SuperCritical Water-cooled Reactors Extracted for the Virtual ......SuperCritical Water-cooled Reactors Extracted for the Virtual Event 14th GIF-IAEA Interface Meeting 49 th GIF PG

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

taninaka

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Extracted for the Virtual Event 14th GIF-IAEA Interface Meeting


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


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


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


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


• 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



• 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，

•



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


• 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


• 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


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



• 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



• 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



• 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




– 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.



– 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.



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



• 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




• 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.



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)



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.)



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.


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


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


THANK YOU FOR ATTENTION !

Documents

SuperCritical Water-cooled Reactors Extracted for the Virtual ......SuperCritical Water-cooled Reactors Extracted for the Virtual Event 14th GIF-IAEA Interface Meeting 49 th GIF PG