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検索結果 23 件

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL. FUEL CYCLE RESEARCH AND DEVELOPMENT. (S&T Issue 2014-14)(CD-ROM) (DE141113602 ; DE141113602; FCRD-UFD-2013-000257; PNNL-22646)

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL. FUEL CYCLE RESEARCH AND DEVELOPMENT. (S&T Issue 2014-14)(CD-ROM) (DE141113602 ; DE141113602; FCRD-UFD-2013-000257; PNNL-22646)
紙図書
CUTA, J.M.(et al.)2013.
全国の図書館
  • 著者標目CUTA, J.M.

PRELIMINARY THERMAL MODELING OF HI-STORM 100S-218 VERSION B STORAGE MODULES AT HOPE CREEK NUCLEAR POWER STATION ISFSI. (S&T Issue 2014-08)(CD-ROM) (DE131096125 ; DE131096125; FCRD-UFD-2013-000297; PNNL-22552)

PRELIMINARY THERMAL MODELING OF HI-STORM 100S-218 VERSION B STORAGE MODULES AT HOPE CREEK NUCLEAR POWER STATION ISFSI. (S&T Issue 2014-08)(CD-ROM) (DE131096125 ; DE131096125; FCRD-UFD-2013-000297; PNNL-22552)
紙図書
CUTA, J.M.(et al.)2013.
全国の図書館
  • 著者標目CUTA, J.M.

Investigation of flammable gas and thermal safety issues for retrieval of waste from Tank 241-AN-105 PNNL11996 DE98 059303

Investigation of flammable gas and thermal safety issues for retrieval of waste from Tank 241-AN-105 PNNL11996 DE98 059303
紙マイクロ規格・テクニカルリポート類
Caley, S. M, Stewart, C. W, Antoniak, Z. I, Cuta, J. M, Mahoney, L. A1998<LS-DE98/059303>
国立国会図書館全国の図書館

Evaluation of the potential for significant ammonia releases from Hanford waste tanks PNNL-11237 DE96 013494

Evaluation of the potential for significant ammonia releases from Hanford waste tanks PNNL-11237 DE96 013494
紙マイクロ規格・テクニカルリポート類
Palmer, B. J, Anderson, C. M, Chen, G, Cuta, J. M, Ferryman, T. A1996<LS-DE96/013494>
国立国会図書館全国の図書館

Ammonia and ammonium hydroxide sensors for ammonia/water absorption machines: Literature review and data compilation PNL-10546 DE95 011871

Ammonia and ammonium hydroxide sensors for ammonia/water absorption machines: Literature review and data compilation PNL-10546 DE95 011871
マイクロ規格・テクニカルリポート類
Anheier, N. C, McDonald, C. E, Cuta, J. M, Cuta, F. M, Olsen, K. B1995<LS-DE95/011871>
国立国会図書館

COBRA-SFS: A thermal-hydraulic analysis code for spent fuel storage and transportation casks PNL-10782 DE96 000770

COBRA-SFS: A thermal-hydraulic analysis code for spent fuel storage and transportation casks PNL-10782 DE96 000770
マイクロ規格・テクニカルリポート類
Michener, T. E, Rector, D. R, Cuta, J. M, Dodge, R. E, Enderlin, C. W1995<LS-DE96/000770>
国立国会図書館

"Duke Power Co Thermal-Hydraulic Statistical Core Design Methodology;App D;Oconee Plant Specific Data (DPC-NE-2005P, App D)."

"Duke Power Co Thermal-Hydraulic Statistical Core Design Methodology;App D;Oconee Plant Specific Data (DPC-NE-2005P, App D)."
紙図書
CUTA, J. M.AFFILIATION NOT ASSIGNED1999/04/30.
全国の図書館

ENGINEERING APPROACH TO TWO-PHASE FLOW MODELING IN REDUCED GRAVITY. (PNL ; PNL-SA-17510)

ENGINEERING APPROACH TO TWO-PHASE FLOW MODELING IN REDUCED GRAVITY. (PNL ; PNL-SA-17510)
紙図書
CUTA, J.M.Pacific Northwest Laboratory(Pacific Northwest Laboratory)1990.
全国の図書館
  • 著者標目CUTA, J.M.

REDUCED GRAVITY BOILING AND CONDENSING EXPERIMENTS SIMULATED WITH THE COBRA TRAC COMPUTER CODE. (PNL ; PNL-SA-15368)

REDUCED GRAVITY BOILING AND CONDENSING EXPERIMENTS SIMULATED WITH THE COBRA TRAC COMPUTER CODE. (PNL ; PNL-SA-15368)
紙図書
CUTA, J.M.(et al.)Pacific Northwest Laboratory(Pacific Northwest Laboratory)1988.
全国の図書館
  • 著者標目CUTA, J.M.

VIPRE-01; A Thermal-Hydraulic Code for Reactor Cores Volume 5; Guidelines (EPRI ; EPRI-NP-2511-CCM-Vol.5)

VIPRE-01; A Thermal-Hydraulic Code for Reactor Cores Volume 5; Guidelines (EPRI ; EPRI-NP-2511-CCM-Vol.5)
紙図書
Stewart, C.W./Cuta, J.M.Electric Power Research Institute(Electric Power Research Institute)1988.
全国の図書館
  • 著者標目Stewart, C.W. Cuta, J.M.

VIPRE (VERSATILE INTERNALS AND COMPONENT PROGRAM FOR REACTORS; EPRI)-0.1. (EPRI ; EPRI-NP-2511-CCM-A-VOL.4)

VIPRE (VERSATILE INTERNALS AND COMPONENT PROGRAM FOR REACTORS; EPRI)-0.1. (EPRI ; EPRI-NP-2511-CCM-A-VOL.4)
紙図書
CUTA, J.M.(et al.)Electric Power Research Institute(Electric Power Research Institute)1987.
全国の図書館
  • 著者標目CUTA, J.M.

COMPARISONS OF COBRA-SFS CALCULATIONS WITH DATA FROM SIMULATED SECTIONS OF UNCONSOLIDATED AND. (EPRI ; EPRI-NP-4593)

COMPARISONS OF COBRA-SFS CALCULATIONS WITH DATA FROM SIMULATED SECTIONS OF UNCONSOLIDATED AND. (EPRI ; EPRI-NP-4593)
紙図書
CUTA, J.M.(et al.)Electric Power Research Institute(Electric Power Research Institute)1986.
全国の図書館
  • 著者標目CUTA, J.M.

VIPRE-01; A Thermal-Hydraulic Code for Reactor Cores Volume 4; Applications (EPRI ; EPRI-NP-2511-CCM-A-Vol.4)

VIPRE-01; A Thermal-Hydraulic Code for Reactor Cores Volume 4; Applications (EPRI ; EPRI-NP-2511-CCM-A-Vol.4)
紙図書
Cuta, J.M./Stewart, C.W.Electric Power Research Institute(Electric Power Research Institute)1987.
全国の図書館
  • 著者標目Cuta, J.M. Stewart, C.W.

LOW GRAVITY FLUID-THERMAL EXPERIMENTS (CONF ; CONF-8706214-1)

LOW GRAVITY FLUID-THERMAL EXPERIMENTS (CONF ; CONF-8706214-1)
紙図書
1987.
全国の図書館

Comparisons of COBRA-SFS Calculations With Data From Simulated Sections of Unconsolidated and Consolidated BWR Spent Fuel (EPRI ; EPRI-NP-4593)

Comparisons of COBRA-SFS Calculations With Data From Simulated Sections of Unconsolidated and Consolidated BWR Spent Fuel (EPRI ; EPRI-NP-4593)
紙図書
Cuta, J.M./Creer, J.M.Electric Power Research Institute(Electric Power Research Institute)1986.
全国の図書館
  • 著者標目Cuta, J.M. Creer, J.M.

Cask consolidated spent fuel thermal analyses using the COBRA-SFS code (PNL ; PNL-SA-13876; CONF-860417-7; DE86011108)

Cask consolidated spent fuel thermal analyses using the COBRA-SFS code (PNL ; PNL-SA-13876; CONF-860417-7; DE86011108)
紙図書
Rector, D.R., Cuta, J.M., Creer, J.M.Pacific Northwest Lab.1986.4.
全国の図書館
  • 著者標目Rector, D.R. Cuta, J.M. Creer, J.M.

VIPRE-0.1: A THERMAL-HYDRAULIC CODE FOR REACTOR CORES. (EPRI ; EPRI-NP-2511-CCM-VOL.2(REV.2))

VIPRE-0.1: A THERMAL-HYDRAULIC CODE FOR REACTOR CORES. (EPRI ; EPRI-NP-2511-CCM-VOL.2(REV.2))
紙図書
CUTA, J.M.(et al.)Electric Power Research Institute(Electric Power Research Institute)1985.
全国の図書館
  • 著者標目CUTA, J.M.

THERMAL-HYDRAULIC ANALYSIS OF CONSOLIDATED SPENT PWR FUEL RODS. FINAL REPORT. (EPRI ; EPRI-NP-3764)

THERMAL-HYDRAULIC ANALYSIS OF CONSOLIDATED SPENT PWR FUEL RODS. FINAL REPORT. (EPRI ; EPRI-NP-3764)
紙図書
CUTA, J.M.(et al.)Electric Power Research Institute(Electric Power Research Institute)1984.
全国の図書館
  • 著者標目CUTA, J.M.

PEGASUS: A MULTI-MEGAWATT NUCLEAR ELECTRIC PROPULSION SYSTEM (CONF ; CONF-860102-10)

PEGASUS: A MULTI-MEGAWATT NUCLEAR ELECTRIC PROPULSION SYSTEM (CONF ; CONF-860102-10)
紙図書
1985.
全国の図書館

COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems ; Programmers' Manual (NUREG ; NUREG/CR-3046-VOL.5; PNL-4385-VOL.5)

COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems ; Programmers' Manual (NUREG ; NUREG/CR-3046-VOL.5; PNL-4385-VOL.5)
紙図書
Koontz, A.S./Cuta, J.M.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
全国の図書館
  • 著者標目Koontz, A.S. Cuta, J.M.