R. Mattas

发表

L p -9 / ! 2 / 3 Results of R & D for LithiumNanadium Breeding Blanket Design JuL 0 7 I 997

I. Kirillov, D. Efremov, D. Smith, 2008 .

Effect of Thin Y-O and Si-O Films on In-situ Formed CaO Coatings on V-4%Cr-4%Ti in Liquid 2.8 at.% Ca-Li *

K. Natesan, R. Mattas, Jong-Hee Park, 2002 .

Results of R&D for lithium/vanadium breeding blanket design

Donald L. Smith, I. Kirillov, A. Rusanov, 1998 .

Development of electrically insulating coatings on vanadium alloys for lithium-cooled blankets*

Donald L. Smith, J. Park, K. Natesan, 1997 .

Vanadium alloys for fusion reactor applications

David L. Smith, Donald L. Smith, R. Mattas, 1992 .

ITER breeding blanket design for the enhanced performance phase

M. Billone, S. Majumdar, D. Loesser, 1998 .

Nuclear responses in INTOR plasma stabilization elements

F. W. Wiffen, Y. Gohar, R. Mattas, 1985 .

The Effect of Sputtering on Stress Distributions in Plasma-Facing Components

J. Blanchard, R. Mattas, 1991 .

Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel

Richard F. Mattas, I. N. Sviatoslavsky, Siegfried Malang, 2004 .

APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

S. Sharafat, I. Sviatoslavsky, C.P.C. Wong, 2003 .

ITER reference breeding blanket design

W. Gulden, A. Lopatkin, G. Celentano, 1999 .

Poloidal divertor systems for impurity and particle control in ignition Tokamaks

D. Post, R. Mattas, 1985 .

Performance limits for fusion first-wall structural materials

Richard F. Mattas, S. Majumdar, Michael C. Billone, 1999 .

Divertor engineering studies for the international tokamak reactor

M. Baskes, J. Blanchard, A. Hassanein, 1986 .

Liquid lithium self-cooled breeding blanket design for ITER

S. I. Sidorenkov, Donald L. Smith, Y. Gohar, 1998 .

Tritium production and distribution in a zircaloy-clad Li7Pb2 assembly irradiated in the oak ridge research reactor☆

A. G. Hins, V. Maroni, J. Krsul, 1983 .

Engineering design of the ITER blanket and relevant research and development results

K. Ioki, R. Raffray, D. Loesser, 1999 .

ITER R&D: Vacuum vessel and in-vessel components: Shield blanket module

W. Dänner, K. Ioki, A. Cardella, 2001 .

ITER first wall:shield blanket

D. Williamson, D. Loesser, P. Barabaschi, 1998 .

The TEXTOR helium self-pumping experiment: Design, plans, and supporting ion-beam data on helium retention in nickel

David L. Smith, Y. Hirooka, B. Doyle, 1990 .

Crucial issues on liquid metal blanket design

S. Malang, G. Casini, R. Mattas, 1991 .

U.S. ITER limiter module design

M. Billone, A. Hassanein, R. Mattas, 1996 .

Fusion Reactor Materials

M. Billone, D. Smith, R. Mattas, 2006 .

Some Implications of Radiation-Induced Property Changes in Austenitic Stainless Steels on ITER First-Wall Design and Performance

E. E. Bloom, T. Kondo, A. Hishinuma, 1991 .

In-cell facility for performing mechanical-property tests on irradiated cladding

R. Mattas, R. Haglund, F. L. Yaggee, 1978 .

Isotope effects on the motion of O-H clusters in Nb

H. Birnbaum, R. Mattas, 1975 .

Internal friction in germanium at low temperatures

W. L. Haworth, H. Birnbaum, R. Mattas, 1972 .

Fusion Reactor Materials

M. Billone, D. Smith, R. Mattas, 2006 .

Model for life-limiting properties of fusion reactor structural materials

D. L. Smith, R. F. Mattas, D. Smith, 1978 .

Materials for breeding blankets

M. Billone, R. Mattas, 1996 .

Impurity Control Systems for Reactor Experiments

D. Post, R. Mattas, 1986 .

Materials for impurity control

M. Abdou, D. Smith, R. Mattas, 1984 .

On the exploration of innovative concepts for fusion chamber technology

Ralph W. Moir, Alice Ying, Mark S. Tillack, 2001 .

Materials integration issues for high performance fusion power systems 1 Work supported by the US Department of Energy, Office of Fusion Energy, under Contract W-31-109-Eng-38. 1

S. Majumdar, Donald L. Smith, Michael C. Billone, 1998 .

Experimental results for Phase II of the JAERI/USDOE collaborative program on fusion blanket neutronics

E. F. Bennett, Y. Ikeda, H. Maekawa, 1989 .

Microstructural examination of fast-neutron irradiated Li2O

R. Mattas, D. Porter, Y. Liu, 1985 .

Material problems and requirements related to the development of fusion blankets : the designer point of view

G. Kalinin, M. Donne, R. Mattas, 1994 .

An impurity control test facility (ICTF) for the study of fusion reactor/plasma edge materials

D. Ehst, N. Hershkowitz, J. Brooks, 1985 .

ALPS-advanced limiter-divertor plasma-facing systems

Ralph W. Moir, Mark S. Tillack, S. Molokov, 1999 .

Tritium recovery from lithium, based on a cold trap

Richard F. Mattas, Dai-Kai Sze, D. Sze, 1995 .

Comparison of lithium and the eutectic lead lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets

Richard F. Mattas, S. Malang, S Malang, 1995 .

STARFIRE, a commercial tokamak power plant design

H. C. Stevens, Richard F. Mattas, Mohamed A. Abdou, 1981 .

Materials issues in diagnostic systems for BPX and ITER

F. W. Wiffen, S. Zinkle, E. Farnum, 1992 .

Self-pumping impurity control by in-situ metal deposition

Richard F. Mattas, Jeffrey N. Brooks, J. Brooks, 1984 .

Measurement techniques for fusion blanket neutronics experiments

E. F. Bennett, M. Abdou, Y. Ikeda, 1995 .

Design and Techniques for Fusion Blanket Neutronics Experiments Using an Accelerator-Based Deuterium-Tritium Neutron Source

E. F. Bennett, M. Abdou, Y. Ikeda, 1995 .

Self-Sustaining Coatings for Fusion Applications - Copper Lithium Alloys

D. Gruen, A. Krauss, M. Mendelsohn, 1985 .

Current state of development and expected performance of copper-lithium alloys as an impurity control system in fusion applications

D. Gruen, A. Krauss, J. Brooks, 1985 .

Sn-Li, a new coolant/breeding material for fusion applications.

S. Zinkle, M. Sawan, E. Cheng, 1999 .

DEMONSTRATION TOKAMAK POWER PLANT

David L. Smith, G. D. Morgan, D. Ehst, 1983 .

MHD considerations for a self-cooled liquid lithium blanket

Richard F. Mattas, Dai-Kai Sze, B. F. Picologlou, 1992 .

Assessment of alkali metal coolants for the ITER blanket

K. Natesan, C. Reed, R. Mattas, 1994 .

Evaluation of the Tungsten Alloy Vaporizing Lithium First Wall and Blanket Concept

C.P.C. Wong, S. Malang, M. Corradini, 2001 .

Helium Pumping Strategies for D-T Fusion Devices

R. Nygren, A. Krauss, O. Auciello, 1990 .

Water-Cooled Solid-Breeder Blanket Concept for ITER

H. C. Stevens, Richard F. Mattas, Dai-Kai Sze, 1989 .