J. Bouchard

France

Key challenges and opportunities

FRP-01

M. Xu

China

Fast reactor development for a sustainable nuclear energy supply in China

FRP-02

J. Rouault
J.P. Serpantié
D. Verwaerde
(presented by:
F. Gauché)

France

French R&D program on SFR and the ASTRID prototype

FRP-03

S.C. Chetal
P. Chellapandi
P. Puthiyavinayagam
S. Raghupathy
V. Balasubramanian
P. Selvaraj
P. Mohanakrishnan
B. Raj

India

Perspective on development of future FBRs in India

FRP-04

K. Hakozaki

Japan

Research and development policy on FBR cycle technology in Japan

FRP-05

J.B. Choi

Korea, Republic of

Status of fast reactor and pyroprocess technology development in Korea

FRP-06

P.G. Schedrovitsky
V.I. Rachkov
O.M. Saraev
A.V. Zrodnikov
V.M. Poplavsky
B.A. Vasilyev
V.N. Ershov
A.V. Bychkov
I.A. Shkabura
V.N. Leonov

Russian Federation

The program of fast reactor development in Russia

FRP-07

P.J. Finck
R.N. Hill

United States of America

The US advanced fuel cycle program: objectives and accomplishments

FRP-08

R. Schenkel

EC

Fast reactor research in Europe: the way towards sustainability

FRP-09

A. Stanculescu
G. Dyck

IAEA

IAEA programme on fast reactor, related fuels, and structural materials technology

FRP-10

T. Dujardin
C. Nordborg
Y.J. Choi

OECD/NEA

OECD Nuclear Energy Agency activities related to fast reactor development

KN-01

J.L. Carbonnier

France

Advanced and innovative reactor concept designs, associated objectives and driving forces

KN-02

V.M. Poplavsky
F.A. Kozlov
Yu.I. Orlov
A.P. Sorokin
A.S. Korolkov
Yu.Ye. Shtynda

Russian Federation

Liquid metal coolants technology for fast reactors

KN-03

R. Nakai

Japan

Design and assessment approach on advanced SFR safety with emphasis on core disruptive accident issue

KN-04

B. Raj
T. Asayama
C. Fazio

India

Structural materials: new challenges, manufacturing and performance

INV-01

T. Mizuno

Japan

Fast reactor fuel development in Japan

INV-02

V.M. Poplavsky
L.M. Zabudko
I.A. Shkaboura
M.V. Skupov
A.V. Bychkov
V.A. Kisly
F.N. Kryukov

Russian Federation

Fuels for advanced sodium cooled fast reactors in Russia: state­of-art and prospects

INV-03

K.O. Pasamehmetoglu

United States of America

Advanced fuels for fast reactors

INV-04

J. Somers
P. Anzieu
J.M. Bonnerot
E. D'Agata
F. Klaassen
R. Hania
(presented by:
D. Haas)

EC

Fast reactor fuel development in Europe

KN-05

S. Tanaka

Japan

Recycle strategies for fast reactors and related fuel cycle technologies

INV-05

J.F. Sauvage
G. Préle
L. Martin

France

The French SFR operating experience

INV-06

S.C. Chetal
P. Kumar
P. Chellapandi

India

The last twenty years experience with fast reactors; Lessons learnt and perspective

INV-07

K. Ito
T. Yanagisawa

Japan

Last twenty years experiences with fast reactors in Japan

INV-08

A.V. Zrodnikov
V.M. Poplavsky
Yu.M. Ashurko
O.M. Saraev
N.N. Oshkanov
M.V. Bakanov
B.A. Vasilyev
Yu.L. Kamanin
V.N. Ershov
M.N. Svyatkin
A.S. Korolkov
Yu.M. Krasheninnikov
V.V. Denisov

Russian Federation

Experience gained in Russia on sodium cooled fast reactors and prospects of their further development

KN-06

A. Siegel

United States of America

Advanced simulation: applications for fast reactors

T. Jo

Japan

Statement at YGE

M. Salvatores

France

Issues and challenges of fast reactors: imaginative breakthrough vs. business as usual

N. Camarcat

France

PDF

V. Kagramanyan

Russian Federation

PDF

C. Hu

China

PDF

P. Frigola

EC

PDF

S. Golub

USA

PDF

A. Chebeskov

Russian Federation

PDF

Y. Sagayama

Japan

PDF

A. Rineiski

Germany

PDF

YOUNG GENERATION EVENT (YGE):

Development and deployment of fast reactor technology to meet global nuclear energy sustainability requirements: A challenge for the young generation

YGE-02

T. Ito

Japan

Important matters in realizing commercial FBR cycle

L. Ren

China

PDF

Y. Liu

China

PDF

K.L. Lee

Korea, Republic of

PDF

W.J. Chang

Korea, Republic of

PDF

F. Gabrielli

Germany

PDF

E. Hourcade

EC

PDF

S. Poglyad

Russian Federation

W. D. Pointer

USA

PDF

S. Beils

France

PDF

T. Jo

Japan

PDF

01-01

N. Camarcat
J.M. Delbecq
J.F. Sauvage
D. Verwaerde
P. Berbey

France

Fast breeder reactor development: EDF's point of view

01-02

Y. Sagayama
K. Okada
T. Nagata

Japan

Progress on reactor system technology in the FaCT project toward the commercialization of fast reactor cycle system

01-03

Y. Kim
D.H. Hahn

Korea, Republic of

Advanced SFR concept design studies at KAERI

01-04

V.M. Poplavsky
A.M. Tsybulya
Yu.E. Bagdasarov
B.A. Vasilyev
Yu.L. Kamanin
S.L. Osipov
N.G. Kuzavkov
V.N. Yershov
M.R. Ashirmetov

Russian Federation

Advanced sodium fast reactor power unit concept

01-05

V.M. Poplavsky
A.M. Tsyboulya
Yu.S. Khomyakov
V.I. Matveev
V.A. Eliseev
A.G. Tsykunov
B.A. Vasiliev
S.B. Belov
M.R. Farakshin

Russian Federation

Core design and fuel cycle of advanced fast reactor with sodium coolant

01-06

D.H. Hahn
C.M. Kang
E.P. Loewen
E.F. Saito

Korea, Republic of

Advanced SFR concept based on PRISM and KALIMER

01-07

K. Aoto
S. Kotake
N. Uto
T. Ito
M. Toda

Japan

JSFR design study and R&D progress in the FaCT project

01-08

A. Alemberti
J. Carlsson
E. Malambu
A. Orden
L. Cinotti
D. Struwe
P. Agostini
S. Monti

Italy

ELSY - The European lead fast reactor

01-09

A.V. Zrodnikov
G.I. Toshinsky
O.G. Komlev
V.S. Stepanov
N.N. Klimov
A.V. Kudryavtseva
V.V. Petrochenko

Russian Federation

SVBR-100 module-type fast reactor of the IV Generation for regional power industry

01-10

J.C. Garnier
J.Y. Malo
F. Bertrand
P. Anzieu
(presented by:
N. Devictor)

France

Recent progress of gas fast reactor program

01-11

M. Konomura
M. Ichimiya
K. Mukai

Japan

Future R&D programs using Monju

01-12

B. Riou
D. Verwaerde
S. Aniel

France

Design features of advanced sodium cooled fast reactors with emphasis on economics

02-01

R. Ganesan
V. Jayaraman
S. Rajan Babu
R. Sridharan
T. Gnanasekaran

India

Behaviour and monitoring of non-metallic impurities in liquid sodium

02-02

C. Latgé

France

Sodium quality control; French developments from Rapsodie to EFR

02-03

S. Eckert
D. Buchenau
G. Gerbeth
F. Stefani
F.P. Weiss

Germany

Some recent developments in the field of liquid metal measuring techniques and instrumentation

02-04

C. Ito
Y. Araki
K. Okazaki
H. Naito
K. Watanabe
N. Takegawa
H. Harano
T. Iguchi
T. Aoyama

Japan

Development of high sensitive and reliable FFD and sodium leak detection technique for fast reactor using RIMS

02-05

F. Baqué
G. Rodriguez
N. Jardin
J.M. Carpeau
J.M. Augem
J. Sibilo

France

Challenges and R&D program for improving inspection of sodium cooled fast reactors and systems

02-06

K. Tsukimori
M. Ueda
S. Miyahara
T. Yamashita

Japan

R&D on Maintenance Technologies for FBR plants in JAEA ­ The status quo and the future plan

02-07

T. Ashida
K. Imaizumi
S. Maeda
M. Takamatsu
T. Sekine
A. Nagai
Y. Maeda

Japan

Restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor Joyo

03-01

S. Beils
B. Carluec
N. Devictor
G.L. Fiorini
J.F. Sauvage

France

Safety for the future sodium cooled fast reactors

03-02

R.A. Wigeland
J.E. Cahalan

United States of America

Mitigation of sodium-cooled fast reactor severe accident consequences using inherent safety principles

03-03

I. Slessarev
P. Alekseev

Russian Federation

Ways to the nuclear power renaissance and vital risk free fast reactors

03-05

G.L. Fiorini
T.J. Leahy
(presented by:
R. Nakai)

France

Generation IV International Forum Risk and Safety Working Group: Terms of reference, accomplishments, current activities & perspectives

03-06

N. Nakae
T. Baba
K. Kamimura

Japan

Basis of technical guideline for FBR fuel safety evaluation in JNES

03-07

K. Haga
H. Endo
T. Nakajima
T. Ishizu

Japan

Development of integrated analytical tools for level-2 PSA of LMFBR

03-08

E.E. Morris
W.M. Nutt
(presented by:
T. Taiwo)

United States of America

Uncertainty analysis for unprotected loss-of-heat-sink, loss­of­flow, and transient-overpower events in sodium-cooled fast reactors

03-09

V.M. Poplavsky
V.I. Matveev
V.A. Yeliseev
I.A. Kuznetsov
A.V. Volkov
M.Yu. Semenov
Yu.S. Khomyakov
A.M. Tsibulya
(presented by:
Yu.Ye. Shvetsov)

Russian Federation

Sodium void reactivity effect influence on the prospective fast neutron reactor safety and concept approaches

03-10

S. Kubo
Y. Shimakawa
H. Yamano
S. Kotake

Japan

Safety design requirements for safety systems and components of JSFR

04-01

J.T. Busby

United States of America

Advanced materials for nuclear reactor systems: alloys by design to overcome past limitations

04-02

G. Müller
A. Weisenburger
A. Heinzel
A. Jianu

Germany

Pulsed e-beam modified FeCrAlY corrosion barriers for future fast reactor systems

04-03

A. Povstyanko
V. Prokhorov
A. Fedoseyev
F. Krykov

Russian Federation

EP-450 Steel as cladding material for fuel rods for fast neutron reactors

04-04

S.H. Kim
C.B. Lee
D.H. Hahn

Korea, Republic of

Development of SFR fuel cladding tube materials

04-05

N. Isobe
N. Kawasaki
M. Ando
M. Sukekawa

Japan

Experimental investigation of strain concentration evaluation based on the stress redistribution locus method

04-06

K. Fukumoto
H. Matsui
N. Akasaka
I. Yamagata

Japan

Microstructural effect of solute addition for Fe-15Cr-20Ni steels irradiated in Joyo

04-07

K. Natesan
M. Li
S. Majumdar
R.K. Nanstad
T.L. Sham

United States of America

Materials and code qualification needs for sodium-cooled fast reactors

04-08

O. Ancelet
M.N. Berton
M. Blat
F. Dalle
P. Dubuisson
O. Gelineau
Y. Lejeail

France

Analysis of the optimization of the secondary hot piping for a sodium fast reactor

04-09

V.S. Ageev
Yu.P. Budanov
A.G. Ioltuhovskiy
M.V. Leontyeva-Smirnova
N.M. Mitrofanova
A.V. Tselishchev
I.A. Shkabura

Russian Federation

Structural materials for Russian fast reactor cores: Status and prospects

04-10

T. Asayama
Y. Nagae
T. Wakai
M. Inoue
T. Kaito
S. Otuka
N. Kawasaki
M. Morishita

Japan

Development of structural materials for JSFR - overview and current status

05-01

А.V. Bychkov
М.V. Kormilitsyn
P.P. Poluectov
V.S. Kagramanyan
Yu.S. Khomyakov
P.N. Alexeyev
А.Yu. Kuznetsov

Russian Federation

Strategies and national programs of closed fuel cycles: Russian vision

05-02

H. Funasaka
T. Koyama
T. Namekawa
T. Nagata

Japan

Development of FBR fuel cycle technology in Japan

05-03

C. Poinssot
D. Warin
C. Rostaing

France

Recent progress in advanced actinide recycling processes

05-05

W. Nakazato
K. Ikeda
R.A. Kochendarfer
S. Kunishima

Japan

Enhancing Minor Actinide Transmutation in ARR

05-06

T. Taiwo
S. Bays
A. Yacout
E. Hoffman
M. Todosow
T. Kim
M. Salvatores

United States of America

U.S. Study on impacts of heterogeneous recycle in fast reactors on overall fuel cycle

05-21P

T. Namekawa
Y. Yamada
A. Kitamura
T. Hosogane
K. Kawaguchi

Japan

Handling technology of low decontaminated TRU fuel for the simplified pelletizing method fuel fabrication system

05-08

F. Gabrielli
V. Romanello
M. Salvatores
A. Schwenk-Ferrero
W. Maschek

Germany

Advanced fuel cycles and fast reactor flexibility

05-09

A.M. Yacout
T.A. Taiwo
C.J. Jeong
U. Laüferts

United States of America

Multi-regional transitional strategies towards fast reactor based nuclear energy systems

05-10

A. Baschwitz
C. Loaëc
J. Fournier
M. Delpech

France

GEN-IV deployment: long term-prospective

05-11

B. Raj
A. Vasile
V. Kagramanian
M. Xu
R. Nakai
Y.I. Kim
V. Usanov

IAEA

Assessment of compatibility of a system with fast reactors with sustainability requirements and paths to its deployment

05-12

A.V. Zrodnikov
V.S. Kagramanyan
A.N. Chebeskov
E.V.  Poplavskaya

Russian Federation

International nuclear fuel cycle centers in global nuclear power infrastructure

05-13

P. Kumar
S. Narasimhan

India

Security and control of nuclear material in PFBR

05-14

J.F. Pilat

United States of America

Proliferation resistance for fast reactors and related fuel cycles: issues and impacts

05-15

D. Greneche

France

Proliferation issues related to the deployment of fast neutron reactors

05-16

Y. Kuno
M. Senzaki
M. Seya
N. Inoue

Japan

Role of safeguards in proliferation resistance for the future nuclear fuel cycle systems

06-01

K. Sugiyama
Z. Zhang

Japan

Thermal and hydrodynamic fragmentation of a single molten stainless steel droplet penetrating sodium pool

06-02

K. Litfin
A. Batta
A. G. Class
T. Wetzel
R. Stieglitz

Germany

Flow distribution and turbulent heat transfer in a hexagonal rod bundle experiment

06-03

Yu.M. Ashurko
G.P. Pugachev

Russian Federation

Phenomenon of local natural circulation in a circuit of nuclear power plant

06-04

R. Kato
H. Saito
H. Ota
K. Kimura

Japan

The R&D test plan using sodium test loop for development  of the 4S

06-05

G. Palmiotti
M. Salvatores
M. Assawaroongruengchot

France

Nuclear data for innovative fast Reactors: Impact of uncertainties and new requirements

06-06

J.M. Ruggieri
J.F. Lebrat
J. Tommasi
P.A Archier
(presented by:
F. Varaine)

France

JEFF-3.1.1 Nuclear data validation for sodium fast reactors

06-07

T. Takeda
W.F.G. van Rooijen

Japan

Sensitivity coefficients for fast reactor core analysis

06-08

K. Mikityuk

Switzerland

Review of the recent FAST project activities related to Gen-IV fast reactors

06-09

T.J. Tautges

United States of America

Coupled multi-physics simulation frameworks for reactor simulation: A bottom-up approach

06-10

V.M. Poplavsky
I.A. Kuznetsov
Yu.Ye. Shvetsov
A.V. Volkov
Yu.M. Ashurko
M.V. Kashcheev
L.A. Shchekotova
G.A. Kunzio

Russian Federation

Computational software package for analyzing the fast neutron reactor safety: Its improvement and development prospects

06-11

M.A. Smith
D. Kaushik
A. Wollaber
W.S. Yang
B. Smith

United States of America

Neutronics code development at Argonne National Laboratory

06-13

A. Rineiski
M. Ishikawa
J. Jang
P. Mohanakrishnan
T. Newton
G. Rimpault
A. Stanculescu
V. Stogov

Germany

Benchmark analyses for BN-600 MOX core with minor actinides

06-14

T. Nakajima
H. Endo
T. Yokoyama

Japan

Analysis of core physics test data and sodium void reactivity worth calculation for Monju core with ARCADIAN-FBR computer code system

06-31P

C. Lee
W.S. Yang

United States of America

Development of multigroup cross section generation code MC2-3 for fast reactor analysis

06-17

T.H. Fanning
T. Sofu
(presented by:
W.D. Pointer)

United States of America

Modeling of thermal stratification in sodium fast reactor outlet plenums during loss of flow transients

06-18

W.D. Pointer
J. Smith
A. Siegel
P. Fischer

United States of America

RANS Simulations of turbulent diffusion in wire-wrapped sodium fast reactor fuel assemblies

06-19

S.M. Woo
H.M. Park
S.H. Chang

Korea, Republic of

The multi-dimensional analysis method development for KALIMER-600 using MARS-LMR CODE

07-01

D. Haas
J.P. Glatz
R.J.M. Konings
V.V. Rondinella
J. Somers

EC

Fast neutron reactor fuel cycle research programme at the Joint Research Centre

07-02

F. Varaine
G. Rimpault
G. Mignot
L. Paret
A. Zaetta
J. Rouault

France

Comparative review on different fuels for Gen-IV sodium fast reactors: merits and drawbacks

07-03

O.N. Nikitin
F.N. Kryukov
S.V. Kuzmin
B.D. Rogozkin
Yu.A. Ivanov
L.M. Zabudko
I.S. Kurina
B. Syriac
J. Noirot

Russian Federation

Results of post-irradiation examinations of inert matrices fuels irradiated in BOR-60 reactor up to 19 at% of burnup in frame of Russian-French BORA-BORA experiment

07-04

J.P. Panakkal
H.S. Kamath

India

Fabrication and quality control of MOX fuel for prototype fast breeder reactor (PFBR)

07-05

A.V. Bychkov
A.A. Mayorshin
O.V. Skiba
V.A. Kisly
O.V. Shishalov
M.V. Kormilitsyn
Yu.M. Golovchenko

Russian Federation

Vibropac MOX - fuel for fast reactors - experience and prospects

07-06

M. Kato
K. Maeda
T. Ozawa
M. Kashimura
Y. Kihara

Japan

Development of Np and Am bearing MOX fuels for Japan sodium cooled fast reactors

07-07

R.N. Jayaraj

India

Manufacture of core sub-assemblies and fertile fuel assemblies for Indian fast breeder programme

07-08

B.O. Lee
J.S. Cheon
H.J. Ryu
J.H. Kim
S.W. Yang
C.B. Lee

Korea, Republic of

Performance evaluation of metallic fuel for SFR

07-09

H. Ohta
T. Ogata
D. Papaioannou
M. Kurata
T. Koyama
J.P. Glatz
V. Rondinella

Japan

Development of minor actinide-containing metal fuels

07-10

T.K. Kim
C. Grandy
R.N. Hill

United States of America

Carbide and nitride fuels in Advanced Burner Reactor

08-01

P. Chellapandi
P. Puthiyavinayagm
V. Balasubramanian
S. Ragupathy
V. Rajanbabu
S.C. Chetal
B. Raj

India

Design concepts for reactor assembly components of 500 MWe future FRs

08-02

B.A. Vasilyev
Yu.L. Kamanin
V.V. Gladkov
V.N. Bartenev
S.F. Shepelev
N.G. Kuzavkov
V.V. Denisov
V.I. Karsonov

Russian Federation

Fast neutron reactor plant equipment upgrading

08-03

N. Kasahara
K. Sato
K. Tsukimori
N. Kawasaki

Japan

Development of elevated temperature structural design methods to realize compact reactor vessels

08-04

M. Chassignet
S. Dumas
C. Majot
G. Prèle
G. Rodriguez
E. Sanseigne

France

Challenges and innovative technologies on fuel handling systems for future sodium cooled fast reactors

08-05

M.K. Birznek
B.S. Chatskiy
Y.A. Bovsha

Russian Federation

Prospects for improvement of supporting systems of BN reactors based on BN-600 and BN-800 engineering experience

08-06

S. Fujiwara
R. Aizawa
Y. Oyamatsu
M. Funato
K. Katsuki
H. Ota

Japan

Development of a large diameter electromagnetic pump and a back-up power supply system for the 4S

08-07

T. Handa
Y. Oda
Y. Ono
K. Miyagawa
I. Matsumoto
K. Shimoji
A. Ide
H. Ishikawa
H. Hayafune

Japan

Research and development for the integrated IHX/pump

08-08

Y. Chikazawa
S. Kotake
S. Sawada

Japan

Comparison of pool/loop configurations in the JAEA fast reactor feasibility study

08-09

H. Yamano
M. Tanaka
A. Ono
T. Murakami
Y. Iwamoto
K. Yuki
H. Sago
S. Hayakawa

Japan

Unsteady elbow pipe flow to develop a flow-induced vibration evaluation methodology for JSFR

09-01

P.J. D'hondt
C. Nordborg
D.R. Weaver

Belgium

Availability of research and test facilities for fast reactor development

09-02

S. Maeda
M. Yamamoto
T. Soga
T. Sekine
T. Aoyama

Japan

Core Modification for the High Core Burn-up to improve Irradiation Efficiency of the Experimental Fast Reactor Joyo

09-03

T.H. Lee
J.H. Eoh
H.Y. Lee
J.H. Lee
T.J. Kim
J.Y. Jeong
S.K. Park
J.W. Han,
Y.B. Lee
D.H. Hahn

Korea, Republic of

Scientific design of large scale sodium thermal-hydraulic test facility in KAERI

09-04

A.V. Bychkov

Russian Federation

Status and basic lines of development of experimental and material science base for fast reactor technologies

10-01

A. Pryakhin
A. Stanculescu
Y. Yanev

IAEA

International fast reactor knowledge organization system

10-02

G. Rodriguez
F. Baqué
C. Latgé
A. Leclerc
L. Martin
B. Vray
T. Montanelli

France

The French Sodium School: Teaching sodium technology for the present and future generations of SFR users

10-03

M. Sawada
N. Koyagoshi
K. Sasaki
M. Nishida

Japan

Human development in Japan and abroad using the prototype FBR “Monju” towards the next-generation age

10-04

S.A.V. Satya Murty
P. Swaminathan
B. Raj

India

Knowledge management in fast reactors and related fuel cycles