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Nuclear design report for Kori nuclear power plant unit 1, cycle 14

Abstract

This report presents nuclear design calculations for cycle 14 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 14 amounts to 366 EFPD corresponding to a cycle burnup of 13680 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs. nozzle by vortex formation during mid-loop operation condition are experimentally investigated. The critical submergence is determined for various types of suction nozzle, and the measurements of velocity distribution are performed in the flow fields near the t-shaped suction nozzle. (Author) 11 refs., 41 figs., 13 tabs.
Authors:
Park, Chan Oh; Kim, Joo Young; Park, Sang Yoon; Song, Jae Woong; Lee, Chong Chul; Baik, Joo Hyun [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Jun 01, 1994
Product Type:
Technical Report
Report Number:
KAERI-TR-443/94
Reference Number:
SCA: 210200; PA: AIX-26:060191; EDB-95:129096; ERA-20:025843; NTS-96:006337; SN: 95001462362
Resource Relation:
Other Information: PBD: Jun 1994
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR FUELING; CONTROL ROD WORTHS; FUEL ASSEMBLIES; NUCLEAR POWER PLANTS; POWER DENSITY; POWER DISTRIBUTION; REACTIVITY COEFFICIENTS
OSTI ID:
103207
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96600701; TRN: KR9500057060191
Availability:
INIS; OSTI as DE96600701
Submitting Site:
KRN
Size:
120 p.
Announcement Date:
Oct 11, 1995

Citation Formats

Park, Chan Oh, Kim, Joo Young, Park, Sang Yoon, Song, Jae Woong, Lee, Chong Chul, and Baik, Joo Hyun. Nuclear design report for Kori nuclear power plant unit 1, cycle 14. Korea, Republic of: N. p., 1994. Web.
Park, Chan Oh, Kim, Joo Young, Park, Sang Yoon, Song, Jae Woong, Lee, Chong Chul, & Baik, Joo Hyun. Nuclear design report for Kori nuclear power plant unit 1, cycle 14. Korea, Republic of.
Park, Chan Oh, Kim, Joo Young, Park, Sang Yoon, Song, Jae Woong, Lee, Chong Chul, and Baik, Joo Hyun. 1994. "Nuclear design report for Kori nuclear power plant unit 1, cycle 14." Korea, Republic of.
@misc{etde_103207,
title = {Nuclear design report for Kori nuclear power plant unit 1, cycle 14}
author = {Park, Chan Oh, Kim, Joo Young, Park, Sang Yoon, Song, Jae Woong, Lee, Chong Chul, and Baik, Joo Hyun}
abstractNote = {This report presents nuclear design calculations for cycle 14 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 14 amounts to 366 EFPD corresponding to a cycle burnup of 13680 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs. nozzle by vortex formation during mid-loop operation condition are experimentally investigated. The critical submergence is determined for various types of suction nozzle, and the measurements of velocity distribution are performed in the flow fields near the t-shaped suction nozzle. (Author) 11 refs., 41 figs., 13 tabs.}
place = {Korea, Republic of}
year = {1994}
month = {Jun}
}