「"Morris, D. G."」の検索結果 | NDLサーチ

検索結果 25 件

タイトルでまとめる

Thermal analysis to support decommissioning of the molten salt reactor experiment ORNL/TM-13026 DE96 011585

マイクロ規格・テクニカルリポート類

Sulfredge, C. D, Morris, D. G, Park, J. E, Williams, P. T1996<LS-DE96/011585>

国立国会図書館

Description of TASHA: Thermal Analysis of Steady-State-Heat Transfer for the Advanced Neutron Source Reactor ORNL/TM-13082 DE97 051256

マイクロ規格・テクニカルリポート類

Morris, D. G, Chen, N. C, Nelson, W. R, Yoder, G. L1996<LS-DE97/051256>

国立国会図書館

Intermetallics and superalloys

紙図書

D.G. Morris, S. Naka, P. Caron (Editors)Wiley-Vch2000

全国の図書館

著者標目Morris, D. G.

Mechanical behaviour of nanostructured materials

紙図書

D.G. MorrisTrans Tech Publicationsc1998

全国の図書館

DESCRIPTION OF TASHA: THERMAL ANALYSIS OF STEADY-STATE-HEAT TRANSFER FOR THE ADVANCED NEUTRON SOUR REACTOR. (ORNL ; ORNL/TM-13082; DE97051256)

紙図書

MORRIS, D.G.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1996.

全国の図書館

UPDATE TO ADVANCED NEUTRON SOURCE STEADY-STATE THERMAL-HYDRAULIC REPORT (ORNL ; ORNL/TM-12398/R1)

紙図書

YODER, G.L.// CARBAJO, J.J.// MORRIS, D.G.// NELSON, W.R. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))Oak Ridge National Laboratory(Oak Ridge National Laboratory)1996.

全国の図書館

HIGH FLUX ISOTOPE REACTOR SYSTEM RELAP5 INPUT MODEL. (ORNL ; ORNL/TM-11647)

紙図書

MORRIS, D.G.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1993.

全国の図書館

THERMAL-HYDRAULIC SIMULATION OF NATURAL CONVECTION DECAY HEAT REMOVAL IN THE HIGH FLUX ISOTOPE REACTOR USING RELAP5 AND TEMPEST. (CONF ; CONF-890173-2)

紙図書

MORRIS, D.G.(et al.)1989.

全国の図書館

THERMAL-HYDRAULIC ANALYSIS OF THE HFIR (HIGH FLUX ISOTOPE REACTOR) (CONF ; CONF-900608-43)

紙図書

MORRIS, D.G.// RUGGLES, A.E.// WENDEL, M.W. (OAK RIDGE NATIONAL LAB., TN (USA))1990.

全国の図書館

DEVELOPMENT OF ENCAPSULATED LITHIUM HYDRIDE SINK-SIDE THERMAL ENERGY STORAGE FOR PULSED SPACE POWER SYSTEMS. (CONF ; CONF-880676-1)

紙図書

MORRIS, D.G.(et al.)1988.

全国の図書館

DEVELOPMENT OF ENCAPSULATED LITHIUM HYDRIDE THERMAL ENERGY STORAGE FOR SPACE POWER SYSTEMS. (ORNL ; ORNL/TM-10413)

紙図書

MORRIS, D.G.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1987.

全国の図書館

ENERGY STORAGE FOR NUCLEAR BURST POWER SYSTEMS. (CONF ; CONF-880122-3)

紙図書

MORRIS, D.G.(et al.)1987.

全国の図書館

ANALYSIS OF TRANSIENT FILM BOILING OF HIGH-PRESSURE WATER IN A ROD BUNDLE. (NUREG ; NUREG/CR-2469; ORNL/NUREG-85)

紙図書

MORRIS, D.G.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.

全国の図書館

DISPERSED FLOW FILM BOILING OF HIGH PRESSURE WATER IN A ROD BUNDLE. (NUREG ; NUREG-CR-2183)

紙図書

MORRIS, D.G.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.

全国の図書館

Dispersed Flow Film Boiling in Rod Bundle Geometry - Steady State Heat Transfer Data and Correlation Comparisons (NUREG ; NUREG/CR-2435; ORNL-5822)

紙図書

Yoder, G.L./Morris, D.G.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.

全国の図書館

TRANSIENT DISPERSED FLOW FILM BOILING OF HIGH PRESSURE WATER IN ROD BUNDLE GEOMETRY. (CONF ; CONF-810804-27)

紙図書

MORRIS, D.G.(et al.)1981.

全国の図書館

THERMAL-HYDRAULIC/HEAT TRANSFER CODE DEVELOPMENT FOR SPHERE-PAC-FUELED LMFBRS. (ORNL ; ORNL-TM-7100)

紙図書

MORRIS, D.G.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1980.

全国の図書館

Recovery of a Creep-deformed Type 316 stainless steel (AERE ; AERE-R-9233)

紙図書

Morris, D.G./Harries, D.R.Atomic Energy Research Establishment(Atomic Energy Research Establishment)1978.

全国の図書館

Creep in a type 316 stainless steel (AERE ; AERE-R-8605)

紙図書

Morris, D.G,Atomic Energy Research Establishment(Atomic Energy Research Establishment)1976.

全国の図書館

MASSIVE PARTICLE FORMATION IN A TYPE 316 STAINLESS STEEL DURING CREEP. (AERE ; AERE-M-2842)

紙図書

MORRIS, D.G.(et al.)Atomic Energy Research Establishment(Atomic Energy Research Establishment)1976.

全国の図書館

RSS