special analysis of thin layers by FIB.
• Commissioning of new facilities - autoclaves (137
ml, 600 C°, 25 Mpa; 850 ml, 700°C, 30 Mpa).
Surface of T505 after 1700 hours in SCW (figure up, MAG 5.54kx, SE)
Surface of Alloy 800H after 1700 hours (figure down, MAG 5.54kx, SE)
Materials and Chemistry Project Update
Slide 2049th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in EU
• Study of the evolution of voids formed in A 690 TT samples pre-tested
in SCW by mean in-situ tests. Collaboration between CIEMAT and CVR
• MEACTOS project (te study of the SCW as an accelerating
environment to produce stress corrosion cracks in an austenitic
stainless steel 316 L type L)A) Photograph of the device used to perform the tensile in-situ tests inside the chamber of a SEM: B)
Evolution with temperature and stress of a C,N(Ti) found in a A690 TT specimen previously tested in SCW.)
Materials and Chemistry Project Update
Slide 2149th GIF PG and 43nd EG Meeting, 26-27 May, 2020
R&D activities in Canada
• SCW Chemistry and Materials Static
Analyses (Autoclaves)
• Conducted several corrosion experiments for
cladding candidates for the Canadian SCWR
and the SCW-SMR.
• Conducted preliminary measurements of
thermal conductivity of corroded cladding
candidates to assess the impact of corrosion of
the fuel performance and safety of the Canadian
SCWR and SCW-SMR.
• Conducted corrosion experiments of welded
specimens to assess the impact of the welding
(heat affected zone).
• SCW Chemistry and Materials Dynamic
Analyses (Loop)
• Conducted several corrosion tests under
dynamic conditions.
• Round Robin #2 – Memo Completed 2019.
Materials and Chemistry Project Update
We
igh
t L
oss (
mg
/dm
2)
310S 800H
0
10
20
30
40
50
60
70
80
90
100
110
120
Mean+1.5*Std Dev
Mean-1.5*Std Dev
Mean+Std Dev
Mean-Std Dev
Mean
Slide 2249th GIF PG and 43nd EG Meeting, 26-27 May, 2020
Summary
• The SCWR meetings have been affected by the virus. The
SSC/PMB 2020 spring meeting and IEM 2020 meeting has
been cancelled
• The China two SCWR projects (TH&S, M&C) has kicked off
to deepen the SCWR concept design for international peers
review
• The joint EU- Canada-China project in H2020 has passed
the first round assessment. It will start this September
Slide 2349th GIF PG and 43nd EG Meeting, 26-27 May, 2020
THANK YOU FOR ATTENTION !