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Results: 1-13 |
Results: 13
THE ARIES-RS POWER CORE - RECENT DEVELOPMENT IN LI V DESIGNS/
Authors: SZE DK BILLONE MC HUA TQ TILLACK M NAJMABADI F WANG XR MALANG S ELGUEBALY LA SVIATOSLAVSKY IN BLANCHARD JP CROWELL JA KHATER HY MOGAHED EA WAGANER LM LEE D COLE D
Citation: Dk. Sze et al., THE ARIES-RS POWER CORE - RECENT DEVELOPMENT IN LI V DESIGNS/, Fusion engineering and design, 41, 1998, pp. 371-376
IRRADIATION CREEP OF VANADIUM-BASE ALLOYS
Authors: TSAI H MATSUI H BILLONE MC STRAIN RV SMITH DL
Citation: H. Tsai et al., IRRADIATION CREEP OF VANADIUM-BASE ALLOYS, Journal of nuclear materials, 263, 1998, pp. 1471-1475
REVISION OF THE TENSILE DATABASE FOR V-TI AND V-CR-TI ALLOYS TESTED AT ANL
Authors: BILLONE MC CHUNG HM SMITH DL
Citation: Mc. Billone et al., REVISION OF THE TENSILE DATABASE FOR V-TI AND V-CR-TI ALLOYS TESTED AT ANL, Journal of nuclear materials, 263, 1998, pp. 1523-1527
OVERVIEW OF THE ARIES-RS REVERSED-SHEAR TOKAMAK POWER-PLANT STUDY
Authors: NAJMABADI F BATHKE CG BILLONE MC BLANCHARD JP BROMBERG L CHIN E COLE FR CROWELL JA EHST DA ELGUEBALY LA HERRING JS HUA TQ JARDIN SC KESSEL CE KHATER H LEE VD MALANG S MAU TK MILLER RL MOGAHED EA PETRIE TW REIS EE SCHULTZ J SIDOROV M STEINER D SVIATOSLAVSKY IN SZE DK THAYER R TILLACK MS TITUS P WAGNER LM WANG XR WONG CPC
Citation: F. Najmabadi et al., OVERVIEW OF THE ARIES-RS REVERSED-SHEAR TOKAMAK POWER-PLANT STUDY, Fusion engineering and design, 38(1-2), 1997, pp. 3-25
THERMAL AND TRITIUM TRANSPORT IN LI2O AND LI2ZRO3
Authors: BILLONE MC
Citation: Mc. Billone, THERMAL AND TRITIUM TRANSPORT IN LI2O AND LI2ZRO3, Journal of nuclear materials, 237, 1996, pp. 1462-1466
MATERIALS FOR BREEDING BLANKETS
Authors: MATTAS RF BILLONE MC
Citation: Rf. Mattas et Mc. Billone, MATERIALS FOR BREEDING BLANKETS, Journal of nuclear materials, 237, 1996, pp. 72-81
PROGRESS IN TRITIUM RETENTION AND RELEASE MODELING FOR CERAMIC BREEDERS
Authors: RAFFRAY AR BILLONE MC FEDERICI G TANAKA S
Citation: Ar. Raffray et al., PROGRESS IN TRITIUM RETENTION AND RELEASE MODELING FOR CERAMIC BREEDERS, Fusion engineering and design, 28, 1995, pp. 240-251
TIARA ANALYSIS OF TRITIUM INVENTORY IN LI2O
Authors: BILLONE MC
Citation: Mc. Billone, TIARA ANALYSIS OF TRITIUM INVENTORY IN LI2O, Fusion engineering and design, 28, 1995, pp. 313-318
STATUS OF BERYLLIUM DEVELOPMENT FOR FUSION APPLICATIONS
Authors: BILLONE MC DALLEDONNE M MACAULAYNEWCOMBE RG
Citation: Mc. Billone et al., STATUS OF BERYLLIUM DEVELOPMENT FOR FUSION APPLICATIONS, Fusion engineering and design, 27, 1995, pp. 179-190
DIFFUSION DESORPTION OF TRITIUM FROM IRRADIATED BERYLLIUM/
Authors: BALDWIN DL BILLONE MC
Citation: Dl. Baldwin et Mc. Billone, DIFFUSION DESORPTION OF TRITIUM FROM IRRADIATED BERYLLIUM/, Journal of nuclear materials, 215, 1994, pp. 948-953
AN ASSESSMENT OF MODELS FOR TRITIUM RELEASE FROM CERAMIC BREEDERS FORBLANKET ANALYSIS APPLICATIONS
Authors: FEDERICI G RAFFRAY AR BILLONE MC WU CH CHO S ABDOU MA
Citation: G. Federici et al., AN ASSESSMENT OF MODELS FOR TRITIUM RELEASE FROM CERAMIC BREEDERS FORBLANKET ANALYSIS APPLICATIONS, Journal of nuclear materials, 215, 1994, pp. 1003-1009
BEHAVIOR OF EBR-II MK-V-TYPE FUEL-ELEMENTS IN SIMULATED LOSS-OF-FLOW TESTS
Authors: LIU YY TSAI H BILLONE MC HOLLAND JW KRAMER JM
Citation: Yy. Liu et al., BEHAVIOR OF EBR-II MK-V-TYPE FUEL-ELEMENTS IN SIMULATED LOSS-OF-FLOW TESTS, Journal of nuclear materials, 204, 1993, pp. 194-202
MODELING THE BEHAVIOR OF METALLIC FAST-REACTOR FUELS DURING EXTENDED TRANSIENTS
Authors: KRAMER JM LIU YY BILLONE MC TSAI HC
Citation: Jm. Kramer et al., MODELING THE BEHAVIOR OF METALLIC FAST-REACTOR FUELS DURING EXTENDED TRANSIENTS, Journal of nuclear materials, 204, 1993, pp. 203-211
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