Investigation of Non-cooldown SG Secondary Condition on the Natural Circulation Cooling Procedure
Main Article Content
Abstract
In typical pressurized water reactor (PWR), in case that one steam generator (SG) cannot be credited for the primary cooldown, it is necessary to homogenize primary coolant temperature among loops using at least one reactor coolant pump (RCP) for the plant cooldown. If the natural circulation condition is established due to unavailability of all the RCPs, the continuous cooldown using intact SGs causes to disturb the smooth depressurization because it leads to void generation in the top of the non-cooldown SG tube where the high temperature coolant is remained. For this purpose, W.Sakuma, et al.[1] suggested the outline of asymmetric cooldown procedure without any RCPs restart. Since the suggested procedure is based on only one secondary condition (SG dry-out) of non-cooldown SG, and hence the impact of difference of the secondary condition should be investigated. In this paper, the sensitivity analyses were performed to confirm the impact on the asymmetric cooldown procedure, and consequently, it was confirmed that the coolable range used in the procedure was expanded if the water inventory exists in non-cooldown SG. Therefore it was concluded that the coolable range which was defined with the SG dry-out condition in non-cooldown SG can be conservatively applied for the operating procedure.
Article Details
Keywords
PWR, natural circulation, loop unbalanced condition, cooling procedure, M-RELAP5 code
References
[2] Anis Bousbia Salah and Jacques Vlassenbroeck, CATHARE Assessment of Natural Circulation in the PKL Test Facility during Asymmetric Cooldown Transients, Hindawi Publishing Corporation, Science and Technology of Nuclear Installations, Volume 2012, Article ID 950389, (2012)
[3] Japan Atomic Energy Agency, Quick-look Data Report of ROSA-2/LSTF Test6 (Natural Circulation Test: ST-NC-41 in JAEA), (2012)
[4] ROSA-IV Group “ROSA-IV Large Scale Test Facility (LSTF) system description for second simulated fuel assembly”, JAERI-M90-176 (1990).
[5] Small Break LOCA Methodology for US-APWR, MUAP-07013-NP-A(R3) (2014)