Published 1976 | Version v1
Book Metadata-only

Reactor protective system for Rajasthan Atomic Power Project

Creators

  • 1. Rajasthan Atomic Power Station, Kota (India)
  • 2. Department of Atomic Energy, Bombay (India). Power Projects Engineering Div.

Description

Design aspects of the reactor protective system for the Rajasthan Atomic Power Station are outlined. The system operates causing the reactor to trip in case the reactor power exceeds the design limit. The reliability of the system is evaluated. The problems encountered in the reactor operation and the methods adopted to solve them are enumerated. (A.K.)

Additional details

Publishing Information

Publisher
Department of Atomic Energy.
Imprint Place
Bombay
Imprint Title
Symposium on nuclear reactor instrumentation [held at] Bombay [during] December 20-23, 1976 [papers]
Journal Page Range
p. 138-141.

Conference

Title
Symposium on nuclear reactor instrumentation.
Dates
20 - 23 Dec 1976.
Place
Bombay, India.

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
9389769
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
RAJASTHAN-1 REACTOR; RAJASTHAN-2 REACTOR; REACTOR INSTRUMENTATION; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; RELIABILITY
Descriptors DEC
CANDU TYPE REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; OPERATION; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; THERMAL REACTORS