Prelim Safety Rpt - Std MHTGR Vol 1

Main
Prelim Safety Rpt - Std MHTGR Vol 1

Prelim Safety Rpt - Std MHTGR Vol 1

0 / 0

Πόσο σας άρεσε αυτό το βιβλίο;

Ποια είναι η ποιότητα του ληφθέντος αρχείου;

Κατεβάστε το βιβλίο για να αξιολογήσετε την ποιότητά του

Ποια είναι η ποιότητα των ληφθέντων αρχείων;

Έτος:

1989

Εκδότης:

US DOE

Γλώσσα:

english

Σελίδες:

471

Αρχείο:

PDF, 15.24 MB

IPFS:

,

english, 1989

Διαβάστε online

Η μετατροπή σε βρίσκεται σε εξέλιξη

Η μετατροπή σε απέτυχε

Ίσως σας ενδιαφέρει

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. 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)

— Graphite Design Handbook

Charles W. Forsberg — [Article] A Large Low-Pressure Advanced High-Temperature Reactor

— Accid. Anal. - Nucl. Powerplants w. Graphite-Moderated BW RBMK Reactors

— Design of the Reactor Core for Nuclear Powerplants (IAEA NS-G-1.12)

— Design, Devel of Gas-Cooled Reactor w Closed-Cycle Gas Turbines (IAEA TECDOC-899)

— Design, Devel Status of Small and Medium Reactor Systems (IAEA TECDOC-881)

— Feasibility Study - Supercritical LWRs for Electrical Power Prodn

— How Large can Reactors be Built Without Possib. of Core-Melt Accicent [pres. slides]

— HTGR - Graphite Technology Development Plan

— Making Core-Melt Accidents Impossible in a Large Reactor [pres. slides]

— Metals Design Handbook

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

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

— Safety Evaluation Rpt - PRISM Liquid-Metal Reactor

— Standard Tech Specs - Babcock & Wilcox Plants Vol 1

— Status, Future Devel. of Modular HTGR Technology (IAEA TECDOC-1198)

— System 80+ Standard [nucl. powerplnt] Design - Vol 02

— Tech Feas, Reliability of Passive Safety Systems for Nucl Powerplants (IAEA TECDOC-920)

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

International Atomic Energy Agency — Gas turbine power conversion systems for modular HTGRs : report of a technical committee meeting held in Palo Alto, United States of America, 14-16 November 2000

M. Ishii; S. T. Revankar; U. S. Rohatgi; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Purdue University.; Brookhaven National Laboratory.; United States. Dept. of Energy. Oakland Operations Of — MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

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

J C Cleveland; J C Conklin; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Oak Ridge National Laboratory — High temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research quarterly progress report, April 1-June 30, 1979

John Henry Buck; Carl F Leyse; Argonne National Laboratory.; Oak Ridge National Laboratory — Materials testing reactor project handbook

Badulescu A. et al. — Liquid Metal Cooled Reactors: Experience in Design and Operation

Kuznetcov V. — Design Features to Achieve Defence in Depth in Small and Medium Sized Reactors

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

Φράσεις κλειδιά