Science and Technology of Nuclear Installations

Integral Test Facilities and Thermal-Hydraulic System Codes in Nuclear Safety Analysis


Publishing date
01 Nov 2011
Status
Published
Submission deadline
01 May 2011

Lead Editor

1AREVA NP GmbH, Paul-Gossen Straße 100, P.O. Box 1109, 91058 Erlangen, Germany

2San Piero a Grado Nuclear Research Group, University of Pisa, Via Livornese 1291, 56100 San Piero a Grado, Italy


Integral Test Facilities and Thermal-Hydraulic System Codes in Nuclear Safety Analysis

Description

A considerable amount of resources have been devoted at international level for establishing and conducting experimental programs in scaled down Integral Test Facilities (ITFs). These were aimed at solving open issues for current Nuclear Power Plant (NPP) types, demonstrating the technical feasibility of innovative designs, and generating reference databases to support code development and assessment. Since the end of the nineties, the maintenance of the competences, including the creation of a new generation of professionals in the area of the nuclear safety, is also a priority objective.

Tens of ITF have been built and operated so far all over the world. Few of them, related to existing water reactor technology, are currently in operation (e.g., ATLAS, PMK, PKL-III, and ROSA IV) or under refurbishment (e.g., PACTEL, PSB-VVER). Some others are constructed or under design and are focused on innovative water reactor concepts (e.g., MASLWR, SPES-3).

The experimental data from such facilities are applicable to full-scale NPP conditions, provided that the test facilities and the initial and boundary conditions of experiments are properly scaled. They are also fundamental for supporting the development and for demonstrating the reliability of computer codes, which is, in general, a regulatory requirement. However, often the results from test facilities cannot be directly applied to a plant, including the “reference” plant for the facility design. Applications of computer codes to accident analyses require the implicit assumptions that these codes have the capabilities to scale up phenomena and processes from test facilities to full-scale plant conditions; this is not ensured a priori.

In view of the above, it has been decided to bring out this special issue which aimed at documenting the present scientific and technical status and recent advances in relation to the subject.

The special issue will include a few, invited, overview papers plus scientific and technical contributions, not limited in numbers. All papers will be subject to the usual reviewing procedure. Potential topics include, but are not limited to:

  • New or refurbished ITF design and construction
  • Recent ITF experimental program
  • Experimental investigations in ITF
  • Design of experimental facilities
  • Scaling issue related to both the representativeness of the phenomena in the facility as well as the applicability of the codes
  • Standard problems and benchmarks
  • Code assessment and validation

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 439374
  • - Research Article

The Integral Test Facility Karlstein

Stephan Leyer | Michael Wich
  • Special Issue
  • - Volume 2012
  • - Article ID 239319
  • - Research Article

PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

Domenico Paladino | Jörg Dreier
  • Special Issue
  • - Volume 2012
  • - Article ID 275693
  • - Research Article

Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

Vladimir N. Blinkov | Oleg I. Melikhov | ... | Siegfried Arndt
  • Special Issue
  • - Volume 2012
  • - Article ID 780472
  • - Research Article

PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

Gy. Ézsöl | L. Perneczky | ... | I. Tóth
  • Special Issue
  • - Volume 2012
  • - Article ID 173637
  • - Research Article

SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

Andrea Achilli | Cinzia Congiu | ... | Milorad Dzodzo
  • Special Issue
  • - Volume 2012
  • - Article ID 238019
  • - Project Report

The LOBI Integral System Test Facility Experimental Programme

Carmelo Addabbo | Alessandro Annunziato
  • Special Issue
  • - Volume 2012
  • - Article ID 282987
  • - Research Article

Trace Code Validation for BWR Spray Cooling Injection and CCFL Condition Based on GÖTA Facility Experiments

Stefano Racca | Tomasz Kozlowski
  • Special Issue
  • - Volume 2012
  • - Article ID 950389
  • - Research Article

CATHARE Assessment of Natural Circulation in the PKL Test Facility during Asymmetric Cooldown Transients

Anis Bousbia Salah | Jacques Vlassenbroeck
Science and Technology of Nuclear Installations
 Journal metrics
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Acceptance rate24%
Submission to final decision110 days
Acceptance to publication14 days
CiteScore1.500
Journal Citation Indicator0.380
Impact Factor1.1
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