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Liquid metal reactor development -Studies on safety measure of LMR coolant

Abstract

A study on the safety measures of LMR coolant showed the results as follows; 1. LMR coolant safety measure. A. Analysis and improvement of sodium fire code. B. Analysis of sodium fire phenomena. 2. Sodium fire aerosol characteristics. It was carried out conceptual design and basic design for sodium fire facility of medium size composed of sodium supply tank, sodium reactor vessel, sodium fire aerosol filter system and scrubbing column, and drain tank etc. 3. Sodium purification technology. A. Construction of calibration loop. (1) Design of sodium loop for the calibration of the equipment. (2) Construction of sodium loop including test equipments and other components. B. Na-analysis technology. (1) Oxygen concentration determination by the wet method. (2) Cover gas purification preliminary experiment. 4. The characteristics of sodium-water reaction. A. Analysis of the micro and small leak phenomena. (1) Manufacture of the micro-leak test apparatus. B. Analysis of large leak events. (1) Development of preliminary code for analysis of initial spike pressure. (2) Sample calculation and comparison with previous works. C. Development of test facility for large leak event evaluation. (1) Conceptional and basic design for the water and sodium-water test facility. D. Technology development for water leak detection system. (1)  More>>
Authors:
Publication Date:
Jul 01, 1995
Product Type:
Technical Report
Report Number:
KAERI-RR-1477/94
Reference Number:
SCA: 210500; PA: AIX-27:015726; EDB-96:035698; NTS-96:014131; SN: 96001546338
Resource Relation:
Other Information: PBD: Jul 1995
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LIQUID METAL COOLED REACTORS; SODIUM; COMPUTER CODES; COOLANT LOOPS; FUEL-COOLANT INTERACTIONS; LIQUID METALS; MOLTEN METAL-WATER REACTIONS
OSTI ID:
187188
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96614682; TRN: KR9500159015726
Availability:
INIS; OSTI as DE96614682
Submitting Site:
KRN
Size:
477 p.
Announcement Date:
Feb 29, 1996

Citation Formats

Hwang, Sung Tae, Choi, Yoon Dong, Park, Jin Hoh, Kwon, Sun Kil, Choi, Jong Hyun, Cho, Byung Ryul, Kim, Tae Joon, Kwon, Sang Woon, Jung, Kyung Chae, Kim, Byung Hoh, Hong, Soon Bok, and Jung, Ji Yung. Liquid metal reactor development -Studies on safety measure of LMR coolant. Korea, Republic of: N. p., 1995. Web.
Hwang, Sung Tae, Choi, Yoon Dong, Park, Jin Hoh, Kwon, Sun Kil, Choi, Jong Hyun, Cho, Byung Ryul, Kim, Tae Joon, Kwon, Sang Woon, Jung, Kyung Chae, Kim, Byung Hoh, Hong, Soon Bok, & Jung, Ji Yung. Liquid metal reactor development -Studies on safety measure of LMR coolant. Korea, Republic of.
Hwang, Sung Tae, Choi, Yoon Dong, Park, Jin Hoh, Kwon, Sun Kil, Choi, Jong Hyun, Cho, Byung Ryul, Kim, Tae Joon, Kwon, Sang Woon, Jung, Kyung Chae, Kim, Byung Hoh, Hong, Soon Bok, and Jung, Ji Yung. 1995. "Liquid metal reactor development -Studies on safety measure of LMR coolant." Korea, Republic of.
@misc{etde_187188,
title = {Liquid metal reactor development -Studies on safety measure of LMR coolant}
author = {Hwang, Sung Tae, Choi, Yoon Dong, Park, Jin Hoh, Kwon, Sun Kil, Choi, Jong Hyun, Cho, Byung Ryul, Kim, Tae Joon, Kwon, Sang Woon, Jung, Kyung Chae, Kim, Byung Hoh, Hong, Soon Bok, and Jung, Ji Yung}
abstractNote = {A study on the safety measures of LMR coolant showed the results as follows; 1. LMR coolant safety measure. A. Analysis and improvement of sodium fire code. B. Analysis of sodium fire phenomena. 2. Sodium fire aerosol characteristics. It was carried out conceptual design and basic design for sodium fire facility of medium size composed of sodium supply tank, sodium reactor vessel, sodium fire aerosol filter system and scrubbing column, and drain tank etc. 3. Sodium purification technology. A. Construction of calibration loop. (1) Design of sodium loop for the calibration of the equipment. (2) Construction of sodium loop including test equipments and other components. B. Na-analysis technology. (1) Oxygen concentration determination by the wet method. (2) Cover gas purification preliminary experiment. 4. The characteristics of sodium-water reaction. A. Analysis of the micro and small leak phenomena. (1) Manufacture of the micro-leak test apparatus. B. Analysis of large leak events. (1) Development of preliminary code for analysis of initial spike pressure. (2) Sample calculation and comparison with previous works. C. Development of test facility for large leak event evaluation. (1) Conceptional and basic design for the water and sodium-water test facility. D. Technology development for water leak detection system. (1) Investigations for the characteristics of active acoustic detection system. (2) Testing of the characteristics of hydrogen leak detection system. 171 figs, 29 tabs, 3 refs. (Author).}
place = {Korea, Republic of}
year = {1995}
month = {Jul}
}