Published 2007 | Version v1
Miscellaneous Metadata-only

Development of a web-based CANDU core management procedures automation system

Creators

  • 1. Inst. for Advanced Engineering (IAE), Yongin (Korea, Republic of)
  • 2. Korea Hydro and Nuclear Power (KHNP), Wolsong (Korea, Republic of)

Description

Introduce CANDU core management procedures automation system (COMPAS) - A web-based application which semi-automates several CANDU core management tasks. It provides various functionalities including selection and evaluation of refueling channel, detector calibration, coolant flow estimation and thermal power calculation through automated interfacing with analysis codes (RFSP, NUCIRC, etc.) and plant data. It also utilizes brand new .NET computing technology such as ASP.NET, smart client, web services and so on. Since almost all functions are abstracted from the previous experiences of the current working members of the Wolsong Nuclear Power Plant (NPP), it will lead to an efficient and safe operation of CANDU plants. (author)

Part of:
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-88-7
Imprint Title
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference
Imprint Pagination
303 Megabytes
Journal Page Range
[16 p.]

Conference

Title
Canada's nuclear renewal and growth
Acronym
28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future
Dates
3-6 Jun 2007
Place
Saint John, New Brunswick (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
38107429
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; COOLANT LOOPS; FUEL CHANNELS; KAERI; REACTOR CORES
Descriptors DEC
COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
Paper T5001; 5 refs., 3 tabs., 14 figs.