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検索結果 12 件

Archaean supracrustal sequences of Dharwar Craton, southern India

Archaean supracrustal sequences of Dharwar Craton, southern India
デジタル文書・図像類
外田, 智千, 堀江, 憲路, M., Satish-Kumar, 上野, 雄一郎, A., Nasheeth, 三島, 郁, 白石, 和行, Hokada, T., Horie, K., Satish-Kumar, M., Ueno, Y., Nasheeth, A., Mishima, K., Shiraishi, K.2013-11-15
全国の図書館
  • 著者標目.... Nasheeth, A. Mishima, K. Shiraishi, K.

THERMAL-HYDRAULIC ANALYSIS FOR CORE CONVERSION TO THE USE OF LOW-ENRICHED URANIUM FUELS IN THE KUR. (KURRI ; KURRI-TR-258)

THERMAL-HYDRAULIC ANALYSIS FOR CORE CONVERSION TO THE USE OF LOW-ENRICHED URANIUM FUELS IN THE KUR. (KURRI ; KURRI-TR-258)
紙図書
MISHIMA, K.(et al.)1984.
全国の図書館
  • 著者標目MISHIMA, K.

FLOW REGIME TRANSITION CRITERIA CONSISTENT WITH TWO-FLUID MODEL FOR VERTICAL TWO-PHASE FLOW. (NUREG ; NUREG/CR-3338; ANL-83-42)

FLOW REGIME TRANSITION CRITERIA CONSISTENT WITH TWO-FLUID MODEL FOR VERTICAL TWO-PHASE FLOW. (NUREG ; NUREG/CR-3338; ANL-83-42)
紙図書
Mishima, K./Ishii, M.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
全国の図書館
  • 著者標目Mishima, K. Ishii, M.

THERMAL-HYDRAULIC CALCULATIONS FOR KUHFR WITH REDUCED ENCRICHMENT URANIUM FUEL. (KURRI ; KURRI-TR-223)

THERMAL-HYDRAULIC CALCULATIONS FOR KUHFR WITH REDUCED ENCRICHMENT URANIUM FUEL. (KURRI ; KURRI-TR-223)
紙図書
MISHIMA, K.(et al.)1982.
全国の図書館
  • 著者標目MISHIMA, K.

Critical heat-flux experiments under low-flow conditions in a vertical annulus. (NUREG ; NUREG/CR-2647; ANL-82-6)

Critical heat-flux experiments under low-flow conditions in a vertical annulus. (NUREG ; NUREG/CR-2647; ANL-82-6)
紙図書
Mishima, K./Ishii, M.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
全国の図書館
  • 著者標目Mishima, K. Ishii, M.

FLOW TEST FOR THE FULL SCALE CORE MOCKUP OF THE KUHFR, (1). (IN JAPANESE) (KURRI ; KURRI-TR-216)

FLOW TEST FOR THE FULL SCALE CORE MOCKUP OF THE KUHFR, (1). (IN JAPANESE) (KURRI ; KURRI-TR-216)
紙図書
MISHIMA, K.(et al.)京都大学原子炉実験所(キョウト ダイガク ゲンシロ ジッケンジョ)1981.
全国の図書館
  • 著者標目MISHIMA, K.

FLOW TEST FOR THE FULL SCALE CORE MOCK-UP TO THE KUHFR, (2). (IN JAPANESE) (KURRI ; KURRI-TR-224)

FLOW TEST FOR THE FULL SCALE CORE MOCK-UP TO THE KUHFR, (2). (IN JAPANESE) (KURRI ; KURRI-TR-224)
紙図書
MISHIMA, K.(et al.)京都大学原子炉実験所(キョウト ダイガク ゲンシロ ジッケンジョ)1981.
全国の図書館
  • 著者標目MISHIMA, K.

STUDY OF TWO-FLUID MODEL AND INTERFACIAL AREA (NUREG ; NUREG/CR-1873; ANL-80-111)

STUDY OF TWO-FLUID MODEL AND INTERFACIAL AREA (NUREG ; NUREG/CR-1873; ANL-80-111)
紙図書
Ishii, M./Mishima, K.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
全国の図書館
  • 著者標目Ishii, M. Mishima, K.

WATER FLOW CHARACTERISTICS OF BAUMKUCHEN TYPE FUEL ELEMENTS FOR KYOTO UNIVERSITY HIGH NEUTRON FLUX REACTOR. (IN JAPANESE) (KURRI ; KURRI-TR-196)

WATER FLOW CHARACTERISTICS OF BAUMKUCHEN TYPE FUEL ELEMENTS FOR KYOTO UNIVERSITY HIGH NEUTRON FLUX REACTOR. (IN JAPANESE) (KURRI ; KURRI-TR-196)
紙図書
MISHIMA, K.(et al.)1979.
全国の図書館
  • 著者標目MISHIMA, K.

EXPERIMENTAL STUDY ON NATURAL-CONVECTION BOILING BURNOUT IN AN ANNULUS. (CONF ; CONF-820901-8)

EXPERIMENTAL STUDY ON NATURAL-CONVECTION BOILING BURNOUT IN AN ANNULUS. (CONF ; CONF-820901-8)
紙図書
MISHIMA, K.
全国の図書館
  • 著者標目MISHIMA, K.

FLOW REGIME TRANSITION CRITERIA CONSISTENT WITH TWO-FLUID MODEL FOR VERTICAL TWO-PHASE FLOW. (ANL ; ANL-83-42)

FLOW REGIME TRANSITION CRITERIA CONSISTENT WITH TWO-FLUID MODEL FOR VERTICAL TWO-PHASE FLOW. (ANL ; ANL-83-42)
紙図書
MISHIMA, K.Argonne National Laboratory(Argonne National Laboratory)
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  • 著者標目MISHIMA, K.

CRITICAL HEAT FLUX EXPERIMENTS UNDER LOW FLOW CONDITIONS IN A VERTICAL ANNULUS. (ANL ; ANL-82-6)

CRITICAL HEAT FLUX EXPERIMENTS UNDER LOW FLOW CONDITIONS IN A VERTICAL ANNULUS. (ANL ; ANL-82-6)
紙図書
MISHIMA, K.Argonne National Laboratory(Argonne National Laboratory)
全国の図書館
  • 著者標目MISHIMA, K.

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