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検索結果 46 件

Beam shut down considerations for large accelerator-driven target systems BNL64667 DE98 000347

Beam shut down considerations for large accelerator-driven target systems BNL64667 DE98 000347
マイクロ規格・テクニカルリポート類
Van Tuyle, G. J, Boggs, B. L1997<LS-DE98/000347>
国立国会図書館

Target designs for Accelerator Production of Tritium (APT) utilizing lithium-aluminum BNL-62724 DE96 008219 CONF-96030614

Target designs for Accelerator Production of Tritium (APT) utilizing lithium-aluminum BNL-62724 DE96 008219 CONF-96030614
マイクロ規格・テクニカルリポート類
Todosow, M, Van Tuyle, G. J1996<LS-DE96/008219>
国立国会図書館

Technologies using accelerator-driven targets under development at BNL BNL-60657 DE94 016794 CONF-940710312

Technologies using accelerator-driven targets under development at BNL BNL-60657 DE94 016794 CONF-940710312
マイクロ規格・テクニカルリポート類
Van Tuyle, G. J1994<LS-DE94/016794>
国立国会図書館

Accelerator-driven assembly for plutonium transformation (ADAPT) BNL-60884 DE95 002415 CONF-9501107

Accelerator-driven assembly for plutonium transformation (ADAPT) BNL-60884 DE95 002415 CONF-9501107
マイクロ規格・テクニカルリポート類
Van Tuyle, G. J, Todosow, M, Powell, J, Schweitzer, D1994<LS-DE95/002415>
国立国会図書館

Experimental evaluation of mercury release from molten lead BNL-60883 DE95 002414

Experimental evaluation of mercury release from molten lead BNL-60883 DE95 002414
マイクロ規格・テクニカルリポート類
Tutu, N. K, Greene, G. A, Van Tuyle, G. J1994<LS-DE95/002414>
国立国会図書館

PLAN TO ASSESS AND DEVELOP ACCELERATOR-DRIVEN WASTE TRANSMUTATION TECHNOLOGY. (LA ; LA-UR-00-5189)

PLAN TO ASSESS AND DEVELOP ACCELERATOR-DRIVEN WASTE TRANSMUTATION TECHNOLOGY. (LA ; LA-UR-00-5189)
紙図書
VAN TUYLE, G.J.(et al.)2000.
全国の図書館

TARGET DESIGNS FOR ACCELERATOR PRODUCTION OF TRITIUM (APT) UTILIZING LITHIUM-ALUMINUM (BNL ; BNL-62724)

TARGET DESIGNS FOR ACCELERATOR PRODUCTION OF TRITIUM (APT) UTILIZING LITHIUM-ALUMINUM (BNL ; BNL-62724)
紙図書
TODOSOW, M.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1996.
全国の図書館

TECHNOLOGIES USING ACCELERATOR-DRIVEN TARGETS UNDER DEVELOPMENT AT BNL (BNL ; BNL-60657)

TECHNOLOGIES USING ACCELERATOR-DRIVEN TARGETS UNDER DEVELOPMENT AT BNL (BNL ; BNL-60657)
紙図書
VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1994.
全国の図書館

SAFETY CHARACTERISTICS OF POTENTIAL WASTE TRANSMUTATION SYSTEMS (BNL ; BNL-49014)

SAFETY CHARACTERISTICS OF POTENTIAL WASTE TRANSMUTATION SYSTEMS (BNL ; BNL-49014)
紙図書
VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1993.
全国の図書館

EXPERIMENTAL EVALUATION OF MERCURY RELEASE FROM MOLTEN LEAD (BNL ; BNL-60883)

EXPERIMENTAL EVALUATION OF MERCURY RELEASE FROM MOLTEN LEAD (BNL ; BNL-60883)
紙図書
TUTU, N.K.// GREENE, G.A.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1994.
全国の図書館

EVALUATIONS OF 1990 PRISM DESIGN REVISIONS. (NUREG ; NUREG/CR-5815)

EVALUATIONS OF 1990 PRISM DESIGN REVISIONS. (NUREG ; NUREG/CR-5815)
紙図書
VAN TUYLE, G.J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1992.
全国の図書館

ANALYSIS OF PIUS REACTOR PASSIVE SHUTDOWN USING PC-BASED MODEL (BNL ; BNL-NUREG-47809)

ANALYSIS OF PIUS REACTOR PASSIVE SHUTDOWN USING PC-BASED MODEL (BNL ; BNL-NUREG-47809)
紙図書
CHENG, H.S.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1992.
全国の図書館

IMPROVED NUMERICAL MODEL FOR THE INVESTIGATION OF THERMAL HYDRAULIC PHENOMENA WITH APPLICATIONS TO LMR REACTOR COMPONENTS (BNL ; BNL-NUREG-47747)

IMPROVED NUMERICAL MODEL FOR THE INVESTIGATION OF THERMAL HYDRAULIC PHENOMENA WITH APPLICATIONS TO LMR REACTOR COMPONENTS (BNL ; BNL-NUREG-47747)
紙図書
CHAN, B.C.// KENNETT, R.J.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1992.
全国の図書館

PLANT ANALYZER FOR PIUS SYSTEM SIMULATIONS (BNL ; BNL-NUREG-46706)

PLANT ANALYZER FOR PIUS SYSTEM SIMULATIONS (BNL ; BNL-NUREG-46706)
紙図書
CHENG, H.S.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1991.
全国の図書館

ANALYSIS OF POSTULATED EVENTS FOR THE REVISED ALMR/PRISM DESIGN (BNL ; BNL-NUREG-46429)

ANALYSIS OF POSTULATED EVENTS FOR THE REVISED ALMR/PRISM DESIGN (BNL ; BNL-NUREG-46429)
紙図書
SLOVIK, G.C.// VAN TUYLE, G.J. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1991.
全国の図書館

PROPOSED PARTITIONING AND TRANSMUTATION OF LONG-LIVED NUCLEAR WASTES (BNL ; BNL-46106)

PROPOSED PARTITIONING AND TRANSMUTATION OF LONG-LIVED NUCLEAR WASTES (BNL ; BNL-46106)
紙図書
VAN TUYLE, G.J.// RAWLINS, J.A. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1991.
全国の図書館

ASSESSMENT OF PRISM RESPONSES TO LOSS OF FLOW EVENTS (BNL ; BNL-NUREG-47818)

ASSESSMENT OF PRISM RESPONSES TO LOSS OF FLOW EVENTS (BNL ; BNL-NUREG-47818)
紙図書
SLOVIK, G.C.// VAN TUYLE, G.J.// SANDS, S. (BROOKHAVEN NATIONAL LAB., UPTON, NY (UNITED STATES))Brookhaven National Laboratory(Brookhaven National Laboratory)1992.
全国の図書館

SUMMARY OF ADVANCED LMR (LIQUID METAL REACTOR) EVALUATIONS: PRISM (POWER REACTOR INHERENTLY SAFE MODULE) AND SAFR (SODIUM ADVANCED FAST REACTOR). (FORMAL REPT.) (NUREG ; NUREG/CR-5364; BNL-NUREG-52197)

SUMMARY OF ADVANCED LMR (LIQUID METAL REACTOR) EVALUATIONS: PRISM (POWER REACTOR INHERENTLY SAFE MODULE) AND SAFR (SODIUM ADVANCED FAST REACTOR). (FORMAL REPT.) (NUREG ; NUREG/CR-5364; BNL-NUREG-52197)
紙図書
VAN TUYLE, G.J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
全国の図書館

MINET (MOMENTUM INTEGRAL NERWORK) CODE DOCUMENTATION. (NUREG ; NUREG-CR-3668)

MINET (MOMENTUM INTEGRAL NERWORK) CODE DOCUMENTATION. (NUREG ; NUREG-CR-3668)
紙図書
VAN TUYLE, G.J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
全国の図書館

HTGR (HIGH TEMPERATURE GAS-COOLED REACTOR) INGRESS ANALYSIS USING MINET. (TECHNICAL REPT.) (NUREG ; NUREG/CR-5355; BNL-NUREG-52193)

HTGR (HIGH TEMPERATURE GAS-COOLED REACTOR) INGRESS ANALYSIS USING MINET. (TECHNICAL REPT.) (NUREG ; NUREG/CR-5355; BNL-NUREG-52193)
紙図書
VAN TUYLE, G.J.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1989.
全国の図書館