PWR Program Progress Rpt [Sep 9 - Oct 20, 1955]...

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PWR Program Progress Rpt [Sep 9 - Oct 20, 1955] [declassified]

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Որքա՞ն է ձեզ դուր եկել այս գիրքը:

Ինչպիսի՞ն է բեռնված ֆայլի որակը:

Բեռնեք գիրքը` գնահատելու դրա որակը

Ինչպիսի՞ն է բեռնված ֆայլերի որակը:

Տարի:

1955

Հրատարակչություն:

US AEC

Լեզու:

english

Էջեր:

95

Ֆայլ:

PDF, 6.28 MB

IPFS:

,

english, 1955

Կարդալ Առցանց

Ներբեռնել (pdf, 6.28 MB)

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Ձեզ կարող է հետաքրքրել

J.N. Lillington — Light Water Reactor Safety: The Development of Advanced Models and Codes for Light Water Reactor Safety Analysis

G.F. Hewitt, John G. Collier — Introduction to Nuclear Power (Series in Chemical and Mechanical Engineering)

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. 7. Power Reactors (Supplement to Vol. 4)

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

— Radiation Effects Review Meeting

— Advanced Post-Irradiation Exam Tech for Water-Reactor Fuel (IAEA TECDOC-1277)

— Behavior of LWR Core Materials Under Accident Conditions (IAEA TECDOC-921)

— Behavior of Water Reactor Fuel Elements Under Accident Conditions (csni77-13)

— Corrosion of Zr Alloys in Nuclear Powerplants (IAEA TECDOC-684)

— Devel., Props. of U-Base Alloys Corrosion-Resistant in High-Temp Water Part IV [declassified]

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— Fuels (nuclear) Development Operations [Jul-Sep 1959] [Declassified]

— Fuels [nuclear] Development Operation [qtrly rpt, Apr-Jun 1961] [declassified]

— Fuels [nuclear] Development Operation [qtrly rpt, Jan-Mar 1961] [declassified]

— In-Vessel Core Degradation [validation martrix] (csni-r2000-21)

— PWR Program Progress Rpt [Dec 2 1955 - Jan 12 1956] [declassified]

— PWR Program Progress Rpt [Jul 15, 1954 - Aug 26, 1954] [declassified]

— Reactor and Materials Tech Monthly Rpt [May, 1965] [Declassified]

— Reactor Engineering Division Qtrly Rpt [Apr-Jun 1954] [Declassified]

— Resume of Uranium Alloy Data - X [declassified]

— Strategic Nuclear Research Collaboration [1999 Annual Rpt]

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

— Thermo-Hydraulic Codes for VVER LOCA and Transients (csni-r2001-4)

— Uranium Alloys - Prep., Fabrication as Zircaloy-2 Clad Fuel Rods [declassified]

— VVER-Specific Features [core degradation] (csni-r98-20)

— Water Reactor Safety Info Meeting Vol 2 [22nd, transactions]

— Zircalloy Clad [nuclear] Fuel Analysis

U.S. Atomic Energy Commission — Fuel elements conference : Paris, November 18-23, 1957 book 1

International Atomic Energy Agency — Fuel failure in normal operation of water reactors : experience, mechanisms and management : proceedings of a Technical Committee meeting held in Dimitrovgrad, Russian Federation, 26-29 May 1992

International Atomic Energy Agency — Technical aspects of high converter reactors : proceedings of a Technical Committee meeting held in Nuremberg, 26-29 March 1990

T J Haste; K Trambauer; OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations — Degraded core quench : summary of progress, 1996-1999 : executive summary

Oak Ridge National Laboratory.; Union Carbide Corporation.; U.S. Atomic Energy Commission — Homogeneous reactor project quarterly progress report for the period ending

Nuclear Energy Agency Committee on the Safety of Nuclear Installations — In-vessel core degradation code validation matrix

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