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 826732
  • - Editorial

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

Klaus Umminger | Alessandro Del Nevo
  • Special Issue
  • - Volume 2012
  • - Article ID 891056
  • - Review Article

Integral Test Facility PKL: Experimental PWR Accident Investigation

Klaus Umminger | Lars Dennhardt | ... | Bernhard Schoen
  • Special Issue
  • - Volume 2012
  • - Article ID 528241
  • - Review Article

Analyses of the OSU-MASLWR Experimental Test Facility

F. Mascari | G. Vella | ... | F. D'Auria
  • Special Issue
  • - Volume 2012
  • - Article ID 375070
  • - Research Article

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Ki-Yong Choi | Yeon-Sik Kim | ... | Won-Pil Baek
  • Special Issue
  • - Volume 2012
  • - Article ID 957285
  • - Research Article

RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation

Takeshi Takeda | Hideaki Asaka | Hideo Nakamura
  • Special Issue
  • - Volume 2012
  • - Article ID 474162
  • - Research Article

Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility

F. Reventós | P. Pla | ... | F. D'Auria
  • Special Issue
  • - Volume 2012
  • - Article ID 158617
  • - Research Article

Remarks on Consistent Development of Plant Nodalizations: An Example of Application to the ROSA Integral Test Facility

J. Freixa | A. Manera
  • Special Issue
  • - Volume 2012
  • - Article ID 548513
  • - Research Article

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

Virpi Kouhia | Heikki Purhonen | ... | Juhani Vihavainen
  • Special Issue
  • - Volume 2012
  • - Article ID 480948
  • - Research Article

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility

A. Del Nevo | M. Adorni | ... | M. Benčík
  • Special Issue
  • - Volume 2012
  • - Article ID 238090
  • - Research Article

RELAP5 Calculations of Bethsy 9.1b Test

Andrej Prošek
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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