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Conceptual study of advanced PWR core design

Abstract

The purpose of this project is for developing and verifying the core design concepts with enhanced safety and economy, and associated methodologies for core analyses. From the study of the sate-of-art of foreign advanced reactor cores, we developed core concepts such as soluble boron free, high convertible and enhanced safety core loaded semi-tight lattice hexagonal fuel assemblies. To analyze this hexagonal core, we have developed and verified some neutronic and T/H analysis methodologies. HELIOS code was adopted as the assembly code and HEXFEM code was developed for hexagonal core analysis. Based on experimental data in hexagonal lattices and the COBRA-IV-I code, we developed a thermal-hydraulic analysis code for hexagonal lattices. Using the core analysis code systems developed in this project, we designed a 600 MWe core and studied the feasibility of the core concepts. Two additional scopes were performed in this project : study on the operational strategies of soluble boron free core and conceptual design of large scale passive core. By using the axial BP zoning concept and suitable design of control rods, this project showed that it was possible to design a soluble boron free core in 600 MWe PWR. The results of large scale core design showed  More>>
Publication Date:
Sep 01, 1997
Product Type:
Technical Report
Report Number:
KAERI/RR-1715/96
Reference Number:
SCA: 210200; PA: AIX-29:000862; EDB-98:048781; SN: 98001898870
Resource Relation:
Other Information: PBD: Sep 1997
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BORON; C CODES; HEXAGONAL LATTICES; NUCLEAR FUELS; POWER RANGE 100-1000 MW; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY
OSTI ID:
595410
Research Organizations:
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE98607827; TRN: KR9700291000862
Availability:
INIS; OSTI as DE98607827
Submitting Site:
KRN
Size:
336 p.
Announcement Date:

Citation Formats

Kim, Young Jin, Chang, Moon Hee, Kim, Keung Ku, Joo, Hyung Kuk, Kim, Young Il, Noh, Jae Man, Hwang, Dae Hyun, Kim, Taek Kyum, and Yoo, Yon Jong. Conceptual study of advanced PWR core design. Korea, Republic of: N. p., 1997. Web.
Kim, Young Jin, Chang, Moon Hee, Kim, Keung Ku, Joo, Hyung Kuk, Kim, Young Il, Noh, Jae Man, Hwang, Dae Hyun, Kim, Taek Kyum, & Yoo, Yon Jong. Conceptual study of advanced PWR core design. Korea, Republic of.
Kim, Young Jin, Chang, Moon Hee, Kim, Keung Ku, Joo, Hyung Kuk, Kim, Young Il, Noh, Jae Man, Hwang, Dae Hyun, Kim, Taek Kyum, and Yoo, Yon Jong. 1997. "Conceptual study of advanced PWR core design." Korea, Republic of.
@misc{etde_595410,
title = {Conceptual study of advanced PWR core design}
author = {Kim, Young Jin, Chang, Moon Hee, Kim, Keung Ku, Joo, Hyung Kuk, Kim, Young Il, Noh, Jae Man, Hwang, Dae Hyun, Kim, Taek Kyum, and Yoo, Yon Jong}
abstractNote = {The purpose of this project is for developing and verifying the core design concepts with enhanced safety and economy, and associated methodologies for core analyses. From the study of the sate-of-art of foreign advanced reactor cores, we developed core concepts such as soluble boron free, high convertible and enhanced safety core loaded semi-tight lattice hexagonal fuel assemblies. To analyze this hexagonal core, we have developed and verified some neutronic and T/H analysis methodologies. HELIOS code was adopted as the assembly code and HEXFEM code was developed for hexagonal core analysis. Based on experimental data in hexagonal lattices and the COBRA-IV-I code, we developed a thermal-hydraulic analysis code for hexagonal lattices. Using the core analysis code systems developed in this project, we designed a 600 MWe core and studied the feasibility of the core concepts. Two additional scopes were performed in this project : study on the operational strategies of soluble boron free core and conceptual design of large scale passive core. By using the axial BP zoning concept and suitable design of control rods, this project showed that it was possible to design a soluble boron free core in 600 MWe PWR. The results of large scale core design showed that passive concepts and daily load follow operation could be practiced. (author). 15 refs., 52 tabs., 101 figs.}
place = {Korea, Republic of}
year = {1997}
month = {Sep}
}