Published 1996 | Version v1
Book Metadata-only

A comprehensive study on the thermal movement of the reactor coolant system for Korea Standard Nuclear Power Plant

Creators

  • 1. Korea Atomic Energy Research Inst., Taejeon (Korea, Republic of). Dept. of Mechanical Engineering
  • 2. ABB Combustion Engineering, Windsor, CT (United States). Dept. of Mechanical Engineering

Description

The specific thermal pattern of each component of the reactor coolant system (RCS) is a basic design parameter for the establishment of the RCS arrangement and support system. Development of an effective method to analyze the global behavior of thermal movement of the RCS is required for design process. In this paper a fundamental but reliable and comprehensive method of obtaining thermal movement of the Korea Standard Nuclear Power Plant (KSNPP) is presented. Experimental results are included to illustrate the validity of the analyses

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1780-6
Imprint Title
Integrity of structures, and fluid systems, hazardous release protection, piping and pipe supports, and pumps and valves. PVP-Volume 333
Imprint Pagination
267 p.
Journal Page Range
p. 27-33.

Conference

Title
American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
21-26 Jul 1996.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28019030
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REPUBLIC OF KOREA; SYSTEMS ANALYSIS; THEORETICAL DATA; THERMAL ANALYSIS; THERMAL EXPANSION
Descriptors DEC
ASIA; COOLING SYSTEMS; DATA; DEVELOPING COUNTRIES; ENRICHED URANIUM REACTORS; EXPANSION; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-960706--.