ISSN 2189-7107

KURRI-EKR- 8

第 14 回加速器駆動システムおよび核変換技術に関する
アジアネットワークワークショップ報告書

Proceedings of 14th International Workshop on Asian Network for
Accelerator-Driven System and Nuclear Transmutation Technology(ADS-NTT 2016)

編集：卞

哲浩

Edited by Cheol Ho Pyeon

京都大学原子炉実験所
Research Reactor Institute, Kyoto University

Preface

The proceedings describe the current status on research and development (R&D) ofaccelerator-driven system (ADS) and nuclear transmutation techniques (NTT), including
nuclear data, accelerator techniques, Pb-Bi target, fuel technologies and reactor physics, inEast Asian countries: China, Korea and Japan.
The proceedings also include all presentation materials presented in “the 14th International
Workshop on Asian Network for ADS and NTT (ADS-NTT2016)” held at Mito, Japan on 5th
September, 2016. The objective of this workshop is to make actual progress of ADS R&D
especially in East Asian countries, as well as in European countries, through sharing mutualinterests and conducting the information exchange each other.
The report is composed of these following items:-

Presentation materials: ADS-NTT 2016

Cheol Ho Pyeon
September 2016

Keywords:
Status report, ADS, NTT, Asian countriesiContents
The 14th International Workshop on Asian Network for Accelerator-Driven
System (ADS) and Nuclear Transmutation Technology (NTT)(ADS-NTT2016), 5th September, 2016, at Mito, Japan
Chair: Dr. Kazufumi Tsujimoto, (JAEA, Japan)

Activities in JAEA induced 1st Technical Meeting (Sep., 2015) for ADS-NTT 2015
Dr. Toshinobu Sasa (JAEA, Japan)･･･････････････････････････ 1

Status of SNF, Gen-IV & ADS in Korea
Prof. Seung-Woo Hong (Sungkyunkwan Univ., Korea)･･････････ 24

Current Status of Subcritical Reactor Technology for ADS in China
Prof. Yunqing Bai (INEST, CAS, China)･･････････････････････････ 51

Current Status on ADS Experiments at KUCA
Prof. Cheolho Pyeon (KURRI, Japan)ii･････････････････････････ 62

14th International Workshop (General Meeting) on
Asian Network for Accelerator-Driven System (ADS) andNuclear Transmutation Technology (NTT) in 2016
(ADS-NTT 2016)- Agendaorganized by Research Reactor Institute, Kyoto University
sponsored by J-PARC, Japan Atomic Energy Agency
5th September, 2016, at Hotel Terrace Garden Mito

September 5th (Monday)
13:30

Registration

13:55 - 14:00

Opening remarks (Prof. Cheolho Pyeon, Kyoto Univ., Japan)

Progress and Status on ADS in Asian countries(Chairman: Dr. Kazufumi Tsujimoto, JAEA)
14:00 – 14:40“Activities in JAEA induced 1st Technical Meeting (Sep., 2015) for
ADS-NTT 2015” (Dr. Toshinobu Sasa, JAEA, Japan)

14:40 – 15:20“Status on Gen-IV research activities in Korea” (Prof. Seung-Woo
Hong, SSKU, Korea)

15:20 – 15:40

Break

15:40 – 16:20“Current Status of Subcritical Reactor Technology for ADS in China”(Prof. Yunqing Bai, INEST, CAS)

16:20 – 17:00“Current Status on ADS Experiments at KUCA” (Prof. Cheolho Pyeon)

17:00 – 17:20

Break

17:20 – 17:50

Round Table by Speakers (Chairman: Prof. Cheolho Pyeon)

17:50 – 18:00

Closing remarks (Chairman: Dr. Toshinobu Sasa)

18:30 – 21:00

Dinner with information exchange hosted by JAEA and KURRI

Secretary office
Contact with Prof. Cheolho Pyeon
Phone: +81-72-451-2356, Fax: +81-72-451-2603
E-mail: pyeon@rri.kyoto-u.ac.jp

Activities in JAEA

inducing 1st Topical Meeting for ADS-NTT
2015
14 th International Workshop on Asian Network for ADSNTT 2016
5 th Sep. 2016, Mito Japan

Toshinobu Sasa

J-PARC Center, Japan Atomic Energy
AgencyContents
 Activities for ADS development in JAEA

National Policy for Energy Supply Future ADS Design
 Status of J-PARC Facility Design Topics in 1st topical meeting Summary

2016/9/12

Asian ADS-NTT Workshop 20162

National Policy for Energy Supply

2016/9/12

Asian ADS-NTT Workshop 2016

3

Nuclear Energy Situation in Japan- Nuclear Power in Latest Strategic Energy Plan -2. Principles of Energy Policy and Viewpoints for Reform Nuclear Power

Important base-load power source as a low carbon and quasi-domesticenergy source, contributing to stability of energy supply-demand
structure, on the major premise of ensuring of its safety, because of theperspectives; 1) superiority in stability of energy supply and efficiency,2) low and stable operational cost and 3) free from GHG emissions during
operation.
Dependency on nuclear power generation will be lowered as much as
possible by energy saving and introducing renewable energy as well as
improving the efficiency of thermal power generation, etc.
Under this policy, we will carefully examine a volume of electricity to be
secured by nuclear power generation, taking Japanʼs energy constraints
into consideration from the viewpoint of stable energy supply, cost
reduction, global warming and maintaining nuclear technologies andhuman resources.

2016/9/12

Asian ADS-NTT Workshop 2016

4

Nuclear Energy Situation in Japan- Radioactive Waste Issues -Chapter 3, Section 4 Re-establishment of the nuclear energy policyGovernment Of Japan (GOJ) will promote technology
development on volume reduction and mitigation of degree ofharmfulness of radioactive waste. Specifically, development oftechnologies for decreasing the radiation dose remaining inradioactive waste over a long period of time and enhancing thesafety of processing and disposal of radioactive waste, including
nuclear transmutation technology using fast reactors andaccelerators, will be promoted by utilizing global networks forcooperation. Also, while GOJ examines the situation of study andprogress in terms of final disposal, it studies the feasibility ofintegrated implementation of the R&D for final disposal andreduction of volume, international research cooperation and a
researcher resource development related to them.

2016/9/12

Asian ADS-NTT Workshop 2016

5

Future ADS Design

2016/9/12

Asian ADS-NTT Workshop 20166Issues and R&Ds for ADS using JPARC
Accelerator
High Power, Reliability, Cost, etc.

MA-loaded Subcritical Core
Physics and Control of SubcriticalCore with MA-bearing Fuel, etc.

Operation Experience, etc.

Structure
Design of Reactor Vessel, Pumps,
SGs, Quake-proof Structure,
Beam Duct & Window, etc.

・2 Individual Facilities
Transmutation Physics Experimental
Facility：TEF-P
Neutronics Tests by Low Power BeamADS Target Test Facility：TEF-T

Utilize existing resources & knowledge

Material Irradiation by High Power BeamFuel, Cycle

Pb-Bi Spallation Target

Fabrication, Irradiation, Reprocessingof MA-bearing Fuel, etc.

Material Irradiation, Operation,
Lifetime Evaluation, etc.

Asian ADS-NTT Workshop 20162016/9/12

7

TEF-MYRRHA Joint Roadmap to Accelerate
Establishment of ADS Transmutation
ADS technology without MA fuel(Pb-Bi core, Acclerator, Operation Experience)Power

ADS Plant
30MW-beam, 800MWth・MA transmutationADS Demo⇒MYRRHA~2.4MW-beam, 50~100MWth・Demonstration of ADS

Physics of MA fuel and Target Development

Improve Window Material

J-PARC

MYRRHA

PurposeElemental Technology（Target、Physics）

System demonstration

Power

Proton:250kW
Core：500W(10Wbeam)

Proton:2.4MW
Core:50～100MW

MA
イオン源

J-PARC Transmutation
Experimental Facility

ターゲット

陽子ビーム

未臨界
核燃料体系
隔離弁
ＫＵＣＡ－Ａ架台
ＦＦＡＧ加速器

250kW-beam
・Pb-Bi target ・ADS core

電磁石

Simulate MA loaded core
Small Amount Irradiation(Several tens kg)• Lead the worldwide RD&D for transmutation technology incooperation with J-PARC and MYRRHA• Obtain knowledge & experience to realize ADS in 2030th

Basic tests (Pb-Bi loop, KUCA, etc.)2010
2016/9/12

2020

2030

Asian ADS-NTT Workshop 2016

2050

Year
8

ADS Proposed by JAEA - LBE Target/Cooled Concept Steam
蒸気発生器
Generator

主循環ポンプMain Pump• Proton beam : 1.5GeV ~30MW• Spallation target : Pb-Bi• Coolant : Pb-Bi• Subcriticality : keff = 0.97

内 筒 tube
Inner
ビームダクトBeam
Duct• Thermal output : 800MWt

Window
ビーム窓• Core height : 1000mm

Core
Vessel
原子炉容器
Core
Support
炉心槽• MA initial inventory : 2.5t

Guard
Vesselガードベッセル• Fuel composition :(60%MA + 40%Pu) Mono-nitride
炉心支持構造物
Support
Structure• Transmutation rate :10%MA / Year (10 units of LWR)
• Burn-up reactivity swing : 1.8%∆k/k
Asian ADS-NTT Workshop 20162016/9/12

9Grant-In-Aid for Nuclear
Researchand development to solve the engineering issues for
Researchtransmutation system using accelerator-driven system
1. MA partitioning process development using
actual waste solution
Spent fuelAn(III): Trivalent actinide
Ln:
Lanthanide
FP:
Fission product
PGM: Platinum group metal

Roughseparation of U

U

Separation ofU, Pu, Np

U, Pu, Np

Separation ofAn(III), Ln

Separation ofAn(III) / Ln

Separation ofCs, Sr

3 years
5M$max

2. Feasibility design study of ADS
2.1 Reactor physics experiments to simulate
ADS using Kyoto University Critical
Assembly (KUCA) with FFAG proton
accelerator

MA partitioning processexperiments from actual waste
solution of used nuclear fuelAm, CmFFAG Accelerator

KUCA Core

2.2 Research and development forengineering issues of ADS

Ln

Movable support

Cs, Sr

Separation of
PGM



PGM
The other FPSeparation of An(III) andlanthanide from HLLW:

Separation of An(III)from lanthanide:

New extractants based on“CHON principle”:
TDdDGA

Invention of new extractants

2016/9/12

Improved reliability of proton LINAC
for ADS
Enhanced feasibility of beam
Proton beam
window of ADS by compensating
the burnup reactivity change
Steam generator

Robust safety aspects based on Reactor vessel
detailed plant dynamic analysis Beam window

Asian ADS-NTT Workshop 2016

Bending magnet

Fuel exchanger
Beam ductPrimary pump
Spallation target
Subcritical coreCore support

10

Increase Beam Reliability
Beam Transport #1
Beam Dump #1

Accelerator #1

Beam Dump #2

Accelerator #2

Beam Transport #2
Subcritical
Core







To improve the reliability of accelerator, parallel accelerator
layout is an ultimate solution
By running two accelerators by 50% of rated power each,reliability requirement for ADS can be satisfied
Optimum layout of parallel accelerator should be determined

2016/9/12

Asian ADS-NTT Workshop 201611

keff adjustment by control rod

ADS with Control Rods for keff adjustment
Install Three B4C CRs (Total Worth:1.5%dk/k) Possible to keep proton beam current around
10mA during the burnup cycleCR Layout (Green)
2016/9/12

Beam Current Change during
burnup

Asian ADS-NTT Workshop 201612

Improvement of passive
safetyReflecting the Fukushima Accident, addition of

PRACS (Primary Reactor Auxiliary Cooling System)
is studied PLOHS with PRACS was analyzed by RELAP5-Mod3
 Confirm the coolant temperature can be kept
below 400°C even in the case of Station Black Out

2016/9/12

Asian ADS-NTT Workshop 2016

13

Subcritical corearrangement
Fuel Exchanger

Beam Duct
CRD
SG
Plug

 Layout of reactor

components
including newly
added equipment
was performed

Guide
Tube

 The scheme toreplace beam
window and fuel isconfirmed

2016/9/12

Asian ADS-NTT Workshop 201614

Status of J-PARC Facility Design

2016/9/12

Asian ADS-NTT Workshop 201615

Transmutation Experimental Facility

Investigate engineering characteristics
of LBE spallation target• 400MeV-250kW Proton Beam
• LBE Temperature 500℃max• Oxygen Potential Controlled• Hot Cell for PIE samples preparation

Explore neutronic performances of ADS and/or
MA-loaded core
• 400MeV-10W Proton Beam
• Table-split type Critical Assembly• MA-bearing pin type fuel for experiments
2016/9/12

Asian ADS-NTT Workshop 201616

Minor Actinide Fuel Handling
Dolly with Shield

Remote Handling Scheme

Pb Coolant Mockup

MA Fuel Loading Device

Requires remote handling device to storage/transport/loading of MA fuel
 Basic functional tests for MA fuel loading device is performed and confirmed the operation
 Heat removal test in Pb Coolant mockup is underway
 To improve accuracy of experiments, fuel rod identification methods is under consideration

2016/9/12

Asian ADS-NTT Workshop 201617

Design of Target Trolley
Level Meter
Exp. Tank
HX
LBE Filter
EMP
Freeze Valve

HeaterDrain Tank

Target Mockup

ShieldBase layout was finished considering thedrain route and maintainability throughshield window.
 Further design harmonized with remote2016/9/12
18
Asian ADS-NTT Workshop 2016
and PM will be performed.
operation by MSMLessons Learned in past 10 years• To realize TEF-T and ADS, JAEA built a static corrosion
experimental equipment (JLBS), four experimental leadbismuth loops (JLBL-1, 2, 3 and 4)• The equipment were installed for corrosion/erosion examination(JLBS, JLBL-1), measurement device development (JLBL-2,
4) and thermal-hydraulic experiments around beam
window(JLBL-3).
JLBL (JAEA Lead-Bismuth flow Loop)
JLBL-1

2016/9/12

JLBL-2JLBS (JAEA Lead-Bismuth
Static corrosion facility)

JLBL-3JLBL-4

Asian ADS-NTT Workshop 201619

New Test Equipment for TEF-T
DesignOxygen-controlled Lbe LOop for Corrosion tests in HIgh temperature•Material corrosion database for various temperature, oxygen potential, LBE flow rate will becollected•The loop will be operated from next April•Addition of corrosion test section with mechanical stress are planned

Integrated Multi-functional MOckup for TEF-T Real-scale TArget Loop
•Demonstration of safe operation of LBE loop by reflecting operation condition of J-PARC LBE
Spallation target•Tests for dynamic behavior of heat removal, functional tests of sensors, loop components areunderway•To prevent corrosion by flowing LBE, oxygen potential in LBE should be controlled in appropriate
potential range (10-5 to 10-7 %)•Development of oxygen potential sensor and loop tests for oxygen potential control mechanism
are underway

2016/9/12

Asian ADS-NTT Workshop 201620

Outline of "OLLOCHI"
Purpose

Fundamental study for future ADS development
Corrosion data collection for PIE on TEF-T irradiated materials.
Development of filtering system

Design concept








High temperature (>500℃) corrosion test
Multi test section
Non-contact type flow meter
Oxygen sensor, oxygen concentration control system
Purification system of LBE
Exchange test-piece without drain (to keep oxygen concentration)
Decrease flange connection to prevent LBE leakage

2016/9/12

Asian ADS-NTT Workshop 201621

Appearance of OLLOCHI
Extended pipes to
Pressure Difference gauge

Globe box

Expansion tank
Test
sections
Air Cooler
HeaterControlpanel

Ultra sonicflow meter
FilterDrain tank(Behind)2016/9/12

Gas
controlpanel
EMP
Asian ADS-NTT Workshop 201622

Schematic flow diagram of OLLOCHIHigh temp. section : max.550℃, T91
Low temp. section : max.450℃, SS316L
Flow rate : 1m/s at high temp. test section
Asian ADS-NTT Workshop 20162016/9/12

23

Tentative Corrosion Test
Program
Phase

2016

2017

2018

1
(Prooftest)

2(Corrosion test,
benchmark)3(Corrosion
test)

Oxygen concentration 10-5 – 107(wt.%)

2019

2020

4
5
(Corrosion(Corrosion
test,
test,
reproducibility
long run test))
)

2021

2022

6
(Corrosion
test)

7(Corrosion
test,
reproducibility
)

←

←

←

←

←

←

←

←

←

←

←

←

LBE flow rate

1m/s

←

←

←

←

←

←

←

←

←

←

←

←

ΔT（℃）

100

←

←

←

←

←

←

←

←

←

←

←

←

Temp.
（℃）

450

450

450

500

500

500

550

550

550

Time

3,000h1,000h 3,000h

5,000h1,000h 3,000h 5,000h(10,000h) 1,000h 3,000h

5,000h

Temp.
（℃）

450

450

500

500

500

500

500

550

550

Time

3,000h5,000h1,000h 3,000h

5,000h1,000h 3,000h

5,000h1,000h 3,000h

←

←

←

F/M steel,welds, coating,
ODS, etc.

←

Test
sectionNo.1
Test
section
No.2

Specimen

2016/9/12

Austenitic, F/M
Austenitic steel, welds,
F/M steel coating, ODS,
etc.

500

Asian ADS-NTT Workshop 2016

550

24

Outline of "IMMORTAL"• Target Mock‐Up loop "IMMORTAL" is a demonstration test loop with most of same
configuration/components of the primary cooling system of TEF –T target• Most of component are actual scales, except a temperature conditioner simulating heatgeneration by the incidence of proton beam.

Purpose of IMMORTAL
1. Dynamic behavior of heat removal
2. Confirmation of operation procedure
3. Integral test of individually developed components
of LBE technologies (including EMP & HX)
4. Production of control sample for PIE of TEF‐T
irradiation sample

2016/9/12

Asian ADS-NTT Workshop 2016

25

Schematic Flow Diagram of IMMORTAL

2016/9/12

Asian ADS-NTT Workshop 201626

Major Specifications of
IMMORTAL/TEF-T
Specifications

IMMORTAL

TEF‐TMax. temperature

500 ˚C500 ˚C

Temperature difference ΔT

100 ˚C100 ˚C

Max. Flow rate

120 liter/min

120 liter/min

Heat deposition by proton beamn/a

200 kW

Power of temperature conditioner

67 kW :to simulate heat generation(about 1/3 of heat deposition)< 10 kW:to control inlet temp. only

Amount of heat exchanger

Design 200 kW
Working 67 kW

200 kW

Inventory of LBE≈ 290 liter≈ 290 liter

Main piping

i.d. 69.3 mm

i.d. 69.3 mm ⇒ i.d. 42.6 mm

Main material

316 SS

316 SS / T91

Flow monitoring system

Ultrasonic flowmeter

Ultrasonic flowmeter

Oxygen Concentration (OC) control
systemAvailable(Pt/Air type sensor)

Available(Pt/Air type sensor)

Liquid pressure gauge

To be installed

Available

Freeze seal type of drain valve

To be installed

Available

2016/9/12

Asian ADS-NTT Workshop 201627

Full Scale TEF-T Target
PurposeModckupA) Confirmation of manufacturing methodB) Confirmation of the residual LBE after drain operation
Confirmed byC) Structural durability in non‐irradiation condition (erosion/corrosion)
long‐run testD) Confirmation of dynamic behavior& flow visualization(LBE flow, heat transfer, flow vibration)
Result of A) & present design of B)
A) BW(2mm thick) part was made by shaving from ingot, and successfully manufactured.
B) To reduce residual LBE, drain hole (6(W)×5(H)mm) was provided at the end of inner pipe.
Manufactured target vessel
Vertical section of target vessel

2016/9/12

Asian ADS-NTT Workshop 201628

LBE Flow visualization in Target
Purpose of flow visualization experimentTo verify the simulated LBE flow (In particular instability of central stagnant region)Confirmation of the effect of planned guide fin (to remove the central stagnant region)Experimental data acquisition to verify the fluid analysis result for upgrade of target vessel
Estimation of the instability of central stagnant region isimportant issue for TEF‐T target.

Central stagnant region

CFD result

2016/9/12



Full‐scale transparent acrylic model of target vessel
Asian ADS-NTT Workshop 2016

29

Fabrication of Oxygen
SensorPt
type: Air hole is prepared. To prevent LBE

leakage by YSZ failure, freeze seal design was
employed in housing.
Air hole
 Bi type: No air hole
SS housing
Length of sensor

240mm

Diameter of YSZ

6/4 mm (O/I)

Length of housing

140mm

For Pt typePt paste/SUS304 wire

For Bi type

Bi/Bi2O3=95:5/Mo wire

2016/9/12

YSZ
Pt type

Asian ADS-NTT Workshop 2016

Bi type30

Control of Co in flowing LBE condition
 Outline of JLBL-4
Specifications of JLBL-4
Main material

316SS

Inventory

20 L

Max. pressure

6 bar

Max. electrical power

7 kW heaters

Max. design temperature

500 ℃

Flow rate of LBE

Max. 40 L/min

Flow rate of observation

EMF

O2 sensor

Bi type sensor (made by SCK･CEN)

LBE temperature

350℃

LBE flowrate

26L/min
Asian ADS-NTT Workshop 20162016/9/12

31

Control of Co in flowing LBE condition
 Result
①

④

②

⑤
③

①

Ar continuous (2days)②

Ar+O2*1 150cc （50sccm×3min）③

Ar+H2*2 500cc（100sccm×5min）④

Ar+O2 150cc （50sccm×3min）⑤

Ar+O2 75ｃｃ
（50sccm×1.5min）*1: 20vol% O2*2: 4.5vol% H2

 Basic oxidation operation was
performed
 It is required to comprehend
the relationship betweenchange of Co and input ofoxygen.
 #③ will be also the effect ofresidual oxygen.
2016/9/12

Asian ADS-NTT Workshop 201632

Topics in 1st Topical Meeting on
Asian ADS-NTT Meeting

2016/9/12

Asian ADS-NTT Workshop 201633

Topical Meeting for LBE
Application







To increase professional information exchange, topicalmeeting was held in-between the regular ADS-NTT meeting
LBE handling technology was selected as a specific topic
Prof. J. Konys (KIT) gave an invited talk
14 presentations from China, Korea and Japan were discussed

2016/9/12

Asian ADS-NTT Workshop 201634

Group Photo

2016/9/12

Asian ADS-NTT Workshop 201635

Slide in Final Discussion

2016/9/12

Asian ADS-NTT Workshop 201636

Proceedings is available
online!
All presentations
during 2 days werecollected in a report
You can find thedigital document on
JAEA website

2016/9/12

Asian ADS-NTT Workshop 201637

Summary

P&T is specified as an option of Japanese energy
policy JAEA proceeds P&T using ADS and TEF design
works




Future ADS Design is performedStudies to improve reliability of intense proton beam
Researches to increase k-eff stability and safety of MA-core

Design study of TEF-T have been performed

Apply existing knowledge from J-PARC Mercury Target
Design optimization to prepare irradiation database for
ADS

Asian ADS-NTT Workshop 2016
1 topical meetingfor Asian ADS-NTT network

2016/9/12
st



38

Status of SNF, GEN IV & ADS in Korea
The 14th Workshop on Asian Network for ADS‐NTT
Mito, Japan
September 5, 2016
Seung‐W00 Hong, SKKU
Il‐Soon Hwang, SNU
Jueun Lee, SNU
Yong‐Hoon Shin, SNU
Myung Jae Song, HYU

 Faculty of DOES

Contents

I. Status of NPP and SNF in Korea
II. Status of GEN IV in Korea
III. ADS research in SKKU
IV. TORIA
V. Summary Faculty of DOES

I. Status of NPP and SNF in Korea

 Facultyof DOES
Current
Status of NPPs in Korea
Generation in 2011
Total : 496 TWh
Nuclear : 154.7 TWh (31.2%)

 In operation(27.053GWe) 23 units• 19 PWRs• 4 PHWRs (CANDU)

 Under construction(3.8GWe) 3 PWRs

Seoul• Shin-Kori-3 : ’08.10~• Shin-Kori-4 : ’09.08~• Shin Wolsung-2: ’08.09~

UlchinWolsong Under license review(5.6GWe) 4 PWRs

Yonggwang

In operation
Under construction
Under license review

Kori• Shin-Ulchin-1• Shin-Ulchin-2• Shin-Kori-5• Shin-Kori-6

Storage Capacity and accumulated SNF as of 2014

Accumulated amount (tons)
Storage capacity (tons)

http://blog.khnp.co.kr/blog/archives/20166

Lessons we learned from failures since 1983
• The government made nine attempts to look for a repository site
since 1983, but failed mostly until 2005.
• Two examples of Decide‐Announce‐Defend‐ Anmyeon‐Do (1990‐1991) ‐ failure‐ Guleop‐Do (1994‐1995) ‐ failure• (Partial) Engagement of Public and Local Government‐ Buan (2003) – still a failure• Success with LILW through Public Engagement‐ Gyeongju city (2005~)• PECOS for SNF

Example 1 : Decide‐Announce‐Defend
Anmyeon‐Do (1990‐1991)• Plan : To build a spent fuel interim storage (HLW)
To invest ~ $900M till 2000
To establish the 2nd KAERI in the local area
• Initiated by the government without engagement of local public• The plan was cancelled in June 1991

Example 2 : Decide‐Announce‐Defend
Guleop‐Do (1994‐1995)• The government decided and announced.
• Proposed site for nuclear waste:‐ Island made of granite (and considered as a safe geological formation)‐ HLW (Interim storage), LILW (Permanent)‐ only 10 people lived in that island (small compensation)

80 Km

Guleop‐Do (1994‐1995)• The residents in the island agreed with the government plan.
• However, people in neighboring islands and Incheon City objected.
• An active fault was found under the sea near the island, and the plan
was cancelled in the end of 1995.

(Partial) Engagement of Public and Local Government
Buan (2003)• Government requested public participation• Several local governments applied for the nuclear waste management site.
‐ Package: Nuclear waste storage site & Proton Accelerator Project‐ The headquarter of Korea Hydro & Nuclear Power Co. will move to the site.
‐ The local government supported and applied.
• Eruption of violence. Injuries of people. Conflict among the local people.
• The plan was cancelled in 2004.

Turning point• On Dec. 17, 2004
The government decided that the repository sites for LILW
and SNF would be separately sought after.
• Involvement of local public was requested by thegovernment

Success with LILW: Through Community Agreement
Gyeongju city (2005 ~ 2015)• Disposal site for just LILW
• Residents applied for hosting the site
> Local governments carried out the vote of residents (2nd Nov. 2005)> Gyeongju (89.5% agreed), Gunsan (84.4%), Yeongdeok(79.3%), Pohang(67.5%)• Construction started in 2008
• “Nuclear Safety and Security Commission” issued approval of use on 11 Dec.
2014
• Community Benefit

Still unsolved problems with SNF• Nov. 2011 ~ Aug. 2012: forum for SNF was formed.
• September, 2012: a law passed for establishing Public
Engagement Commission on Spent Nuclear Fuel Management,
PECOS

PECOS for Spent Nuclear Fuels
Public Engagement Commission on Spent Nuclear Fuel Management,
PECOS (2013~2015)• The public engagement started with the launch of PECOS in 2013
• PECOS consists of 15 members, from human & social science and technicalengineering, representatives recommended by NGO and residents in NPP
areas.
• The commission plays a role of deciding principles and methods of the
public engagement program, and submitting recommendation (national
plan on SNF) to government.
• The commission submitted recommendation to the government on June2015.

Recommendation by PECOS
Recommended the government to seek a repository site for SNF:
• Timeline for constructing:an intermediate storage (for 7 years)
an underground Research Lab (for 14 years)
a permanent repository (for 10 years)• Capacity: 707,476 bundles
LWR 42,839 bundles, HWR 664,637 bundles• Establish a “Center for Environment Monitoring” in the region“Government Basic Plan” for SNF• Based on the PECOS recommendation,
July 2015 ~ April 2016,a Task Force Team (in the government)
for “Basic Plan for SNF” was worked out.

II. Status of GEN IV in Korea

Status of GEN IV (Pyro-SFR) in Korea•

On Dec. 2008, (Nuclear energy Long Range Plan)
Pyro + SFR (Gen IV)~ 2025, Pyro for 30 tons
~ 2028, SFR for 300 ㎿e•

On Nov. 2011, Revision of the original plan
SFR (300㎿e → 100㎿e),•

On Jan. 2015,
Necessity of a site for SFR (to be built by 2028)•

On June, 2015, Revision of the Korea-US Agreement
Use of SNF for a research purpose•

By 2020, Korea-US collaboration research and agreement for
feasibility of pyroprocessing (in terms of economy, non-profileration)

from presentation by Dr. H. K. Joo, KAERI, 2014

from presentation by Dr. H. K. Joo, KAERI, 2014

III. ADS Research in SKKU

 Faculty of DOES

Topics of ADS R&D in SKKU

1. Computational modeling: TNudy
2. Transmutation of LLFP’s: 99Tc, 129I, ..
3. Accelerator Driven Molten Salt Reactor
4. Neutron Cross Section Measurement
5. Development of Cyclotrons for ADS

1. TNudy(ROOT Nuclear Data Library)••A C++ library, powered by ROOT, to read, process andvisualize ENDF nuclear data
ENDF= Evaluated Nuclear Data Format– Nuclear reaction data for E ≤ 20 MeV, including cross sections
and neutron yields– Written in ASCII, and can be read most conveniently by
FORTRAN (i.e., fixed length records and so on)

An example of ENDF file… …
4.009300+4 9.210840+100004034 3 170-1.537640+7-1.537640+700174034 3 171724034 3 17
21.554330+7 0.000000+0 1.575580+7 8.802450-5 1.600000+7 2.610420-34034 3 17
31.700000+7 9.111520-2 1.800000+7 2.766320-1 1.900000+7 4.673160-14034 3 1742.000000+7 6.148280-1
4034 3 1750.000000+0 0.000000+000004034 3 099999
4.009300+4 9.210840+100004034 3 220
… …

2. Transmutation of LLFPs

Experiment with a cyclotron in CAL, France• Started a TARC experiment through an international collaboration• Initial verification of the simulation for neutron flux with samples• Preliminary Results: Gamma rays from Indium sample & its activity
115In (n,γ) 116mIn

3. Acc. Driven Molten Salt Reactor
Implementation of an LBE spallation target
in an accelerator-driven molten salt subcritical reactor

4. Neutron Cross Section Measurement at
KIRAMS• Estimated cross section of 209Bi (n, 4n) 206Bi• Estimated cross section for 89Y (n, 2n) 88Y

5. Accelerator Group in SKKU(Prof. Jong Seo Chai)

9 MeV, 100uA

13 MeV, 100uA

Layout of the Cyclotron System for ADS

4 Injector cyclotrons~ 9 MeV, 3 mA

4 Intermediate SSC~ 70 MeV, 3 mA

2 Main SSC~ 700 MeV, 6 mA

~ 700 MeV, 12 mA (~8MW)

III. TORIA(Thorium Optimized Radionuclide Incineration Arena)

Pyroprocess‐SFR System•

Anticipated amount of SNF is about 1000 ton per year at 2025 in
Korea– It contains 1% of TRU, which is about 10 ton•

Pyroprocess separates TRU from SNF– Separated TRU goes to SFR– Residual waste contains about 10kg of TRU

SNF
1000 ton

1% of TRU (10 ton)

Pyroprocess

TRU
9990 kg

Residual
Waste

SFR

10kg of TRU

The First topical Meeting on Asian Network for Accelerator‐driven Systems and Nuclear Transmutation Technology

32

Pyroprocess‐SFR‐TORIA System
Residual waste containing TRU is mixed with thorium and used for fuel of
TORIA. This system leaves behind only low and intermediate level waste
SNF
1000 ton

Pyroprocess

1% of TRU (10 ton)

TRU
9990 kg

SFR

Residual
Waste

TRU
10 kg
TORIA

10kg of TRU

Low and
Intermediate
Level Waste

Thorium

Fuel of subcritical reactor
33

The First topical Meeting on Asian Network for Accelerator‐driven Systems and Nuclear Transmutation Technology

Concepts of TORIA•TORIA: Thorium Optimized Radionuclide
Incineration Arena
Cyclotron•

Proton beam

Purpose– TORIA is designed for the purpose ofmanaging spent nuclear fuel by burning
TRU and long-lived fission product•Subcritical
reactorCharacteristics
1.
2.
3.
4.

Accelerator-driven subcritical system
Dedicated burner
Thorium based oxide fuel
LBE as coolant and target material

Conceptual diagram of TORIAThe First topical Meeting on Asian Network for Accelerator‐driven Systems and Nuclear Transmutaion Technology

34

Design of Critical TORIA 1
Parameter

Value

Thermal power

30MWthPower plant efficiency

35%

Refueling interval

800 days

Primary coolant

Lead-bismuth eutectic

Fuel type(Th-TRU)O2

Cladding, structure material

HT9

Pellet nominal density (%TD)

100.0

Active core height/equivalentdiameter (H/Deq)<1

Number of pins
per one assembly

64 including
4 skeletal bar

Average effective
multiplication factor

1.01104

Average core power density

28.856W/cc

Average linear power density

4.252kW/m

35

Design of Critical TORIA 2- Design of marine TORIA is based on the URANUS design- Thermal power is 50MWth- Equivalent core diameter is 1.9m and height of active core is 1.8m
Parameters

Value

Power

50 (MWth)Number of pins per one assembly

61 including 1 skeletalbar

Pin pitch-to-diameter ratio

1.35

Fuel pin pitch

21.33 (mm)

Fuel pin diameter

14.4 (mm)Cladding thickness

0.06cmActive core height1800 (mm)Equivalent core diameter

1900 (mm)Fission gas plenum height

1300 (mm)Lower plenum height

300 (mm)

Fuel

40.82%

Coolant

50.03%

Structure

9.14%

Volumefraction

36

Design Criteria of Subcritical TORIA
Accelerator
The protons are injected onto a spallation target to produce source neutrons
for driving the subcritical core, and proton is generated by accelerator
Beam power needed to drive a 0.8‐GW ADS subcritical core(assumes a 50‐cm‐diameter LBE spallation target) †Beam
Energy500 MeV

600 MeV26.5 MW

23 MW

Rx Power

800 MWth
26.5
23

3MW

MYRRHA(600MeV,

100 MWth

TORIA
30 MWth5mA)
1 MW

0.86 MW(500 MeV,(600 MeV,

2 mA)

1.43 mA)

37

The First topical Meeting on Asian Network for Accelerator‐driven Systems and Nuclear Transmutaion Technology†H. Aït Abderrahim, et. al., “Accelerator and Target Technology for Accelerator Driven Transmutation and Energy Production” ADS white paper 2010

Design Criteria of TORIA
Preliminary core design
Main parameters of preliminary core
Thermal power

30MWthPower plant efficiency

35%

Refueling interval

1000 days

Primary coolant

Lead‐bismuth eutectic

Fuel type(Th‐TRU)O2

Cladding, structure material

HT9

Pellet nominal density (%TD)

100.0

Active core height/equivalentdiameter (H/Deq)<1

Number of pins per one assembly

64 including 4 skeletal bar

Average effective
multiplication factor

0.955

Average core power density

28.856W/cc

Average linear power density

4.252kW/m

Average discharge burnup

14.127MWd/kgHM

The First topical Meeting on Asian Network for Accelerator‐driven Systems and Nuclear Transmutaion Technology

Deq=137.51cm

38In 2015, Korea signed the GIF-LFR MoU to become a full
member of the GIF-LFR provisional System Steering Committee

39

Summary• Korea signed the GIF-LFR MoU to become a full
member of the GIF-LFR provisional System Steering
Committee• SNU and SKKU are doing fundamental but original
researches for transmutation and ADS.
• Close international collaboration with China, Japan andEurope is needed.

Current Status of Subcritical Reactor
Technology for ADS in China

Presented by: Yunqing Bai

Contributed by FDS TeamKey Laboratory of Neutronics and Radiation Safety
Institute of Nuclear Energy Safety Technology (INEST)
Chinese Academy of Sciences

www.fds.org.cn
14th International Workshop of ADS-NTT 2016, Mito, 5 Sept.

Contents
I. Strategy and plan
II. Design and R&D Progress

III. Summary

China’s Plan on Nuclear Energy( Plan up to 2020 ) Nuclear power plant in China˄
˄by August, 2015˅ 25 reactors (~ 23.6GWe) in operation
 26 reactors ( ~28.7GWe) under construction National plan of developing nuclear energy before 2020
 58 GWe in operation
 30 GWe under construction National plan for nuclear and radiation safety before 2020
 More R&D are required to enhance nuclear safety, especially in the basic
research of nuclear safety ~79.8 billion RMB investment plan (~13.3 billion US dollars)

Key Issues of Nuclear Energy Development

1. Limitation of Fuel Resourcesᷛ~60 year available resources for utilization
2. Nuclear accidentᷛTMI, Chernobyl, Fukushima
3. Disposition of Nuclear Wasteᷛlong term radioactive toxicity

Advanced and innovative nuclear energy system should be a viable
way to solve nuclear energy problems.

Latest Roadmap of Generation IV Reactors—— GIF organization evaluated in 2014

LFR is expected to be the first Generation-IV nuclear system toachieve industry demonstration and commercial application.

China Lead-based Reactor Development Plan
 Chinese Academy of Sciences (CAS) launched the ADS Project, and plan to constructdemonstration ADS transmutation system ~ 2030s through three stages.

 China LEAd-based Reactor (CLEAR) is selected as the reference reactor for ADS project
and for Lead cooled Fast Reactor (LFR) technology development.

ADS Demonstration Facility
Accelerator˖0.6-1GeV/~10mA
Reactor˖China Lead-based Engineering
Demonstration Reactor CLEAR-II (~100MW)ADS Research Facility
Accelerator˖
˖~250MeV
Reactor˖China Lead-based
Research Reactor CLEAR-I(~10MW)ADS Commercial Prototype Facility
Accelerator˖1.5-2GeV/~10mA
Reactor˖China Lead-based Commercial
Prototype Reactor CLEAR-III (~1000MW)

RFQ
Accelerate element
High current ion source
Superconducting cavity

CLEAR-I Implementation Plan
Subcritical
Test
CLEAR-I (Phase A)
Subcritical operation
for ADS integration
technology test

CLEAR-S

Critical
Test
CLEAR-I (Phase B)
Critical operation
for fast reactor
technology test

CLEAR-0

CLEAR-V

Components and Integrated Test Facilities

Contents
I. Strategy and plan
II. Design and R&D Progress
1. Reactor Design
2. Key Technology R&D
3. Safety Assessment

III. Summary

Current Status of CLEAR-I Project Reactor Design 2011-2014˖
˖Conceptual Design 2015-2016˖Preliminary Engineering Design Technical R&D
 2011-2013˖PbBi Loop Construction and Components Fabrication

 2014-2016˖Thermal-hydraulic, material, safety and Integrated Test Platform Test Safety Analysis
 2011-2014˖Software V&V, Accident and Environmental Impact Analysis
 2015-2016: Integrated Simulation of System and Environmental Impact

Key Technologies and Integrated Test Facilities
4 Kinds of Key Technologies

3 Test Reactors
in INEST/FDS

I. Coolant materials technology
II. Struct. Materials & Nucl. FuelIII. Key Components Development
IV. Instrumentation and Control/HDGDOOR\&RROHG
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&/($56

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CLEAR-I System Design Status¾ The detailed conceptual design has been done (more than 20 Systems)¾ Preliminary engineering design is underway
1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
12.
13.
14.

Nuclear Design
Thermo-hydraulic Design
Coolant System
Reactor Structure
Reactivity Control System
Refueling System
LBE Process System
Fuel Assembly
Safety System
I&C System
Application System
Radiation Protection System
Auxiliary System…

Design Objective and Principle
 Design Objectives
 ADS and Lead cooled Fast Reactor technology validation platform• Neutronics; Thermal hydraulics; Safety characteristics• Key components R&D and measurement control technology
 Fundamental science and neutron irradiation research platform• Fuel and material irradiation• Isotope production and nuclear technology training Design Principles
 Feasible technology• Mature material and fuel; Low power; Pool type vessel Reliable safety• Natural circulation; Passive decay heat removal system
 Capability of flexible experiment• Dual mode operation; Remote handling refueling system Technical continuity• MOX fuel, Minor actinides transmutation fuel…

Main Design Parameters
Parameter

ValuesThermal power (MW)10

Activity height (m)Activity diameter (m)Fuel (enrichment)

0.8
1.05
UO2(19.75%) at first

Cooling
SystemPrimary coolant
Inlet/Outlet temperature (ć)
Coolant drive typeHeat exchanger
Second coolant
Heat sink

LBE~300/385
Forced Circulation

Material

Cladding
Structure

Core

4
Water
Air cooler
15-15Ti/316Ti
316L

Key Technologies R&D

PbBi Coolant Loop KYLIN-II Experimental functionsz

Materials & Components test••z

Thermal-hydraulic behavior test
•
•
•

z

Corrosion of structural materials
Qualification of prototypicalcomponents
Natural/Forced/Mixed circulation
Fuel Bundle test
CFD and System Code validation

Reactor Typical/Severe Accident Test•

Heat exchanger tube rupture accident

 Main parameters
z
z
z
z
z

Temperature: 200oC~1100oC
Design Pressure: 25 MPa
Mass flow rate: 50m3/h
Total power: ~2000kW
Inventory of PbBi: ~20tons

Series PbBi loops were built to develop the
LBE technology and support the design andconstruction of CLEAR.

Materials, Components and I&C Technologies
 Coolant Materials

 Key Components

Oxygen measurement
and control

Lead bismuth eutectic

 Structural Materials and Fuel316l corrosion

Fuel assembly simulator

Mechanical pump

Double wall heatexchanger Instrumentation and Control

Fuel handling system

Full scope reactor
simulator

Lead-based Non-nuclear Reactor CLEAR-S Objectives and Functions−−−

Reactor prototype components validation▪

Pump, HX, DHR…;▪

Refueling machine, Control rod system.

Pool thermal-hydraulic integral test▪

Integral circulation test in pool type facility;▪

Code V&V (NTC, RELAP, CFD, etc.).

Large scale SGTR (interaction of HLM with water)

 Main Parameters−

Dimensions: 1:1 height, 1:2.5 diameter to CLEAR-I−

Temperature: 250oC~550oC−

Thermal power: 2.5MW (7 full scale fuel bundles)−

Mass flow rate: ~100m3/hComponents fabrication completed, the construction is underway.

Lead-based Zero Power Reactor (CLEAR-0)‒ Validation of the nuclear analysis method, code and database‒ Validation of the nuclear design and control technology‒ Provide experimental data to support the licensing of CLEAR-I
CLEAR-0
7\SH

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Zero Power Reactor (CLEAR-0)

Design of CLEAR-0 is completed, the construction is underway.

Lead-based Zero-Power Facility
Fusion neutron generator Driven Subcritical reactor/blanket (FDS-0)+,1(*3XOVH%HDP

Accelerator-based
Neutron Source
˄HINEG˅)LVVLRQ)XHO

6WHDG\%HDP

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&/($5

Zero Power Facility
˄CLEAR-0˅

High Intensity Fusion NEutron Generator HINEG( Phase-I, ~1012-1013n/s )Steady Beamline

Parameter

Steady beam

Pulsed beam

Yield

~1012-1013n/s>1010n/s

Beam size

10-20mm

<10mm

FWHM

—

<1.5nsPulsed Beamline

HINEG-I

HINEG-I Rotating Tritium Target

Low Energy Beam Transport Section

Experimental Hall

The installation of HINEG-I has been finished and successfully produced a
D-T fusion neutron yield of up to 1012 n/s.

Software Development
and Integrated Simulation

Softwares Developed at INEST/9OS[RGZOUTUL,[TJGSKTZGR6N_YOIGR6XUHRKSY
• SuperMC
• NTC
• MTC
• TAS
• RiskA• HENDL• RiskBase

Super Monte Carlo Simulation Program for Nuclear and Radiation Process
Neutronics-Thermohydraulics Coupled Simulation Program
Magnetic-Thermohydraulics Coupled Simulation Program
Tritium Analysis Program for Fusion System
Reliability and Probabilistic Safety Assessment ProgramHybrid Evaluated Nuclear Data Library
Database Management System for Reliability Analysis

II. Interactive Design and Optimization• RVIS• MCAM• RiskAngel• ARTS• SYSCODE• FusionDB

Virtual Reality-Based Simulation System for Nuclear and Radiation Safety
Multi-Physics Coupling Analysis Modeling Program
Risk Monitor for Nuclear Power Plant
Accurate/Advanced Radiotherapy System
System Analysis Program for Parameter Optimization & Economical Assessment of Fusion Reactor
Database Management System for Fusion

III. Multi-process Integrated Comprehensive Simulation• Virtual4DS• ITER-V• CLEAR-V• VisualBUS• CROSS• NCoud• NBigData

Virtual Nuclear Power Plant in Digital Society
Lead-based Virtual Reactor
Virtual Integrated Simulation Platform for ITER
CAD-Based Multi-Functional 4D Neutronics Simulation System
Informationization Platform for Collaborative Research and Management
Nuclear Cloud Platform
Nuclear Big Data Platform

Independent intellectual property rights¾ >800 person-years ,Certificated by international Benchmarking, Applied in 80+ nations

SuperMC: Super Monte Carlo Calculation Program for
Nuclear and Radiation Process

Support of complex problems & Validated by thousands of benchmarking

Application of Virtual4DS for CLEAR

Lead-based Virtual Reactor (CLEAR-V) Reactor System Design and Optimization• Nuclear, Thermal-hydraulic, structure, system design
and parameter optimization

 Multi-physics Integrated Simulation• Monitor the performance of any part of the reactor atany point in full cycle

 System Analysis and Assessment• Safety and accident analysis, environmental impact
assessment

 Virtual Reality based Lifelike Simulation• Virtual

tour,

assembly&

designvalidation,

Maintenance optimization & training

Contents
I. Strategy and plan
II. Design and R&D Progress

III. Summary

Overview of China Lead-Based Reactor Development
Selection & Implementation

Initial R&D

ADS
CLEAR-II
ADSADS
CLEAR-III

CLEAR-I
dual mode
sub-/critical

Final Goals/HDGEDVHG)XVLRQ5HDFWRU
ITER
FDS-MFXDEMO•Electricity•Transmutation

Critical Application*HQ,9/)5

,QQRYDWLYH
&RQFHSWH2 production
Thorium-basedHigh Temperature……

•Fuel Breeding•Others
˄H2 productionǃ…˅

Supporting R&D and Integrated Test

Summary
1.

Lead-based reactor has many attractive features and may play animportant role in the future energy supply, including a bridge role in
the transition period from fission energy to fusion energy.

2.

China has launched the ADS engineering construction project in2011. The engineering design and related R&D activities for China
lead-based reactors CLEAR are going on in order to finish theconstruction of the first engineering test system around 2020s.

3.

Study on application concepts showed good prospects of leadbased reactor.

4.

Chinese government is encouraging wider and deeper international
collaboration on S&T research projects, including lead-based reactor
program.

Institute of Nuclear Energy Safety Technology,
Chinese Academy of Sciences ( INEST, CAS ) Jointly sponsored by: Hefei Institutes of Physical Science, CAS (CASHIPS) University of Science and Technology of China (USTC) Key programs:
 Advanced Fission Reactor Design and R&D ᷉ADS - CLEAR᷊ Fusion/Hybrid Reactor Design and R&D ᷉ITER/FDS᷊ Nuclear Safety Innovation Project for Scientific andTechnological Development~400 members

 10 Divisionsˈ 400~500 Staff + 200~300 Students

Major Research Areas˖˖
1. Nuclear reactor safety᷉reactor design, nuclear detect & experiments, safety analysis methodology, …᷊
2. Radiation safety and environmental impact
᷉radiation protection & shielding, chemistry safety of nuclear energy, …᷊
3. Nuclear emergency and public safety᷉nuclear safety culture, nuclear accident emergency, nuclear power economics, …᷊
The major professional/fundamental research basis for nuclear energy safety
technology in China to promote the efficient and safe application of nuclear energy.

Website: www.fds.org.cn
E-mail: contact@fds.org.cn

Current Status on Accelerator
Accelerator‐‐Driven System(ADS) Experiments at
Kyoto University Critical Assembly (KUCA)
Cheolho Pyeon
Research Reactor Institut
Institute,e, Kyoto University, Japanpyeon@rri.kyoto‐‐u.ac.jp
pyeon@rri.kyoto

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 1

Contents
 Background and Purpose Composition of ADS in Kyoto Univ.
‐ Kyoto University Critical Assembly (KUCA)‐ Fixed‐Field Alternating Gradient (FFAG) accelerator 235U‐loaded ADS experiments with 100 MeV protons
 Neutron characteristics on solid targets (W, W‐Be and Pb‐Bi)‐ Static analyses: Reaction rate (k‐source)‐ Kinetic analyses: Subcriticality  ($)
Prompt neutron decay constant  (1/s)
 Summary

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 2

Background and Purpose
Background An original concept of ADS for producing energy and transmuting MA and LLFP Neutron characteristics on solid targets (W, W‐Be and Pb‐Bi) in ADS
 Influences of solid target on 235U‐loaded ADS experiments with 100 MeV protons‐ Neutron yield (Number of neutrons / one proton)‐ Reaction rate distribution (k‐source)‐ Subcriticality and prompt neutron decay constantPurpose Investigate neutron characteristics of solid targets throughstatic and kinetic analyses of experiments and calculations (MCNP)ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 3

ADS with 100 MeV protons at KUCA

100 MeV protons + W target = S
pallation neutronsFig. Beam line of protons
targetFig. KUCA core
 KUCA core
‐ A solid‐moderated and –reflected core
Fuel: HEU, Th, NU
Moderator: Poly., Gr, Be
Reflector: Al, Fe, Pb, Pb‐Bi FFAG accelerator‐ 100 MeV energy‐ 1 nA intensity‐ 20 Hz repetition, 100 ns width
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

Fig. Beam line of FFAG accelerator
C. H. Pyeon, Kyoto Univ. 4

235U‐ADS core configuration
26

25

24

23

22

21

20

19

18

17

16

15

14

13

12

11

10

9

8

7

6

5

4

Z
Y

F

X

Fuel (1/8"P60EUEU)

FC#2

UIC#5

W

Polyethylene reflector

V
UC

Control rod

S

Safety rod

N

Neutron source (Am-Be)

FC

Fission chamber

UIC

UIC detector

TR

In wire position
FC#1

FC#3
S6

Q

F

F

F

F

F

P

F

F

F

F

F

O

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

M

N

C1

L

C2

S4

UIC#5
S5

K

C3

J
I

BF3 #1 detector (1/2" diameter)

HCore target
locationG

BF3 #2 detector (1" diameter)

E
UIC#6

Air region

D

Optional fiber detector (LiF+ZnS)

B
A
A'
Original target
location

Source: C. H. Pyeon, et al., Nucl. Technol., 192, 181 (2015).

Proton beams

Fig. Top view of core configuration of 235U‐ADS with 100 MeV protons
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 5

235U‐ADS in KUCA: Experimental analyses
Experiment Neutron yield‐ Protons: 27Al(p, n+3p)24Na‐ Spallation Neutrons: 115In(n, n’)115mIn
 Reaction rates (M and k‐source)‐ Profiles: 115In(n, )116mIn

Calculation
 MCNP6
 Nuclear data libraries‐ JENDL/HE‐2007: Protons and spallation
neutrons‐ JENDL‐4.0: Transport‐ JENDL/D‐99: Reaction rates

 Subcriticality‐ PNS and Noise methods

Definition of parameters Neutron yield = Spallation neutrons / Protons‐ Spallation neutrons: 115In(n, n’)115mIn‐ Protons: 27Al(p, n+3p)24Na
 (Normalized) Reaction rates = Profiles / Spallation neutrons‐ Profiles: 115In(n, )116mIn (thermal) or 115In(n, n’)115mIn (fast)‐ Spallation neutrons: 115In(n, n’)115mIn

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 6

Static: Neutron yield
Table Dimension of target
In wire position
S6

C1

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

S5

TargetDiameter [mm]Thickness [mm]

W

50.0

12.0

S4

W‐Be

50.0

W: 12.0
Be: 10.0

C3

Pb‐Bi

50.0

18.0

C2

Table Comparison between measured and calculated
neutron yield

Core target
locationTargetCalculation

Experiment

C/E valueW

0.57 ± 0.01

0.21 ± 0.01

2.66 ± 0.01

W‐Be

0.32 ± 0.01

0.15 ± 0.01

2.13 ± 0.04

Pb‐Bi

0.38 ± 0.01

0.17 ± 0.01

2.27 ± 0.04

Void region

Original target
locationProton beams

Source: C. H. Pyeon, et al., Nucl. Technol., 192, 181 (2015).

Fig. Core configuration of 235U‐PE core(100 MeV protons)
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 7

 Very unique peak ranging between 85 and100 MeV neutrons(for 100 MeV proton injection)

10-6
W
10-7

Pb-Bi

W-Be

‐> How about influences on neutron
characteristics in the core?

10-8
W target
W-Be target
10-9

Pb-Bi target

10-10
10-2

10-1

100

101

Neutron energy [MeV]Fig. Neutron spectrum of injection of 100 MeV protons
into heavy metal target

 Spectrum of spallation neutrons(100 MeV proton injection)‐ W, W‐Be and Pb‐Bi targets‐ Almost same102

Neutron flux per lethargy bin [1/cm2/source]

Neutron flux per energy bin [1/cm2/eV/source]

235U‐ADS: Source spectrum of target

10-6
W (9 mm)
W (9 mm) - Be (6 mm)

10-7

W (9 mm) - Be (6 mm)
10-8

10-9
W (9 mm)
10-10
0

20

40

60

80

100

Neutron energy [MeV]Fig. Comparison between neutron spectra of W and
W‐Be targets
Source: C. H. Pyeon, et al., Nucl. Technol., 192, 181 (2015).

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 8

Normalized reaction rates [Arbitrary units]

Static: Neutron multiplication
In wire position
S6

C1

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

C2

S4

S5

C3

40.0

Polyethylene
regionAir region

30.0Core region

W target
W-Be target
Pb-Bi target

20.0

10.0

0

0

10

20

30

40

50

60

70

Distance from location of original target [cm]Fig. Measured reaction rate distribution (M and k‐source study)
Core target
location

Table Comparison between measured and calculated M values(Subcriticality: 2,657 pcm)

Void region

Original target
locationTargetCalculation

Experiment

C/E valueW

1.73 ± 0.01

1.85 ± 0.02

0.93 ± 0.01

W‐Be

2.29 ± 0.01

2.36 ± 0.03

0.97 ± 0.01

Pb‐Bi

1.95 ± 0.01

1.94 ± 0.02

1.01 ± 0.01

Proton beams

Fig. Core configuration of 235U‐PE core(100 MeV protons)

Source: C. H. Pyeon, et al., Nucl. Technol., 192, 181 (2015).

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 9

Kinetic: Subcriticality (pcm)105

In wire region

C1

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

S5

M CNPX = 4902 pcm (BF3 #1)

104

C2

F

Countin rate [1/s]S6S4

W target
W-Be target
103

Pb-Bi target

102
C3

101

0

0.01

0.02

0.03

0.04

0.05

Time evolution [s]

C

t

t

Fig. Core configuration of 235U‐PE coreFig. Measured neutron behavior on time evolution( and eff study)

Table Measured subcriticality (dollar units) by the PNS (area ratio method) method (Ref.: 4,902 pcm)

TargetBF3 #1 in (10, U)

BF3 #2 in (15, X)

Optical fiberW

4944 ± 78

6386 ± 101

6228 ± 99

W‐Be5004 ± 83

7050 ± 114

4929 ± 77

Pb‐Bi4903 ± 77

6356 ± 924912 ± 74

Source: C. H. Pyeon, et al., Nucl. Technol., 192, 181 (2015).
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 10

Benchmarks on Solid Pb‐Bi target

Table Target study on W, W‐Be and Pb‐Bi
keff

Reaction rate
(In wire) fork‐source

PNS method

Noise method

0.987

Available

Available

Available

0.980

Available

Available

Available

0.973

Available

Available

Available

0.950

Available

Available

Available

Subcriticality

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 11

235U & Pb
Pb‐‐BiBi‐‐zoned core with Pb
Pb‐‐Bi target

C1

S5

F

F

F

F

F

F

F

F

F

F

F

F'

F'

F'

F

F

F'

F'

F'

F

F

F'

F'

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

F

16

16

C2

S4

Fig. Fuel assembly of 235U‐PE and Pb‐Bi
C3

Proton beams

Normalized neutron flux per lethargy (arbitraryb unit)

S6

0.08

1/8"Pb-Bi60EU-EU
1/8"P60EU-EU

0.07
0.06
0.05
0.04
0.03
0.02
0.01
0.00
-8
10

10

-7

10

-6

10

-5

10

-4

10

-3

10

-2

10

-1

10

0

10

1

Energy (MeV)

Fig. Neutron spectrum of core center in F‘ at 100 MeV
proton injection onto Pb‐Bi target

Fig. Core configuration of 235U and Pb‐Bi zoned core
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 12

Subcriticality benchmarks

Table Subcriticality in 235U & Pb‐Bi‐zoned core with Pb‐Bi target
Subcriticality
keff
PNS method

Noise method

0.980

Available

Available

0.950

Available

Available

0.920

Available

Available

0.900

Available

Available

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 13

Reaction rates (Neutron spectrum) analyses
ADS experiments with 100 MeV protons
 235U & Pb‐Bi‐zoned core with Pb‐Bi target‐ Indium reaction rate distribution: Analyses of k‐source by 115In(n, )116mIn‐ Spectrum index: 115In(n, )116mIn / 115In (n, n’) 115mIn‐ Neutron spectrum: Activation foils; Al, Fe, In, Au and Ni (MeV threshold)‐ Subcriticality ranging between 0.98 and 0.90
Table Reaction rates in 235U & Pb‐Bi‐zoned core with Pb‐Bi target

keff

Reaction rate
(In wire) for
M and k‐source

Activation foils forSpectrum(Al, Fe, In, Au, Ni)

0.980

Available

Available

0.950

Available

Available

0.920

Available

Available

0.900

Available

Available

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 14

IAEA ADS Exp. Benchmarks in KUCA
 235U‐ADS with 14 MeV neutrons(KURRI‐TR‐444, 2014: IAEA ADS CRP 2007)
http://www.rri.kyoto‐u.ac.jp/PUB/report/03_tr/img/KURRI‐TR‐444.pdf
 232Th‐ADS with 14 MeV neutrons or 100 MeV protons (W target)(KURRI‐TR(CD)‐48, 2015: IAEA ADS CW 2013)
http://www.rri.kyoto‐u.ac.jp/PUB/report/04_cd/img/KURRI‐TR‐48.pdf
 235U & Pb‐Bi‐zoned‐ADS with 100 MeV protons & Pb‐Bi target(Being in IAEA ADS CRP 2016)
Contact me directly (sharing with JAEA of Japan, INEST; IMP of China and others)‐ Pb‐Bi target study‐ Pb‐Bi‐zoned core study‐ Global results of static and kinetic studies(subcriticality ranging between 0.98 and 0.90)

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 15

Summary Solid Pb‐Bi target study of ADS with 100 MeV protons‐ Reaction rate distribution: 115In(n, )116mIn‐ Kinetic parameters by the PNS and the Noise methods‐ Subcriticality ranging between 0.99 and 0.95
 Neutronics on 235U and Pb‐Bi‐zoned core
‐ Kinetic parameters by the PNS and the Noise methods‐ Subcriticality ranging between 0.98 and 0.90
 Reaction rate analyses‐ Reaction rate distributions: 115In(n, )116mIn (thermal)
115In (n, n’)115mIn (fast)‐ Activation foils: Al, Fe, In, Au and Ni (MeV threshold) Future works (ADS with 100 MeV protons; Pb‐Bi target)‐ Neutronics (Global results) on 235U and Pb zoned (Fast‐like spectrum) core
‐ 237Np (capture and fission) and 241Am (fission) irradiation

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 16

Round discussion on ADS‐
ADS‐NTT2016

Cheolho Pyeon
Research Reactor Institut
Institute,e, Kyoto University, Japanpyeon@rri.kyoto‐‐u.ac.jp
pyeon@rri.kyoto

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 1

Discussion issues
 Dr. Sasa of JAEA, Japan‐ Nuclear energy situation in Japan‐ Future ADS design: TEF R&D and current status‐ MA and Pb‐Bi related technologies
 Prof. Hong of SSKU, Korea‐ Status on spent fuel management in Korea‐ Status on GEN‐IV (Pyro‐SFR) in Korea‐ ADS research in SSKU
 Dr. Bai of INEST, China‐ Strategy and plan of ADS (until 2020)‐ CLEAR‐0, I, II and III‐ Software development for actual experimental facilities
 Prof. Pyeon of KU, Japan‐ Characteristics on Pb‐Bi target and Pb‐Bi‐zoned core
‐ IAEA ADS benchmarks of KUCA
‐ Future ADS experiment plan
Open the proceedings of ADS‐NTT 2016, “KURRI‐KR(CD) in 2016,” on KURRI web site soon!
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 2

IAEA ADS Exp. Benchmarks in KUCA
 235U‐ADS with 14 MeV neutrons(KURRI‐TR‐444, 2014: IAEA ADS CRP 2007)
http://www.rri.kyoto‐u.ac.jp/PUB/report/03_tr/img/KURRI‐TR‐444.pdf
 232Th‐ADS with 14 MeV neutrons or 100 MeV protons (W target)(KURRI‐TR(CD)‐48, 2015: IAEA ADS CW 2013)
http://www.rri.kyoto‐u.ac.jp/PUB/report/04_cd/img/KURRI‐TR‐48.pdf
 235U & Pb‐Bi‐zoned‐ADS with 100 MeV protons & Pb‐Bi target(Being in IAEA ADS CRP 2016)
Contact me directly (sharing with JAEA of Japan, INEST; IMP of China and others)‐ Pb‐Bi target study‐ Pb‐Bi‐zoned core study‐ Global results of static and kinetic studies(subcriticality ranging between 0.98 and 0.90)
10 Participant countries (13 institutions) in IAEA ADS CRP 2016:
Argentina, Belarus, China (INEST and IMP), Germany (KIT), Hungary, India (BARC),
Italy (Polito Torino and ENEA), Korea (SNU), US (ANL) and Japan (JAEA and Kyoto Univ.)
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 3

M&C 2017 in Jeju
Jeju,, Korea on 16
16‐‐20, Apr. 2017
 Subcriticality system analysis methods (Track 4)
 4‐1 Subcriticality Measurement and Online Monitoring Techniques 4‐2 Spent Fuel Cask/Storage Analyses 4‐3 Deterministic and Monte Carlo Analysis of ADS
 4‐4 Energy and Spatial Correction Factors for Subcriticality Measurements
 4‐5 Uncertainty of the Methodologies for Subcriticality Determination
 4‐6 Integral Parameters and their Experimental Determination
 4‐7 Others
 Special session (Chair: Prof. T. Endo, Nagoya Univ., Japan)
Title: ADS Benchmarks at KUCA
 Energy and spatial correction factors for kinetic parameters Deterministic and stochastic analysis methods On‐line monitoring techniques of subcriticality
 Uncertainty of methodology for subcriticality
 Higher‐harmonics analyses for kinetic parameters Development of reactor analysis codes
Please access to, http://mc2017.org/
ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 4

Next meeting (Topical meeting) in 2017
 New meeting schedule fixed since 2015:‐ General meeting by rotation (Japan, Korea and China) in every two years (even)‐ Topical meeting (any country) in every two years (odd)
5th Rotation schedule 13th, 2015 (Japan): Topical meeting at JAEA (Pb‐Bi techniques) 14th, 2016 (Japan): General meeting 15th, 2017 (???): Topical meeting: Topic and Venue ‐> Any suggestion?
 16th, 2018 (Korea): General meeting 17th, 2019 (???): Topical meeting 18th, 2020 (China): General meeting

ADS‐NTT2016, Mito, Japan, 5th Sep. 2016

C. H. Pyeon, Kyoto Univ. 5

KUR REPORT OF
KYOTO UNIVERSITY RESEARCH
REACTOR INSTITUTE
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