Materials testing reactor project handbook

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Materials testing reactor project...

Materials testing reactor project handbook

John Henry Buck, Carl F Leyse, Argonne National Laboratory., Oak Ridge National Laboratory

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کال:

1951

خپرندویه اداره:

Oak Ridge, Tenn., United States Atomic Energy Commission, Technical Information Service, [1955?]

ژبه:

english

صفحه:

569

لړ (سلسله):

U.S. Atomic Energy Commission. TID-7001; TID, 7001

فایل:

PDF, 38.88 MB

IPFS:

,

english, 1951

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کاپی کول (pdf, 38.88 MB)

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ممکن تاسی علاقمند شی

H.R.McK HYDER — REACTORS VOL 2

IAEA — Directory of Nuclear Reactors, Volume 1. Power Reactors

IAEA — Directory of Nuclear Reactors, Vol. 4. Power Reactors (Revised and Supplemented Edition of Vol. 1)

IAEA — Directory of Nuclear Reactors, Vol. 5. Research, Test and Experimental Reactors (Supplement to Vols. 2 and 3)

IAEA — Directory of Nuclear Reactors, Vol. 6. Research, Test and Experimental Reactors (Supplement to Vol. 2, 3 and 5)

IAEA — Directory of Nuclear Reactors, Vol. 7. Power Reactors (Supplement to Vol. 4)

IAEA — Directory of Nuclear Reactors

IAEA — Directory of Nuclear Reactors, Vol. 9. Power Reactors (Supplement to Vol. 4 and 7)

various — Beam-Hole Flux Monitors [declassified]

— Crit Exper, Physics Calcs for Low-Enriched, Hi-temp Gas Cooled Reactors (IAEA TECDOC-1249)

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— Neutron Sources and Their Appls [ANS Meeting Apr 19-21, 1971 - Sssions I, II]

— Neutronic Methods, Models - Adv Neutron Src Reactor [3-element core]

— NPR Reactor Hazards Review Vol 1 (phase 1 - production) [declassified]

— Nuclear Reactor Tech Manual (Physics Section, 100-N) Vol 1 [draft] [Declassified] -

— Prelim Fracture Analysis - Core Pressure Boundary Tube - ANS Reactor

— Prelim Safety Rpt - Std MHTGR Vol 1

— Reactor Design, Feasability - High Flux Research Reactor

— System 80+ Standard [nucl. powerplnt] Design - Vol 04

McLain, H.A.; Oak Ridge National Laboratory.; United States. Dept. of Energy. Office of Scientific and Technical Information — HFIR FUEL ELEMENT STEADY STATE HEAT TRANSFER ANALYSIS. REVISED VERSION

L. L. Taylor; H. H. Loo; USDOE Office of Environmental Management (EM) (US); Idaho National Engineering and Environmental Laboratory.; United States. Dept. of Energy. Office of Scientific and Technical Information — Shippingport LWBR (Th

Max Weber; U.S. Atomic Energy Commission. Division of Reactor Development and Technology — Status of LMFBR reheat in Western Europe, 1972 : report of the United States of America LMFBR Sodium Reheat Team visit to France, Germany (FRG), Netherlands, and United Kingdom, May 22-June 6, 1972

Oak Ridge National Laboratory. Metallurgy Division.; Union Carbide Corporation — Metallurgy Division annual progress report for period ending

Robertson, R.C.; Oak Ridge National Laboratory.; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information — MSRE DESIGN AND OPERATIONS REPORT. PART I. DESCRIPTION OF REACTOR DESIGN

Brian L Koponen — Nuclear criticality safety experiments, calculations, and analyses, 1958 to 1982 : compilation of papers from the Transactions of the American Nuclear Society

E H Lockwood; General Electric Company.; U.S. Atomic Energy Commission.; Hanford Atomic Products Operation — Reactor physics primer

M.A. Schultz — Control of nuclear reactors and power plants

— Research Reactor Fuel Management 4 (RRFM 2000)

— Research Reactor Fuel Management 7 (RRFM 2003)

— Proceeding International Group on Research Reactor 2 (IGORR 1992)

— Proceeding International Group on Research Reactor 3 (IGORR 1993)

— Proceeding International Group on Research Reactor 7 (IGORR 1999)

John R. Lamarsh — Introduction to Nuclear Reactor Theory

— Nuclear Physics and Reactor Theory. Module 1. Atomic and Nuclear Physics

— The Nuclear Physics and Reactor Theory Handbook

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