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Reactor physics data for safety analysis of CANFLEX-NU CANDU-6 core

Abstract

This report contains the reactor physics data for safety analysis of CANFLEX-NU fuel CANDU-6 core. First, the physics parameters for time-average core have been described, which include the channel power and maximum bundle power map, channel axial power shape and bundle burnup. And, next the data for fuel performance such as relative ring power distribution and bundle burnup conversion ratio are represented. The transition core data from 0 to 900 full power day are represented by 100 full power day interval. Also, the data for reactivity devices of time-average core and 300 full power day of transition core are given.
Publication Date:
Aug 01, 2001
Product Type:
Technical Report
Report Number:
KAERI/TR-1899/2001
Resource Relation:
Other Information: 2 tabs; PBD: Aug 2001
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; CANDU TYPE REACTORS; CONVERSION RATIO; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; NUMERICAL DATA; POWER DISTRIBUTION; REACTOR CORES; SAFETY ANALYSIS
OSTI ID:
20305732
Research Organizations:
Korea Atomic Energy Research Institute, Taejon, (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
TRN: KR0202716066896
Availability:
Available from INIS in electronic form
Submitting Site:
KRN
Size:
223 pages
Announcement Date:

Citation Formats

Jeong, Chang Joon, and Suk, Ho Chun. Reactor physics data for safety analysis of CANFLEX-NU CANDU-6 core. Korea, Republic of: N. p., 2001. Web.
Jeong, Chang Joon, & Suk, Ho Chun. Reactor physics data for safety analysis of CANFLEX-NU CANDU-6 core. Korea, Republic of.
Jeong, Chang Joon, and Suk, Ho Chun. 2001. "Reactor physics data for safety analysis of CANFLEX-NU CANDU-6 core." Korea, Republic of.
@misc{etde_20305732,
title = {Reactor physics data for safety analysis of CANFLEX-NU CANDU-6 core}
author = {Jeong, Chang Joon, and Suk, Ho Chun}
abstractNote = {This report contains the reactor physics data for safety analysis of CANFLEX-NU fuel CANDU-6 core. First, the physics parameters for time-average core have been described, which include the channel power and maximum bundle power map, channel axial power shape and bundle burnup. And, next the data for fuel performance such as relative ring power distribution and bundle burnup conversion ratio are represented. The transition core data from 0 to 900 full power day are represented by 100 full power day interval. Also, the data for reactivity devices of time-average core and 300 full power day of transition core are given.}
place = {Korea, Republic of}
year = {2001}
month = {Aug}
}