Department of Energy's team's analyses of Soviet designed VVERs

Technical Report · Fri Sep 01 00:00:00 EDT 1989

DOI:https://doi.org/10.2172/6527859· OSTI ID:6527859

This document provides Appendices A thru K of this report. The topics discussed respectively are: radiation induced embrittlement and annealing of reactor pressure vessel steels; loss of coolant accident blowdown analyses; LOCA blowdown response analyses; non-seismic structural response analyses; seismic analyses; S'' seal integrity; reactor transient analyses; fire protection; aircraft impacts; and boric acid induced corrosion. (FI).

• Research Organization: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (USA)
• Sponsoring Organization: DOE/NE
• OSTI ID: 6527859
• Report Number(s): DOE/NE-0086-Rev.1-Anal.App.; ON: DE91002401
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AIRCRAFT
IMPACT SHOCK
PRESSURE VESSELS
ANNEALING
EMBRITTLEMENT
STEELS
WWER TYPE REACTORS
LOSS OF COOLANT
REACTOR MATERIALS
REACTOR SAFETY
SEISMIC EFFECTS
BLOWDOWN
BORIC ACID
CORROSION
FIRES
HEAT TRANSFER
HYDRAULICS
MECHANICAL VIBRATIONS
RADIATION EFFECTS
SEALS
TRANSIENTS
USSR
ACCIDENTS
ALLOYS
ASIA
CHEMICAL REACTIONS
CONTAINERS
EASTERN EUROPE
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EUROPE
FLUID MECHANICS
HEAT TREATMENTS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties