052

G.A.K. Crommelin, H. van Dam

The NEREUS approach to broader applications on the nuclear technology

069

J. Kupitz et al.

IAEA activities on emerging nuclear systems

017

K. Tucek, J. Wallenius, J. Carlsson, W. Gudowski

Optimal distribution of fuel, poisons and diluents in sub-critical cores dedicated to waste transmutation

020

A.S. Gerasimov et al.

Americium and curium isotopes transmutation in accelerator driven systems

044

A. Abánades, A. Pérez-Navarro

Preliminary design studies for a 100 MW energy amplifier prototype

045

C. Rubbia et al.

A pebble-bed gas-cooled ADS system based on resonance enhancement transmutation

049

H. Boerner et al.

Experimental study of the transmutation of actinides in high intensity neutron fluxes

070

P.W.P.H. Ludwig, A.H.M. Verkooijen

Thermal stresses in the core a fast energy amplifier cooled with lead under normal operating conditions including reactor scram and secondary pump trip

073

A. Yamamoto, T. Misawa, H. Unesaki, S. Shiroya

Basic study on neutronics design of accelerator driven subcritical reactor for neutron source in Kyoto university research reactor institute (KURRI)

078

S. Taczanowski, J. Cetnar, G. Domanska, P. Gronek

Water cooled asymmetrically coupled accelerator-driven subcritical systems for transmutations

085

H.U. Wider, A.V. Jones

Lead/Bismuth-cooled, thorium based ADS and critical systems meet sceptic's criteria

093

C. Aragonese et al.

Analysis of different design options for the beam target of the energy amplifier demonstration facility

097

J.F. Lebrat et al.

Experimental investigation of multiplying subcritical media coupled with an accelerator: The MUSE experiments

098

H. Aït Abderrahim et al.

MYRRHA: A multipurpose accelerator driven system for research & development

003

V.B. Glebov et al.

Combined radiation protection of MOX fuel by short-term irradiation and admixture of U-232

006

B.R. Bergelson et al.

The Single-purpose Electro-Nuclear Facility (ENF)

010

S.E. Chigrinov, H.I. Kiyavitskaya, et al.

A subcritical facility development and demonstration experiment to research transmutation of long-lived radioactive waste

012

S.F. Sidorkin et al.

About ADS of the Moscow meson facility

023

G.V. Kiselev

New original ideas for accelerator driven systems

024

A.S. Gerasimov

Radiation accumulation in chloride salt and tungsten target of accelerator-driven system

033

M. Piera, S. Fan, J.M. Martínez-Val

An analysis of neutron sources for accelerator driven systems

034

J.M. Martínez-Val et al.

Nuclear and thermal-hydraulic analysis of pebble-bed transmutators

038

P. Vertes, A. Brolly

Evaluation of neutron sources for ADTW system

042

A. Rineiski, W. Maschek, B. Merk

Development of a moving fuel simmer-III model for transient analysis of a molten salt ADS

057

T.Y. Song et al.

Radiation damage study of HYPER beam window

065

A. Stankovsky et al.

Accumulation and transmutation of spallation products in accelerator-driven core

067

M. Pesic et al.

ADS with HEU in the Vinca institute

075

A.P. Barzilov et al.

Parametric study of ADS blanket with dual fast/thermal spectrum

087

A.Yu. Konobeyev, Yu.A. Korovin et al.

Nuclide composition of Pb-Bi coolant irradiated in 80 MW subcritical reactor

092

V.S. Barashenkov et al.

ADS's based on the 660 MeV proton phasotron JINR for research on utilization of plutonium

099

K. Van Tichelen et al.

MYRRHA: Design of a windowless spallation target for a prototype accelerator driven system

027

L. Bilbao, J.G. Linhart, G. Verri

Fusion from a m Z-pinch compressed by a cylindrical liner

032

Capabilities of existing powerful heavy ion accelerators to serve as drivers for fusion energy production experiments

041

V.S. Belyaev et al.

Bases of photo field fusion concept

047

S.A. Slutz et al.

Z-pinch driven fusion energy

004

J.F. Miramar Blázquez

Determination of transport mean free path for runaway electrons in a plasma corresponding to the inertial confinement fusion

008

D.G. Koshkarev, M.D. Churazov

Inertial confinement fusion with superpower heavy ion driver

025

A.G. Aksenov, M.D. Churazov

Advanced fuel target in HIF

035

S. Eliezer et al.

Cylindrical implosions by magnetic compression driven by Z-pinches

040

V.S. Belyaev, A.P. Matafonov, A.S. Kurilov

Development of diagnostic methods for measurement of neutron and gamma-radiation from laser produced plasma

060

Y. Kuroki et al.

Energy and momentum deposition effect of alpha-particles in the stagnation phase of ICF plasmas

061

H. Matsuura, Y. Tomita, Y. Nakao, K. Kudo, M. Ohta

Ion distribution functions and 14-MeV neutron generation rate in D-³He field-reversed configuration plasmas

063

T. Johzaki et al.

Two-dimensional diffusion code for calculating alpha-particle effects in ICF plasmas

066

Yu.I. Chernukhin et al.

Efficiency measurements of ⁶LiD thermal to fast neutrons converter in the experimental channel of IWW-2M reactor

096

G. Velarde et al.

Analysis of alternative targets design, materials and safety aspects in inertial fusion reactors

007

J. Guidez

Fast breeder reactor prospective

009

H. van Dam

The self-stabilizing criticality wave reactor

013

H. Sekimoto, K. Ryuu

A long life lead-bismuth cooled reactor with candle burnup

016

K. Mitachi et al.

Performance of a small molten-salt power reactor operated in thorium-uranium fuel-cycle

028

W.J.M. de Kruijf et al.

Non-linear characteristics of thermohydraulic instabilities in innovative BWRs

029

J.F. Kikstra, A.H.M. Verkooijen

Dynamic modelling of a nuclear gas turbine cogeneration plant for control system design

050

M. Rosselet, R. Chawla, O.P. Joneja, T. Williams

Measurement and analysis of shutdown rod worths in LEU-HTR configurations

053

Z. Alkan et al.

Concept of a non-meltable heavy water cooled and moderated pebble-bed-reactor

054

M-H. Kim, K-H. Kim

Fuel cycle performance indices in a high-converting LWR core design with once-through thorium fuel cycle

064

K. Nikitin et al.

Long-life water cooled small reactor with U-Np-Pu fuel

089

J.B.M. de Haas, A.I. van Heek, J.C. Kuijper

Fuel optimization for the ACACIA nuclear cogeneration plant

091

J.B.M. de Haas, E. Türkcan

HTTR criticality, physical parameters calculations and experimental results

014

H. Sekimoto, T. Murakami

Molten salt fuel fast reactor in the future equilibrium state

030

J.L. Kloosterman et al.

Numerical simulation of transient processes in a fluidized bed nuclear reactor

031

Y. Nishi, I. Kinoshita

Innovative heat exchanger for FBRs

048

V. Jagannathan, S. Ganesan, R. Karthikeyan

Sensitivity studies for a thorium breeder reactor design with the nuclear data libraries of WIMS library update project

051

R. Chawla et al.

Analysis of fuel enrichment effects investigated in the PROTEUS-LWHCR phase II experiments

079

F. Sefidvash, A.A. Mohamad

Passive cooling characteristics of the fluidized bed nuclear reactor

080

L.N. Carteciano, B. Dorr, G. Grötzbach

Numerical investigation of the single phase natural convection in sump cooling experiments with the FLUTAN code

090

Y. Ronen, M. Aboudy, D. Regev

Homogeneous ²⁴²Am fueled reactor for neutron capture therapy

095

S. Ganesan, H. Wienke

On the criticality property of ²³³Pa derived from various nuclear data files using the NJOY and the MCNP codes

018

J.A. Oyedele, A.A. Harms, A.N. Kornilovsky

On the dynamics of fuel pellets in pellet suspension reactor

046

S.A. Slutz et al.

Direct energy conversion in fission reactors: A U.S. NERI project

055

V.A. Belokogne

The principles of design for flying machines based on the fusion microexplosions

100

A.V. Gulevich et al.

Application of the nuclear photon engines for space studies

011

H. Takahashi

Subcritical fission plasma and pebble-bed reactors

086

V. Nedyelin, V.M. Pavlovych, S.A. Yatskevich

The concept of nuclear reactor with subcritical core and neutron field control by the gaseous or liquid flows of fissile materials

019

V. Arkhipov, H.J. Rütten

Second progress report on the IAEA coordinated research program on the potential of Th-based fuel cycles to constrain Pu and to reduce the long-lived waste toxicity

036

J.M. Martínez-Val et al.

Plutonium elimination in transmutation reactors

062

K. Konashi et al.

Transmutation method using neutron irradiation targets of actinide hydrides

081

E.T. Cheng, C. Wong

Transmutation of actinide in fusion reactors and related systems analysis

037

Z. Chizhikova et al.

Thorium fuel cycle based on natural uranium and ²³³U with the use of LWRs and FRs

076

T.O. Evdokimova, P.V. Kryukov

The concept of processing waste nuclear fuel by high-temperature ultracentrifuging