1,721,369 research outputs found
Capabilities and limits of system codes", Lecture L4 at Course on Thermal-hydraulic Phenomena in Nuclear Reactor Technology - Sofia (BG)
No full textA Course in Nuclear thermal-hydraulics was organized by UNIPI in Sofia at the time of the cold war (Soviet Union collapsed in 1991). Contact crossing the iron curtain were extremely complex. The entire Course consists of several hundred slides (all preserved in paper format by the corresponding author) and a couple dozen lectures (see copies below). Two pages from the Course are reported below. The current lecture deals with the capabilities of nuclear thermal-hydraulic codes in predicting transient performance of Nuclear Power Plants
Introduction to Nuclear Reactor Thermalhydraulics", Lecture L2 at Course on Thermal-hydraulic Phenomena in Nuclear Reactor Technology
No full textA Course in Nuclear thermal-hydraulics was organized by UNIPI in Sofia at the time of the cold war (Soviet Union collapsed in 1991). Contact crossing the iron curtain were extremely complex. The entire Course consists of several hundred slides (all preserved in paper format by the corresponding author) and a couple dozen lectures (see copies below). Two pages from the Course are reported below. The current lecture deals with introductory remar
Italian point of view in assessment and validation of large thermal-hydraulic computer codes", University of Pisa Report, DCMN - RL 070(83), Pisa (I), Dec. 1983, 3rd Meet. of the CSNI SACTE Task Group, Paris (F), Nov. 30-Dec. 3, 1983
No full textAs Italian representative inside the thermal-hydraulic task group of Organization for Economic Cooperation and Development (OECD) / Nuclear Energy Agency (NEA) / Committee on the Safety of Nuclear Installations (CSNI), the current author was requested to present the Country point of view in relation to assessment and validation of system thermal-hydraulic code.
The point of view was discussed preliminarily with experts of ENEA (research Institution in Italy) and DISP (regulatory authority). The document was presented in Paris at the OECD/NEA headquarters and constitute one basis of the publication below
BEPU current ideas
No full textRather than abstract- the Foreword is provided: A paper like the present one provides the summary of knowledge spread within the scientific community. A huge number of researchers contributed to the knowledge. BEPU activities have been performed in the last twenty years. Hereafter I wish to acknowledge (in alphabetic order) some of them who directly or indirectly have been in touch and contributed with ideas and writings to the topics discussed in this paper: N. Aksan, D. Bestion, C. Camargo, N. Debrecin, R.B. Duffey, M. Dusic, N. Fil, G. Galassi, M.R. Galetti, H. Glaeser, D. Groeneveld, Y. Hassan, K. Ivanov, P. Kirillov, L. Leung, P. Lien, O. Mazzantini, B. Mavko, F. Menzel, J. Misak, H. Nakamura, B. Nigmatulin, H. Ninokata, F. Pelayo, A. Petruzzi, R. Pochard, M. Reocreux, F. Reventos, U.S. Rohatgi, E. Sartori, R. R. Schultz and B.R. Sehgal. Many more have taught me the basics of this matter, e.g. S. Banerjee, M. Cumo, B. Guerrini, E. Hicken, H. Karwat, R. T. Lahey, F. Mayinger, K. Tasaka, F. Winkler, K. Wolfert, G. Yadigaroglu and N. Zuber. All those listed may not necessarily share the BEPU vision in the text
OECD CSNI State-Of-the-Art-Report on thermalhydraulics of Emergency Core Cooling Systems: Review of the Operation of Experimental Facilities", OECD-CSNI Report SINDOC (89)101, Paris (F), 1989
No full textAs Italian representative inside the thermal-hydraulic task group of Organization for Economic Cooperation and Development (OECD) / Nuclear Energy Agency (NEA) / Committee on the Safety of Nuclear Installations (CSNI), the current author contributed to a preliminary activity which ended up in an OECD publication. The framework of the activity is assessment and validation of system thermal-hydraulic codes.
The present report deals with the assessment of the capabilities of experimental facilities available in the world (OECD Countries) for the validation of computer codes in nuclear reactor safety. The scaling issue and the quality of instrumentation and documentation of results are at the focus of attention
Comments, questions and answer to the passive system status report (> 1000 comments addressed)
No full textF. D’Auria, Pisa, December 11, 2019. SOAR on Passive systems: Comments and answers from rev-02 (Sept. 20, 2019) to rev-03 (Nov. 07, 2019), to rev-04 (Dec. 10, 2019), to rev-05 (Dec. 11, 2019) and to rev- 06 (Dec. 15, 2019). These are reported in the order they have been received and implemented. This report consists of 126 pages including the present one. All sets of received comments (more than 1100) to rev02 of the SOAR on Passive Systems are identified below (bold characters, Roman numbering), including Institution, acting scientist(s) and date of comment delivery. Each individual comment is identified by Arab digits numbering (in a few cases, in Italics, my comment to the comment). My answer is provided in red color below. Each Lead Author (at least) is expected to read the comments and the answers and to provide additional comments as needed. Starting from page 69, comments from rev03 to rev04 are discussed. Starting from page 107 comments from rev04 to rev05 are discussed. Any addition to the main text or comment to the comments below should be discussed at the December 11-13, 2019 meeting. An excellent job was done by contributors who provided comments below (although, in a few cases, contributors put questions instead of addressing unclear topics). Furthermore: (in general), my answer ‘Done. Thanks.’ implies that the contributor found an editorial bug; my answer ‘Done.’ implies that the text is improved. I introduced new text as discussed at item 309. The following documents-files are considered (all documents are available by the author here) from rev02 to re03: I) USNRC – Peter Lien – Sept. 27, 2019 – items 1 to 30 II) BelV – Anis Bousbia-Salah – Oct. 4, 2019 – items 31 to 60 IIIa) GRS – Sebastian Buchholz and Andreas Wielenberg, Oct. 16, 2019 (e-mail text) – items 61 to 72 IIIb) GRS – Andreas Wielenberg – Oct. 16, 2019 – item 73 IIIc) GRS – S. Buchholz and A. Wielenberg, Oct. 16, 2019 (word attachment to e-mail) – items 74 to 185 IIId) GRS – S. Buchholz and A. Wielenberg, Oct. 16, 2019 (pdf attachment to e-mail) – items 186 to 243 IV) NUBIKI – Barnabas Toth, Oct. 17, 2019 – CH3 – items 244 to 271 IVa) NUBIKI: Barnabas Toth, Oct. 26, 2019 – foreword, Abstract and CH 1 – items 272 to 281 IVb) NUBIKI: Barnabas Toth, Oct. 26, 2019 – CH2 – items 282 to 290 IVc) NUBIKI: Barnabas Toth, Oct. 26, 2019 – CH4 – items 291 to 308 V) UNIPI: Francesco D’Auria, Oct. 28, 2019 – CH1 (new section 1.2.1) – item 309 VI) IRSN: Christophe Herer, Oct. 29, 2019 – section 2.2.4 – item 310 VII) POLIMI: Francesco Di Maio, Oct. 29, 2019 – items 311 to 430 VIII) UNIPI: Marco Lanfredini, Oct. 30, 2019 – items 431 to 447 IX) KAERI: Kyoung-Ho Kang, Oct. 31, 2019 – items 448 to 497 X) KINS: Kyusik Do, Oct. 31, 2019 – items 498 to 530 2 XI) FRAMATOME & IRSN, Oct. 31, 2019 – items 531 to 606 XII) UNIV. LUXEMBOURG (via Herer), Oct. 31, 2019 – item 607 XIII) IRSN: Christophe Herer (related to CH 1-3), Nov. 1, 2019 – items 608 to 637 XIV) IRSN: Christophe Herer (related to CH 4), Nov. 1, 2019 – items 638 to 651 XV) ENEA: Fulvio Mascari (two files received, both here) Nov. 3, 2019 – items 652 to 701 Activity from rev-03 to rev-04 summarized starting at page 69
Comment to the Elsevier proposed Book Molten Corium Retention in Nuclear Reactors: Insights from experiments
No full textWater cooled nuclear reactors constitute almost 96% of the total nuclear reactors operating worldwide. Three major accidents in nuclear history i.e. TMI, Chernobyl and recent Fukushima have compelled nuclear scientists and engineers to have a relook at the safety of nuclear reactors. Past decade has seen an exponential growth on research contributed towards severe accident research. In this perspective, severe accident management strategies have been developed to retein the molten corium either insider the reactor vessel (called as in-vessel retention) or by cooling the corium debris in core catchers located outside the reactor vessel. One of the crucial aspects of molten corium retention is corium coolability in severe accident mitigation. Corium coolability is an extremely complex phenomenon due to presence of multiple components with different modes of direct and indirect heat transfer with phase change, and occurrence of multiple phases. In order to build understanding of these phenomena, extensive experimentation is needed. Conducting experiments at severe accident condition is a challenging task due to elevated temperatures and presence of radioactive materials. The aim of this book is to present to the scientific community, the physics behind several complex phenomena occurring during corium coolability that has been obtained through meticulous and challenging series of experiment at severe accident conditions, which have proved for in vessel retention and ex-vessel corium coolability in core catchers
Acknowledgements and Additional Notices (related to the J NED Special Issue 'Trends and Perspectives in Nuclear Thermal-hydraulics')
No full textThe decision to propose publishing the Special Issue (SI) was taken around February 2019; the importance of having it ready in time for the next International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), to be held in August 2019, soon became clear. This left very little time for concluding formal agreements, sending out invitations to authors, the subsequent preparation of the papers by the authors, the review process and ensuing publication. All this required a special commitment by the actors, authors, reviewers, editors and editorial staff involved. Sincere thanks are due first of all to the authors of the papers, including the commemorations. Their readiness to honor the memory of Bal Raj Sehgal, George Yadigaroglu and Geoffrey Hewitt is noted. The names of all the authors can be found in the list of contents. Contact authors, leading authors and scientists who stimulated the papers are listed in alphabetical order
Comment to the Elsevier Book A Survey of the Status of electricity generation in the world
No full textChapter 1 will be significantly updated with new data, because within last 3 years we have quite visible changes in electricity generation in the world. Also, the chapter will be increased in a number of pages up to 50%. New material for the Chapter will be partially based on the following papers: a) Pioro, I., Duffey, R.B., Kirillov, P.L., Pioro, R., Zvorykin, A., and Machrafi, R., 2019. Current Status and Future Developments in Nuclear-Power Industry of the World, ASME Journal of Nuclear Engineering and Radiation Science, Vol. 5, No. 2, 27 pages. Free download from: http://nuclearengineering.asmedigitalcollection.asme.org/article.aspx?articleID=2718229. b) Pioro, R., Zvorykin, A., Rachid, M., and Pioro, I., 2018. Study on Current Status and Future Developments in Nuclear-Power Industry of the World, Proceedings of the 26th International Conference On Nuclear Engineering (ICONE-26), July 22-26, London, England, Paper #82085, 14 pages. c) Pioro, R., Zvorykin, A., Machrafi, R., and Pioro, I., 2019. Current Achievements and Future Trends in Nuclear-Power Industry of the World, Proceedings of the 27th International 1 Updates and additions are yellow highlighted Conference On Nuclear Engineering (ICONE-27), May 19-24, Tsukuba, Ibaraki, Japan, Paper #1910, 10 pages. PART ONE GENERATION IV NUCLEAR-REACTOR CONCEPTS 35 Preface to Part One 35 2 INTRODUCTION: GENERATION IV INTERNATIONAL FORUM 37 I.L. Pioro 2.1 Origins of the Generation IV International Forum 37 2.2 Generation IV goals 38 2.3 Selection of Generation IV systems 39 2.4 Six Generation IV nuclear energy systems 40 2.5 Summary 52 Acknowledgments 54 References 54 Chapter 2 will be updated with new data, because within last 3 years we have some changes in Generation IV International Forum materials. Updated material for the chapter will be based on GIF website. 3 Very high-temperature reactor 55 X.L. Yan 3.1 Development history and current status 55 3.2 Technology overview 57 3.3 Detailed technical description 60 3.4 Applications and economics 77 3.5 Summary 87 Acronyms 87 References 89 Chapter 3 looks good as for now. However, I. Pioro will add new material on possible power cycles for very high temperature reactors in Appendices. New material for the Chapter will be based on the following paper: a) Mahdi, M., Popov, R., and Pioro, I., 2018. Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs, Proceedings of the 26th International Conference On Nuclear Engineering (ICONE-26), July 22-26, London, England, Paper #81618, 9 pages.
Evaluation of an ELSEVIER book proposal - Nuclear Safety
No full textActivity consisting in answering a reviewer questionnaire proposed by Elsevie
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