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Development on the technologies for tritium removal processes

Abstract

While tritium exposure to the site-workers in Wolsung NPP is upto about 40 % of the total personnel exposure, Korea Institute of Nuclear Safety has asked tritium removal facility, as one of the requirements for post reactor construction, after operation of four CANDU reactors in Wolsung site. For the purpose of essential removal of tritium from the heavy water system of the heavy water reactors, an experiment of Ar-N{sub 2} cryogenic distillation tower was carried out as a preliminary study for development of liquid-phase catalytic exchange - cryogenic hydrogen distillation process. The steady-state reached after 50 minutes under 90 K in the Ar-N{sub 2} distillation column (inner diameter 20 mm, height 500 mm) packed with Dixon ring ({phi} 3 mm x H 3 mm), and the ratios of Ar-concentration at the top and at the bottom measured by gas chromatography within {+-}1 % relative error was approximately 93 : 3. This value was distillation performances quite higher than those estimated by computer-simulation, which might be due to good efficiency of the packing materials. Several dynamic characteristics such as height equivalent to theoretical plate or effects of the kind of packing materials for Ar-N{sub 2} distillation column to be produced will  More>>
Authors:
Sung, Ki Woong; Kim, Yong Ik; Nah, Jung Won; Koo, Je Hyoo; Kim, Kwang Lak; Chung, Heung Suk; Lee, Han Soo; Cho, Yung Hyun; Paek, Seung Woo; Kang, Heui Suk; [1]  Chung, Yong Won [2] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
  2. In Hah Univ., Inchun (Korea, Republic of)
Publication Date:
Dec 01, 1994
Product Type:
Technical Report
Report Number:
KAERI-RR-1435/94
Reference Number:
SCA: 052001; 400703; PA: AIX-27:016245; EDB-96:034696; NTS-96:014134; SN: 96001546467
Resource Relation:
Other Information: PBD: Dec 1994
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; TRITIUM; EXTRACTION COLUMNS; ARGON; COMPUTERIZED SIMULATION; CRYOGENICS; DISTILLATION; NITROGEN; RADIOACTIVE WASTE PROCESSING; REMOVAL; WOLSUNG-1 REACTOR; WOLSUNG-2 REACTOR
OSTI ID:
187190
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE96614789; TRN: KR9500128016245
Availability:
INIS; OSTI as DE96614789
Submitting Site:
KRN
Size:
133 p.
Announcement Date:
Feb 29, 1996

Citation Formats

Sung, Ki Woong, Kim, Yong Ik, Nah, Jung Won, Koo, Je Hyoo, Kim, Kwang Lak, Chung, Heung Suk, Lee, Han Soo, Cho, Yung Hyun, Paek, Seung Woo, Kang, Heui Suk, and Chung, Yong Won. Development on the technologies for tritium removal processes. Korea, Republic of: N. p., 1994. Web.
Sung, Ki Woong, Kim, Yong Ik, Nah, Jung Won, Koo, Je Hyoo, Kim, Kwang Lak, Chung, Heung Suk, Lee, Han Soo, Cho, Yung Hyun, Paek, Seung Woo, Kang, Heui Suk, & Chung, Yong Won. Development on the technologies for tritium removal processes. Korea, Republic of.
Sung, Ki Woong, Kim, Yong Ik, Nah, Jung Won, Koo, Je Hyoo, Kim, Kwang Lak, Chung, Heung Suk, Lee, Han Soo, Cho, Yung Hyun, Paek, Seung Woo, Kang, Heui Suk, and Chung, Yong Won. 1994. "Development on the technologies for tritium removal processes." Korea, Republic of.
@misc{etde_187190,
title = {Development on the technologies for tritium removal processes}
author = {Sung, Ki Woong, Kim, Yong Ik, Nah, Jung Won, Koo, Je Hyoo, Kim, Kwang Lak, Chung, Heung Suk, Lee, Han Soo, Cho, Yung Hyun, Paek, Seung Woo, Kang, Heui Suk, and Chung, Yong Won}
abstractNote = {While tritium exposure to the site-workers in Wolsung NPP is upto about 40 % of the total personnel exposure, Korea Institute of Nuclear Safety has asked tritium removal facility, as one of the requirements for post reactor construction, after operation of four CANDU reactors in Wolsung site. For the purpose of essential removal of tritium from the heavy water system of the heavy water reactors, an experiment of Ar-N{sub 2} cryogenic distillation tower was carried out as a preliminary study for development of liquid-phase catalytic exchange - cryogenic hydrogen distillation process. The steady-state reached after 50 minutes under 90 K in the Ar-N{sub 2} distillation column (inner diameter 20 mm, height 500 mm) packed with Dixon ring ({phi} 3 mm x H 3 mm), and the ratios of Ar-concentration at the top and at the bottom measured by gas chromatography within {+-}1 % relative error was approximately 93 : 3. This value was distillation performances quite higher than those estimated by computer-simulation, which might be due to good efficiency of the packing materials. Several dynamic characteristics such as height equivalent to theoretical plate or effects of the kind of packing materials for Ar-N{sub 2} distillation column to be produced will be available for design study of cryogenic hydrogen distillation process. 19 figs, 17 tabs, 21 refs. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Dec}
}