Published 1977 | Version v1
Journal article

Russian approach to nuclear reactor safety

Creators

  • 1. Oak Ridge National Lab., TN

Description

Soviet reactor and power-station design initially proceeded from a safety philosophy that did not acknowledge a loss-of-coolant accident caused by a double-ended pipe break nor a massive core meltdown as credible eventualities to be considered in the design of systems and details. Generally, engineered safeguards and conservatism in design have been regarded as adequate insurance against accidents that could escalate to a point where there is significant radiation damage to either plant personnel or the public. Recently, there has been some change in the attitude of scientists toward secondary containment in pressurized-water-reactor plants. In pressure-tube boiling-water reactors and liquid-metal-cooled fast breeder reactors, Soviet experience on several demonstration and ''semicommercial'' units has been interpreted to mean that core damage propagation and accidents involving large energy releases are not credible. It appears, however, that there is not complete unanimity on all safety questions and greater dispersion of authority and more formal safety reviews seem to be in the making

Additional details

Publishing Information

Journal Title
Nucl. Saf.
Journal Volume
18
Journal Issue
4
Series
Nucl. Saf.
Journal Page Range
438-450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8343481
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
HUMAN POPULATIONS; NUCLEAR POWER PLANTS; PLANNING; REACTOR SAFETY; REACTOR SITES; USSR
Descriptors DEC
EUROPE; NUCLEAR FACILITIES; POPULATIONS; POWER PLANTS; SAFETY; THERMAL POWER PLANTS