Science and Technology of Nuclear Installations

Countercurrent Flow Limitations in a Pressurized Water Reactor


Publishing date
15 Apr 2012
Status
Published
Submission deadline
15 Oct 2011

Lead Editor

1Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Institute of Safety Researches, Berlin, Germany

2Institute of Nuclear Safety System, Incorporated (INSS), 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan

3Department of Mechanical & Industrial Engineering, Faculty of Engineering, Gadjah Mada University, Yogyakarta, Indonesia


Countercurrent Flow Limitations in a Pressurized Water Reactor

Description

In the event of hypothetical accident scenarios in a pressurized water reactor (PWR), emergency strategies have to be mapped out, in order to guarantee the reliable removal of decay heat from the reactor core. One essential passive heat removal mechanism is the reflux cooling mode. It can appear during a small break loss-of-coolant accident (LOCA) or because of loss of residual heat removal (RHR) system during midloop operation at plant outage. In the scenario of a loss-of-coolant accident (LOCA) in a PWR, it is considered that the reactor will be depressurized and vaporization will take place. This should lead to “reflux condensation,” which may be a favorable event progression; the generated steam will flow to the steam generator. This steam will condense in the steam generator, and the condensate will flow back through the hot leg to the reactor, resulting in countercurrent steam/water flow.

For a given condensate flow rate, if the steam mass flow rate increases to a certain value, a portion of the condensate will exhibit a partial flow reversal by the steam in the opposite flow direction towards the steam generator. This phenomenon is known as countercurrent flow limitation (CCFL). The keys to CCFL control are an improved understanding of these conditions, development of a suitable experimental data base, and novel tools to characterize the practical conditions in order to produce a better physical CCFL model.

We invite investigators to contribute original research articles as well as review articles that will simulate the continuing efforts to understand this important phenomenon. We are interested also in articles that explore the CCFL in a simple pipe configuration in order to support the physic behind the CCFL phenomena. Potential topics include, but are not limited to:

  • New experimental investigations on the countercurrent gas-liquid two-phase flow in a PWR hot leg as well as in downcomer and tie plate during blowdown
  • Development of experimental database on CCFL in a simple pipe/channel construction
  • Development of phenomenological and analytical model for the prediction of CCFL in a certain part of a PWR as well as in a simple channel construction
  • Computational fluid dynamics (CFD) effort on CCFL and relating phenomena, such as water hammer, steam condensation, and reflooding behavior
  • Latest experimental techniques require to investigate CCFL and provide data for CFD validation
  • Future discussion on R&D need about CCFL issues, with a focus on fuel coolability and relating severe accidents in a nuclear reactor

Before submission authors should carefully read over the journal's Author Guidelines, which are located at http://www.hindawi.com/journals/stni/guidelines/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/ according to the following timetable:


Articles

  • Special Issue
  • - Volume 2012
  • - Article ID 608678
  • - Editorial

Countercurrent Flow Limitations in a Pressurized Water Reactor

Deendarlianto | Thomas Höhne | Michio Murase
  • Special Issue
  • - Volume 2012
  • - Article ID 513809
  • - Research Article

Counter Current Flow Limitation of Gas-Liquid Two-Phase Flow in Nearly Horizontal Pipe

Sigit Prayitno | R. A. Santoso | ... | Dirk Lucas
  • Special Issue
  • - Volume 2012
  • - Article ID 298452
  • - Research Article

Experimental Characterisation of the Interfacial Structure during Counter-Current Flow Limitation in a Model of the Hot Leg of a PWR

Christophe Vallée | Toshifumi Nariai | ... | Michio Murase
  • Special Issue
  • - Volume 2012
  • - Article ID 907364
  • - Research Article

Numerical Simulation of Size Effects on Countercurrent Flow Limitation in PWR Hot Leg Models

I. Kinoshita | M. Murase | A. Tomiyama
  • Special Issue
  • - Volume 2012
  • - Article ID 754724
  • - Research Article

Countercurrent Flow Limitation at the Junction between the Surge Line and the Pressurizer of a PWR

Taiga Doi | Takashi Futatsugi | ... | Akio Tomiyama
  • Special Issue
  • - Volume 2012
  • - Article ID 785157
  • - Research Article

Experimental Investigation of Rising Gas Bubble Characteristics from a Vertical Tube under CCFL Condition

Kunihito Matsumura | Fumito Kaminaga
  • Special Issue
  • - Volume 2012
  • - Article ID 209542
  • - Research Article

Image-Processing-Based Study of the Interfacial Behavior of the Countercurrent Gas-Liquid Two-Phase Flow in a Hot Leg of a PWR

Gustavo A. Montoya | Deendarlianto | ... | Christophe Vallée
  • Special Issue
  • - Volume 2012
  • - Article ID 935391
  • - Research Article

VOF Calculations of Countercurrent Gas-Liquid Flow in a PWR Hot Leg

M. Murase | A. Tomiyama | ... | A. Yamaguchi
  • Special Issue
  • - Volume 2012
  • - Article ID 174838
  • - Research Article

Countercurrent Air-Water Flow in a Scale-Down Model of a Pressurizer Surge Line

Takashi Futatsugi | Chihiro Yanagi | ... | Akio Tomiyama
  • Special Issue
  • - Volume 2012
  • - Article ID 731616
  • - Research Article

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Jung-Hua Yang | Jong-Rong Wang | ... | Chunkuan Shih
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate33%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore0.810
Impact Factor1.082
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