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Evaluation report on CCTF Core-II reflood test C2-5 (Run 63). Effect of decay heat level on PWR reflood phenomena

Technical Report:

Abstract

The following items on decay heat effect on PWR reflood phenomena were revealed by investigation on results of CCTF tests in the range of 1.06 kW/m to 1.4 kW/m of initial average linear power (Peak linear power: 2.04 kW/m to 2.69 kW/m; Total power: 7.1 MW to 9.4 MW). These power levels simulate most probable case to very conservative case for PWR LOCA analyses. (1) The overall flow characteristics in the low power test (1.06 kW/m of initial average linear power) were qualitatively similar to that of the base case test (1.4 kW/m of initial average linear power). 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 under the low power condition at least up to 1.06 kW/m of the initial average linear power for a prediction of PWR reflood phenomena. (2) On the other hand, the following quantitative influence of the power on PWR reflood phenomena was observed. This result was consistent to that previously observed in FLECHT-SET tests performed in the scope of the initial average linear power from 1.88 kW/m to 2.35 kW/m. (3) Observed  More>>
Authors:
Iguchi, Tadashi; Sugimoto, Jun; Akimoto, Hajime; Okubo, Tsutomu; Murao, Yoshio; [1]  Sudoh, Takashi; Okabe, Kazuharu
  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-91-174
Reference Number:
SCA: 220900; 210200; PA: JPN-91:012208; SN: 92000659242
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REWETTING; AFTER-HEAT; LOSS OF COOLANT; REACTOR SAFETY; TWO-PHASE FLOW; ECCS; HEAT TRANSFER; REACTOR EXPERIMENTAL FACILITIES; CYLINDRICAL CONFIGURATION; TEMPERATURE RANGE 0400-1000 K; REACTOR CORES; EVALUATION; 220900; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10117404
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92768130; TRN: JP9112208
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
108 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, Murao, Yoshio, Sudoh, Takashi, and Okabe, Kazuharu. Evaluation report on CCTF Core-II reflood test C2-5 (Run 63). Effect of decay heat level on PWR reflood phenomena. Japan: N. p., 1991. Web.
Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, Murao, Yoshio, Sudoh, Takashi, & Okabe, Kazuharu. Evaluation report on CCTF Core-II reflood test C2-5 (Run 63). Effect of decay heat level on PWR reflood phenomena. Japan.
Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, Murao, Yoshio, Sudoh, Takashi, and Okabe, Kazuharu. 1991. "Evaluation report on CCTF Core-II reflood test C2-5 (Run 63). Effect of decay heat level on PWR reflood phenomena." Japan.
@misc{etde_10117404,
title = {Evaluation report on CCTF Core-II reflood test C2-5 (Run 63). Effect of decay heat level on PWR reflood phenomena}
author = {Iguchi, Tadashi, Sugimoto, Jun, Akimoto, Hajime, Okubo, Tsutomu, Murao, Yoshio, Sudoh, Takashi, and Okabe, Kazuharu}
abstractNote = {The following items on decay heat effect on PWR reflood phenomena were revealed by investigation on results of CCTF tests in the range of 1.06 kW/m to 1.4 kW/m of initial average linear power (Peak linear power: 2.04 kW/m to 2.69 kW/m; Total power: 7.1 MW to 9.4 MW). These power levels simulate most probable case to very conservative case for PWR LOCA analyses. (1) The overall flow characteristics in the low power test (1.06 kW/m of initial average linear power) were qualitatively similar to that of the base case test (1.4 kW/m of initial average linear power). 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 under the low power condition at least up to 1.06 kW/m of the initial average linear power for a prediction of PWR reflood phenomena. (2) On the other hand, the following quantitative influence of the power on PWR reflood phenomena was observed. This result was consistent to that previously observed in FLECHT-SET tests performed in the scope of the initial average linear power from 1.88 kW/m to 2.35 kW/m. (3) Observed special phenomenon induced by the low power condition is a short-term (a few seconds) differential pressure oscillation around the cold legs, which was caused by (1) the complete steam condensation at cold leg ECC ports and (2) the formation of the water plug in the cold legs. However, this oscillation had no adverse effect on the core cooling. The oscillation was observed when the power level reached the value corresponding to the decay heat at about 730 s after scram. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Oct}
}