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Experimental and analytical study on cesium iodide behavior in piping in wave experiment

Abstract

The WAVE (Wide range Aerosol model VErification) experiments have been performed at JAERI to investigate cesium iodide (CsI) deposition onto an inner surface of piping wall under typical severe accident conditions. The test facility consists of a dish containing CsI powder, electrical heaters and a straight pipe of 1.5 m in length with diameter of 0.042m. Nitrogen gas and superheated steam were injected into the pipe to carry the vaporized CsI and to simulate the thermohydraulic condition for the PWR hot-leg inlet. Analyses of the experiments have been conducted with a three-dimensional thermohydraulic code, SPRAC and the radionuclide behavior analysis codes, ART and VICTORIA. A clear difference was found in the deposition behavior between nitrogen and steam conditions as carrier gases. For nitrogen gas, the analyses well reproduced the experimental results by closely coupling the CsI behavior and the detailed thermohydraulic analyses. For steam carrier gas, on the contrary, the experimental results could not be well reproduced without the use of larger aerosol size. Since the observed enhancement of aerosol size in superheated steam cannot be explained by existing models, it is necessary to further investigate this mechanisms by experiment and analysis. (author) 34 figs., 23 refs.
Authors:
Hidaka, A; Igarashi, M; Hashimoto, K; Sugimoto, J; [1]  Yoshino, T [2] 
  1. Japan Atomic Energy Research Inst., Dep. of Reactor Safety Research, Tokai-mura (Japan)
  2. Toshiba Advanced System Corp., Isago Kawasaki-ku (Japan)
Publication Date:
Dec 01, 1996
Product Type:
Technical Report
Report Number:
PSI-97-02; CONF-9606320-; NEA/CSNI/R(96)-6.
Reference Number:
SCA: 210200; 400201; PA: AIX-28:037568; EDB-97:078523; SN: 97001796024
Resource Relation:
Conference: 4. CSNI workshop on the chemistry of iodine in reactor safety, Wuerenlingen (Switzerland), 10-12 Jun 1996; Other Information: PBD: Dec 1996; Related Information: Is Part Of Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety; Guentay, S. [ed.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)]; PB: 716 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 40 CHEMISTRY; CESIUM IODIDES; EVAPORATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; A CODES; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; NITROGEN; PIPES; S CODES; STEAM; THEORETICAL DATA; V CODES
OSTI ID:
481723
Research Organizations:
Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Country of Origin:
Switzerland
Language:
English
Other Identifying Numbers:
Other: ON: DE97624048; TRN: CH9700220037568
Availability:
INIS; OSTI as DE97624048
Submitting Site:
CHN
Size:
pp. 531-546
Announcement Date:
Jun 23, 1997

Citation Formats

Hidaka, A, Igarashi, M, Hashimoto, K, Sugimoto, J, and Yoshino, T. Experimental and analytical study on cesium iodide behavior in piping in wave experiment. Switzerland: N. p., 1996. Web.
Hidaka, A, Igarashi, M, Hashimoto, K, Sugimoto, J, & Yoshino, T. Experimental and analytical study on cesium iodide behavior in piping in wave experiment. Switzerland.
Hidaka, A, Igarashi, M, Hashimoto, K, Sugimoto, J, and Yoshino, T. 1996. "Experimental and analytical study on cesium iodide behavior in piping in wave experiment." Switzerland.
@misc{etde_481723,
title = {Experimental and analytical study on cesium iodide behavior in piping in wave experiment}
author = {Hidaka, A, Igarashi, M, Hashimoto, K, Sugimoto, J, and Yoshino, T}
abstractNote = {The WAVE (Wide range Aerosol model VErification) experiments have been performed at JAERI to investigate cesium iodide (CsI) deposition onto an inner surface of piping wall under typical severe accident conditions. The test facility consists of a dish containing CsI powder, electrical heaters and a straight pipe of 1.5 m in length with diameter of 0.042m. Nitrogen gas and superheated steam were injected into the pipe to carry the vaporized CsI and to simulate the thermohydraulic condition for the PWR hot-leg inlet. Analyses of the experiments have been conducted with a three-dimensional thermohydraulic code, SPRAC and the radionuclide behavior analysis codes, ART and VICTORIA. A clear difference was found in the deposition behavior between nitrogen and steam conditions as carrier gases. For nitrogen gas, the analyses well reproduced the experimental results by closely coupling the CsI behavior and the detailed thermohydraulic analyses. For steam carrier gas, on the contrary, the experimental results could not be well reproduced without the use of larger aerosol size. Since the observed enhancement of aerosol size in superheated steam cannot be explained by existing models, it is necessary to further investigate this mechanisms by experiment and analysis. (author) 34 figs., 23 refs.}
place = {Switzerland}
year = {1996}
month = {Dec}
}