Perspectives in System Thermal-Hydraulics

The paper deals with three main topics: a) the definition of System Thermal-Hydraulics (SYS TH), b) a historical outline for SYS TH and, c) the description of elements for reflection when planning research projects or improvement activities, this last topic being the main reason for the paper. Distinctions between basic thermal-hydraulics and computational Fluid-Dynamics (CFD) on the one side and SYS TH on the other side are considered under the first topic; stakeholders in the technology are identified. The proposal of Interim Acceptance Criteria for Emergency Core Cooling Systems in 1971 by US NRC (AEC at the time) is recognized as the starting date or the triggering event for SYS TH (second topic). The complex codes and the main experimental programs (list provided in the paper) constitute the pillars for SYS TH. Caution or warning statements are introduced in advance when discussing the third topic: a single person (or a researcher) has little to no possibility, or capability, of streamlining the forthcoming investments or to propose a roadmap for future activities. Nevertheless, the ambitious attempt to foresee developments in this area has been pursued without constraints connected with the availability of funds and with industrial benefits or interests. Demonstrating the acceptability of current SYS TH limitations and training in the application of those codes are mentioned as the main challenges for forthcoming research activities

Nodalization effects on RELAP5 results related to MTR research reactor transient scenarios

The present work deals with the anal y sis of RELAP5 results obtained from the evaluation study of the total loss of flow transient with the deficiency of the heat removal system in a research reactor using two different nodalizations. It focuses on the effect of nodalization on the thermal-hydraulic evaluation of the re search reactor. The analysis of RELAP5 results has shown that nodalization has a big effect on the predicted scenario of the postulated transient. There fore, great care should be taken during the nodalization of the reactor, especially when the avail able experimental or measured data are insufficient for making a complete qualification of the nodalization. Our analysis also shows that the research reactor pool simulation has a great effect on the evaluation of natural circulation flow and on other thermal-hydraulic parameters during the loss of flow transient. For example, the on set time of core boiling changes from less than 2000 s to 15000 s, starting from the beginning of the transient. This occurs if the pool is simulated by two vertical volumes in stead of one vertical volume

Un nuovo approccio di analisi, gestione e controllo del processo edilizio sul patrimonio storico

2012 - 2013The theme of the recovery of historical buildings is current, especially in a period in which, for known economic, financial, social and political reasons, interventions of new constructions and investment have declined dramatically and investments, although contained, are diverted to energy rehabilitation and functional recovery and restoration of existing buildings. Our country has a housing stock that, if properly managed and developed, can turn into an asset by potential priceless. Often, however, customers, designers and contractors are not ready for action in addressing the demanding projects on historical buildings, losing opportunities for development and economic growth. Just think, for example, to the considerable funds that the EU allocates periodically to facilitate the recovery of historic buildings and that often our country is not able to find or spend. The most common causes of these inefficiencies are attributable to the reluctance - in the fields of engineering and architecture - to the planning, management of enterprise-resource, teamwork, updated, the industrialization of construction site, quality control and so on. This PhD research is aimed to study, from the theoretical point of view and from the study of the state of the art, the efficiency - in terms of productivity and quality of work - of a new approach for analysis, management and control of the building process, through the use of the methodology of building information modeling using two case studies of reference: the assessment of the applicability of the BIM Surveying to the historical buildings and the possible benefits of the latter compared to the use of traditional survey methods. Building information modeling, already widely used successfully in other countries as part of interventions of new construction, it is a 'way of working' relatively young and little known in many advanced counties, including Italy. It is configured as a holistic and coordinated method to assist architects, engineers, customers, decision makers, maintenance staff and all those involved in the building project. In the current traditional practice, the life cycle of a building - from design, to construction management, from supply management to the maintenance work in the year - remains fragmented and based on a continuous and not-organized exchange of information between the various actors involved in the construction process. Errors, omissions or inaccuracies contained in these documents (paper or digital) are often due to unexpected costs, delays in the design and execution of the work, of legal actions between clients and companies or designers... [edited by Author]XII n.s

Nuclear Energy for Sustainable Economic Development

The discovery and the application of nuclear energy constitute the most important technological achievement of the past century. However, the development and the exploitation of this technology have been remarkably smaller than foreseeable. An overview of the significant features of the nuclear technology including the comparison with competitive energy sources is made. The “embedded” safety engineering and the pollution are discussed and the main features are mentioned. Indeed, nuclear technology can be applied for the sustainable society development by producing substantial amount of clean water from the ocean. The idea is to build up nuclear power plant sites that produce desalinated water and pump it several tens of kilometers away to form a lake into a desert region. This could help to establish the conditions for an agriculture-based civilization

Validation of CATHARE TH-SYS Code Against Experimental Reflood Tests

This paper presents results of a code validation activity that has been carried out at the University of Pisa within the EC-funded NURESAFE project, aimed to assess CATHARE2 v2.5_3 Mod3.1 code capabilities to simulate scenarios featuring reflood conditions. For such purpose, experimental data available from FEBA and ACHILLES separate-effect test facilities was used. In order to set-up a reference calculation model, rigorous sensitivity studies have been performed for every of the selected experimental test facilities. Quantitative analysis of the results has been carried out for all of the considered tests, using the Fast Fourier Transform Based Method (FFTBM) for accuracy quantification of code predictions. The calculations of experimental tests of ACHILLES facility have been performed with CATHARE2 v2.5_3 mod 3.1 using both 1-D and 3-D models. The no-regression of the results predicted by such code was successfully checked through qualitative and quantitative comparison with results obtained by the one of previous code versions: CATHARE2 v2.5_2 mod 7.1. An assessment of the capabilities of the new CATHARE3 v1.3.13 code to simulate reflood phenomena using both two- and three-field 1-D models has then been carried out, based on the same ACHILLES tests. Simulations by CATHARE3 (three-field) exhibit faster quenching than CATHARE2, mainly due to the presence of the droplet field enhancing the heat exchange from the fuel rod simulators. The performed qualitative analysis has shown the ability of CATHARE2 code to capture the main features of the reflood phenomena using appropriate modeling. Nonetheless, the quantitative analysis shows a systematic underprediction of the PCT and faster quenching in the majority of tests

Assessment of NEPTUNE_CFD Code Capabilities to Simulate Two-Phase Flow in the OECD/NRC PSBT Subchannel Experiments

This paper deals with the validation of the multifield computational fluid dynamics code NEPTUNE_CFD v2.0.1 against experimental data available from the OECD/NRC NUPEC PWR subchannel and bundle tests (PSBT) international benchmark. The present work is performed in the framework of the NURESAFE European collaborative project and focuses on the steady-state single subchannel void fraction tests. From overall 126 PSBT experiments covering wide range of test conditions and 4 different geometrical configurations of PWR subchannel, 42 tests have been selected and simulated using NEPTUNE_CFD. Following the NEA/CSNI (Nuclear Energy Agency / Committee on the Safety of Nuclear Installations) best practice guidelines about computational grid design and grid quality, mesh sensitivity analysis has been performed using axial and radial grid refinement. Both axial and radial mesh sensitivity studies do not exhibit any significant change in the predicted results, which thus result to be grid-converged. Besides, a series of sensitivity calculations have been performed in order to investigate the influence of uncertainties of the experimental boundary conditions on the code predictions. The influence of code physical and closure models on the void fraction prediction has been studied and discussed in detail. Generally, the calculated cross-sectional averaged void fraction at the measurement plane differs from the measured one by maximum of +/- 8%. This discrepancy is comparable to the 2σ experimental uncertainty range on void fraction measurement. The performed investigations have shown the ability of NEPTUNE_CFD to predict reasonably the void fraction in PSBT subchannel using appropriate modelling

Chapter Frammenti urbani e nuove visualizzazioni: la piazzetta di San Gennaro all’Olmo a Napoli

The 43rd UID conference, held in Genova, takes up the theme of ‘Dialogues’ as practice and debate on many fundamental topics in our social life, especially in these complex and not yet resolved times. The city of Genova offers the opportunity to ponder on the value of comparison and on the possibilities for the community, naturally focused on the aspects that concern us, as professors, researchers, disseminators of knowledge, or on all the possibile meanings of the discipline of representation and its dialogue with ‘others’, which we have broadly catalogued in three macro areas: History, Semiotics, Science / Technology. Therefore, “dialogue” as a profitable exchange based on a common language, without which it is impossible to comprehend and understand one another; and the graphic sign that connotes the conference is the precise transcription of this concept: the title ‘translated’ into signs, derived from the visual alphabet designed for the visual identity of the UID since 2017. There are many topics which refer to three macro sessions: - Witnessing (signs and history) - Communicating (signs and semiotics) - Experimenting (signs and sciences) Thanks to the different points of view, an exceptional resource of our disciplinary area, we want to try to outline the prevailing theoretical-operational synergies, the collaborative lines of an instrumental nature, the recent updates of the repertoires of images that attest and nourish the relations among representation, history, semiotics, sciences

Post-BEMUSE Reflood Model input uncertainty methods (PREMIUM) Benchmark Phase II: identification of influential Parameters

The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system thermal-hydraulic codes by considering a concrete case: the physical models involved in the prediction of core reflooding. The PREMIUM benchmark consists of five phases: - Phase I: mainly, definition of the different uncertainty methods; - Phase II: determination of the physical models influential in reflooding using the test 216 of the FEBA programme; - Phase III: quantification of the uncertainties of the parameters associated with the physical models identified as influential within Phase II, using FEBA/SEFLEX experimental results; - Phase IV: validation of the found uncertainties within Phase III by propagating them in the 2-D PERICLES reflood experiment; this phase will be performed blindly except for the coordinators; - Phase V: synthesis report. This report presents the results of Phase II. Phase II is dedicated to the identification of the uncertain code parameters associated with physical models used in the simulation of reflooding conditions. This identification is made on the basis of the Test 216 of the FEBA/SEFLEX programme according to the following steps: - identification of influential phenomena; - identification of the associated physical models and parameters, depending on the used code; - quantification of the variation range of identified input parameters through a series of sensitivity calculations. A procedure for the identification of potentially influential code input parameters has been set up in the Specifications of Phase II of PREMIUM benchmark. A set of quantitative criteria has been as well proposed for the identification of influential IP and their respective variation range. Thirteen participating organisations, using 8 different codes (7 system thermal-hydraulic codes and 1 sub-channel module of a system thermal-hydraulic code) submitted Phase II results. The base case calculations show spread in predicted cladding temperatures and quench front propagation that has been characterized. All the participants, except one, predict a too fast quench front progression. Besides, the cladding temperature time trends obtained by almost all the participants show oscillatory behaviour which may have numeric origins. Adopted criteria for identification of influential input parameters differ between the participants: some organisations used the set of criteria proposed in Specifications “as is”, some modified the quantitative thresholds proposed in Specifications, and others used their own methodologies. This fact was a partial reason for the different ranges of input parameter variation identified by participants, in addition to differences of the physical models adopted by the different codes. Therefore, such different variation ranges of IP and, correspondingly, such different variation ranges of cladding temperature and time of rewet, make rather difficult the task of meaningful and easy-comprehendible comparison of Phase II results. Out of a total of 72 input parameters, initially considered by all participants, only 6 were identified as influential by more than 4 participants that are: - bundle power; - wall heat transfer coefficient; - interphase friction coefficient; - interphase heat transfer coefficient; - heat transfer (enhancement) at the quench front; - droplet diameter. It should be noted that actual parameters considered in parameter “Heat transfer (enhancement) at the quench front” are code-specific and may have different influence on calculation results. Several participants discarded some identified influential parameters (e.g., droplet diameter) due to existing relation between this kind of parameters so-called “Input Coefficient Parameters” and more global parameters (e.g. interfacial friction coefficient and interphase heat transfer coefficient which use the droplet diameter) so-called “Input Global Parameters”. Some participants also discarded identified influential so-called “Input Basic Coefficients” (e.g. bundle power) since their uncertainty has not to be determined in the Phase III but will be provided by the coordinator from experimental data. The behaviour of the variation of the responses at the extremes of IP range of variation greatly depends on the type of input parameter and on the code used. Mainly, the following two different behaviours can be characterized: - For some parameters, like power, wall heat transfer and interphase heat transfer coefficients, a qualitative (but not quantitative) agreement between different codes is observed. - For other parameters, like interphase friction coefficient and droplet diameter, a contrary behaviour (i.e. in correspondence of one of the extreme of the IP range, the direction of change of the responses is different) between different codes and even between different selected models within the same code can be observed. This suggests that the effect of such parameters on the cladding temperatures is quite complex, probably because it involves a lot of physical models (e.g., via interphase friction and interphase heat transfer coefficients for the droplet diameter). It shall be noted that the analysis of differences between the reflood models of different codes is out of scope of the PREMIUM benchmark. Nevertheless, it is recommended to take into account the physical models/ input parameters found as influential by the other participants in order to select the influential input parameters for which uncertainties are to be quantified within the Phase III of PREMIUM. In particular, input parameters identified as influential by other participants using the same code should be considered

Measurement of the radiation field surrounding the Collider Detector at Fermilab

We present here the first direct and detailed measurements of the spatial distribution of the ionizing radiation surrounding a hadron collider experiment. Using data from two different exposures we measure the effect of additional shielding on the radiation field around the Collider Detector at Fermilab (CDF). Employing a simple model we parameterize the ionizing radiation field surrounding the detector.Comment: PDF document, 5 pages, including 10 encapsulated postscript figures: Proceedings for the IEEE/NSS-MIC 2003 Conference, Portland, Oregon, October 19-25, 200

THE REGENERATION OF PUBLIC HERITAGE ESTATE IN CAMPANIA: AN ASSESSMENT APPROACH

The propensity for sustainability represents one of the most difficult challenges globally in recent decades. The programs of 2030 Agenda define some objectives related to construction including the increase in housing, the promotion of social inclusion and the upgrading of healthcare structures. The main objective of the research is the definition of an instrument to support the administrations to identify buildings suitable for transformation in social housing and healthcare constructions, with reference to public asset with a cultural value, disused or "badly used". Through multi-criteria evaluations based on the analysis of parametric indicators, the methodology intends to define a protocol useful for the purposes already mentioned and for meta-project guidelines that guarantee a sustainable approach to the transformation and regeneration of the real estate in question. The initial objectives and methodological aspects are presented in this paper