Advanced Reactors with Innovative Fuels

Workshop Proceedings, Villigen, Switzerland 21-23 October 1998

Advanced Reactors with Innovative Fuels
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Advanced Reactors with Innovative Fuels

Workshop Proceedings, Villigen, Switzerland 21-23 October 1998

Plutonium and minor actinide burning or recycling in thermal and fast reactors is being studied in many countries with the aim of maintaining and developing fuel cycle options which can be adjusted to changing demands and constraints. The challenge is to move towards an economically and socially sustainable nuclear energy system based on advanced reactors - advanced water-cooled reactors, fast reactors and perhaps accelerator-based, hybrid reactors - and new types of fuel cycles which help to minimise the waste arising. An additional issue concerns the availability of resources for the long-term future. This workshop introduced new ideas on R&D activities and identified areas and research tasks relevant for the deployment of new systems and in which international co-operation can be strengthened. The roles played by existing experimental facilities as well as possible needs for new ones are discussed. The conclusions of the technical sessions are synthesised and the results of a round table discussion on international co-operation are presented.

Publish Date
Publisher
OECD Publishing
Language
English
Pages
462

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Table of Contents

Foreword
Executive Summary
Opening Session
-Opening Address by S. Ion
Barriers and Incentives to Introducing New Reactors in the Deregulated Electricity Market by W. L. Wilkinson
The Need to Preserve Nuclear Fuels and Materials Knowledge by L. C. Walters and J. Graham
High Temperature Gas Reactors
-European Collaboration on Research into High-Temperature Reactor Technology by T.J. Abram, D. Hittner, W. von Lensa, A. Languille, D. Buckthorpe, J. Guidez, and J. Martin-Bermejo
Design of B4C Burnable Particles Mixed in LEU fuel for HTRs by V. Berthou, J. L. Kloosterman, H. van Dam, T.H.J.J. Ver der Hagen
Thorium and Plutonium Utilisation in Pebble-Bed Modular Reactor by U.E. Sikik, H. Dikmen, Y. Cecen, U. Colak, and O.K. Kadiroglu
A Conceptual Fluidised Particle-Bed Reactor - Application of Space-Dependent Kinetics by C.C. Pain, J.L.M.A. Gomes, M.D. Eaton, C.R.E. de Oliveira, A. P. Umpleby, A.J.H. Goddard, H. van Dam, T.H.J.J. van der Hagen, and D. Lathouwers
Design and Performance of Innovative Fuels
-Extensive Characterisation of a Material for Understanding its Behaviour as a Nuclear Fuel: The Case of a Zirconia-Plutonium Inert-Matrix Fuel by C. Degueldre, F. INgold, C. Hellwig, S. Conradson, M. Dobeli, and Y.W. Lee
Annular Plutonium-Zirconium Nitride Fuel Pellets by M. Streit, F. Inold, L. J. Gauckler, and J.-P. Ottaviani
Rock-Like Oxide Fuels for Burning Excess Plutonium in LWRs by T. Yamashita, K. Kruamoto, H. Akie, Y. Nakomo, N. Nitani, T. Nakamura, K. Kusagaya, and T. Ohmichi
Application of Cermica Nuclear Fuel Materials for Innovative Fuels and Fuel Cycles by Y.-W. Lee
Innovative MOX Fuel for Fast Reactor Applications by K. Bakker, H. Thesingh, t. Ozawa, Y. Shigetome, S. Kono, H. Endo, Ch. Hellwig, P. Heimgartner, F. Ingold, H. Wallin
Behaviour of Rock-Like Oxide Fuels under Reactivity-Initiated Accident Conditions by K. Kusagaya, T. Nakamura, M. Yoshinaga, and H. Akie
Theoretical Requirements to Tolerances to be Imposed on Fuel Rod Design Parameters for RBEC-M Lead-Bismuth Fast Reactor by A. Vasiliev, P Alekseev, K. Mikityuk, P. Fomichenko, and A. Shestopalov
Advanced Plutonium Assembly (APA): Evolution of the Concept, Neutron and Thermal-Mechanic Constraints by J. Porta, B. Gastaldi, C. Krakowiak-Aillaud, and L. Buffe
Thermophysical and Chemical Properties of Minor-Actinide Fuels by M. A. Mignanelli and R. Thetford
Some Views on the Design and Fabrication of Targets or Fuels Containing Curium by J. Sowers, A. Fernandez, R.J.M. Konings and G. Ledergerber
Evolutionary and Modular Water Reactors
-Innovative Features and Fuel-Design Approach in the IRIS Reactor by B. Petrovic, M. Carelli, E. Greenspan, H. Matsumoto, E. Padrovani, and F. Ganda
Core Concept for Long Operating Cycle Simplified BWR (LSBWR) by K. Hiraiwa, N. Yoshida, M. Nakamaru, H. Heki, M. Aritomi
Core Design Study on Reduced-Moderation Water Reactors by H. Akie, Y. Nakamo, T. Sirakawa, T. Okubo, and T. Iwamura
The Utilisation of Thorium Fuel in a Generation IV Light Water Reactor Design by T. J. Downar, Y. Xu
Thorium Fuel in LWRs: An Option for an Effective Reduction of Plutonium Stockpiles by D. Porsch, D. Sommer
PWRs Using HTGR Fuel Concept with Cladding for Ultimate Safety by Y. Shimazu, H. Tochihara, Y. Akiyama, and K. Itoh
Feasibility of Partical LWR Core Loadings with Inert-Matrix Fuel by U. Kasemeyer, Ch. Hellwig, D. W. Dean, R. Chawla, G. Meier, and T. Williams
CEA Studies about Innovative Water-Cooled Reactor Concepts by P. Dumaz, A.Bergeron, G. M. Gautier, J. F. Pignatel, G.PRimpault, G. Youinou
BARS: BWR with Advanced Recycle System by K. Hiraiwa, Y. Yamamoto, K. Yoshioka, M. Yamaoka, A. Inoue, J. Mimatu
Advanced Fuel Cycle for Long-Lived Core of Small-Size Light Water Reactor of ABV Type by A. Polismakov, V. Tsbulsky, A. Chibinyaev, and P. Alekseev
A New Approach for the Systems Dedicated to Transmutation: The Reactor with Compensated Beta by B. Bernardin
Fast Spectrum Reactors
-A Simplified LMBFR Concept (SFR) by D. V. Sherwood, and T. A. Lennox
The Design of the Enhanced Gas-Cooled Reactor (EGCR) by H. M.Beaumont, A. Cheyne, J. Gilroy, G. Hulme, T. A. Lennox, R. E. Sunderland, and D.P.Every
The Flexibility of CO2-Cooled Fast Reactors for Plutonium and Minor-Actinide Management by H. M>Beaumont, R. E. Sunderland, T. A. Lennox, J. T. Murgatroyd, E. K. Whyman, G. Hulme, and S. J. Crossley
RBEC Lead-Bismuth-Cooled Fast Reactor: Review of Conceptual Design by P. Alekseev, P. fomichenko, K. Mikityuk, V. Nevinitsa, T. Shchepetina, S. Subbotin, and A. Vasiliev
Design and Performance Studies for Minor-Actinide Target Fuels by T. D. Newton and P.J. Smith
Applications of "CANDLE" Burn-Up Startegy to Several Reactors by H. Sekimoto
Molten-Salt Reactors
-Molten-Salt Reactor for Burning of Transuranium Nuclides Forming in Closed Nuclear Fuel Cycle by P. N.Alekseev, A. A. Dudnikov, V. v. Ignatiev, N.N. Ponomarev-Stepnoy, V. N. Prusakov, S. A. Subbotin, A. V. Vasiliev, and R. Ya. Zakirov
AMSTER: A Molten Salt Reacor Concept Generating Its Own 233U and Incinerating Transuranium Elements by D. Lecarpentier, C. Garzenne, J. Vergnes, H. Mouney, and M. Delpech
The SPHINX Project: Experimental Verification of Design Inputs for a Transmuter with Liquid Fueld Based on Molten Flourides by M. Hron, J. Uhlir, and J. Vanicek
Proposal of a Molten-Salt Systm for Long-Term Energy Production by V. Berthou, I. Slessarev, and M. Salvatores
Accelerator-Driven Systems
-Experimental Investigations of the Accelerator-Driven Transmutation Technologies at the Subcritical Facility "Yalina" by S.E. Chiginov, H. I. Kiyavitskaya, I. g. Serafinovich, I. L.adhno, C. K.Rutkovskaia, Y. fokov, A. M> Khilmanovich, B. A. Marstinkevich, V. V. Bournos, S. V. Korneev, S. E. Mazanik, A. V. Kulikovsakya, T.P. Korbut, N. K. Voropaj, I. V. Zhouk, and M. K. Kievec
MYRRHA, A Multi-Purpose ADS for R&D: PRe-Design Phase Completion by H> Ait Abderrahim, P. Kupschus, PH.Benoit, E. Malambu, K. Van tichelen, B.Arien, F. Vermeersch, Th Aoust, Ch. De Raedt,S. Bodart, P.D'hondt, Y. Jongen, S. Ternier, and D. Vandeplassche
Optimisation of Condeptual Design of Cascade Subcritical Molten-Salt Reactor by A. Vasiliev, P. Alekseev, A. Dudnikov, K. Mikityuk, and S. Subbotin
Transmutation and Incineration of MAs in LWRs, MTRs, and ADSs by Ch De Raedt, B.Verboomen, Th-Aoust, H. Ait Abderrahim, E. Malambu, and L. H. Baetsle
Determination of the 233Pa(n,f) Reaction Cross-Section for Thorium Fueled Reactors by F. tovesson, F.J. Hambsch, A. Oberstedt, B. Fogelberg, E. Ramstrom and S. Oberstedt
Miscellaneous Themes
-The Key Role of Critical Mock-Up Facilities for Neutronics Physics Assessment fo Advanced Reactors: An Overview of CEA Cadarache Tools by g. Bignan, D. Rippert, and P. Fougeras
Advnaced concepts for Waste Management and Nuclear Energy Production in the EURATOM 5th Framework Programme by M. Hugon, V. P. Bhatnagar, and J Martin Bermejo
Annex 1. List of Participants
Annex 2. Technical Programme

Edition Notes

Published in
Paris
Series
Nuclear science, Nuclear Science

The Physical Object

Format
[electronic resource]:
Pagination
462 p.
Number of pages
462

Edition Identifiers

Open Library
OL53207588M
ISBN 13
9789264173866

Work Identifiers

Work ID
OL39091153W

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