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Evaluation report on CCTF Core-II reflood test C2-1 (Run 55). Effect of pressure on reflood phenomena

Technical Report:

Abstract

A high pressure test (0.42 MPa) on the reflood phenomena was performed with the CCTF. The result of the test was compared with the experimental result of the base case test (0.2 MPa). (1) The overall flow characteristics in the high pressure test were qualitatively similar to that of the base case test. Any qualitatively different phenomena were not recognized during reflood phase. This indicates that it is reasonable to utilize the physical reflood model developed from the result of the base case test to the high pressure condition at least up to 0.42 MPa for prediction of reflood behavior of PWRs. (2) On the other hand, following quantitative influence of high pressure on reflood phenomena was observed. The core cooling was better, and the mass flow rate of the steam generated in the core was larger. However, the steam velocity was smaller due to higher density of the steam. Therefore, the steam discharge through loops was easier and hence the so-called steam binding effect was weaker. And, the water accumulation rate in the core was larger. Consequently the core flooding mass flow rate was larger. Since the core cooling was better, the maximum core temperature was lower and the  More>>
Authors:
Iguchi, Tadashi; Sugimoto, Jun; Akimoto, Hajime; Okubo, Tsutomu; Murao, Yoshio [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Oct 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-173
Reference Number:
SCA: 220900; 210200; PA: JPN-91:012207; SN: 92000659241
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REWETTING; PWR TYPE REACTORS; MEDIUM PRESSURE; EVALUATION; REACTOR CORES; REACTOR EXPERIMENTAL FACILITIES; REACTOR SAFETY; ECCS; TWO-PHASE FLOW; LOSS OF COOLANT; PRESSURE DEPENDENCE; TIME DEPENDENCE; 220900; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10117118
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92768129; TRN: JP9112207
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
104 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, and Murao, Yoshio. Evaluation report on CCTF Core-II reflood test C2-1 (Run 55). Effect of pressure on reflood phenomena. Japan: N. p., 1991. Web.
Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, & Murao, Yoshio. Evaluation report on CCTF Core-II reflood test C2-1 (Run 55). Effect of pressure on reflood phenomena. Japan.
Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, and Murao, Yoshio. 1991. "Evaluation report on CCTF Core-II reflood test C2-1 (Run 55). Effect of pressure on reflood phenomena." Japan.
@misc{etde_10117118,
title = {Evaluation report on CCTF Core-II reflood test C2-1 (Run 55). Effect of pressure on reflood phenomena}
author = {Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, and Murao, Yoshio}
abstractNote = {A high pressure test (0.42 MPa) on the reflood phenomena was performed with the CCTF. The result of the test was compared with the experimental result of the base case test (0.2 MPa). (1) The overall flow characteristics in the high pressure test were qualitatively similar to that of the base case test. Any qualitatively different phenomena were not recognized during reflood phase. This indicates that it is reasonable to utilize the physical reflood model developed from the result of the base case test to the high pressure condition at least up to 0.42 MPa for prediction of reflood behavior of PWRs. (2) On the other hand, following quantitative influence of high pressure on reflood phenomena was observed. The core cooling was better, and the mass flow rate of the steam generated in the core was larger. However, the steam velocity was smaller due to higher density of the steam. Therefore, the steam discharge through loops was easier and hence the so-called steam binding effect was weaker. And, the water accumulation rate in the core was larger. Consequently the core flooding mass flow rate was larger. Since the core cooling was better, the maximum core temperature was lower and the last quenching was earlier. This result was the same as that previously observed in CCTF tests in the scope of the pressure upto 0.3 MPa. (3) The higher pressure leads to the better core cooling, and hence the safety margin increases with the increase in the pressure. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}