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Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code / / prepared by Fulvio Mascari [and five others]
| Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code / / prepared by Fulvio Mascari [and five others] |
| Autore | Mascari Fulvio |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactors - Design and construction
Light water reactors - Design and construction Pressurized water reactors - Design and construction Nuclear reactors - Analysis Nuclear reactors - Testing |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the OSU MASLWR 001 and 002 tests by using the TRACE code |
| Record Nr. | UNINA-9910707643603321 |
Mascari Fulvio
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Application of the Principle of Defence in Depth in Nuclear Safety to Small Modular Reactors : Addendum to INSAG 10
| Application of the Principle of Defence in Depth in Nuclear Safety to Small Modular Reactors : Addendum to INSAG 10 |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Havertown : , : International Atomic Energy Agency, , 2024 |
| Descrizione fisica | 1 online resource (22 pages) |
| Collana | INSAG Series |
| Soggetto topico |
Nuclear reactors - Safety measures
Nuclear reactors - Design and construction |
| ISBN |
9789201219244
9201219245 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | EXECUTIVE SUMMARY -- 1. INTRODUCTION -- 2. SMALL MODULAR REACTOR DESIGNS -- 3. APPROACH OF INSAG-10 TO DEFENCE IN DEPTH -- 4. APPLICATION TO SMALL MODULAR REACTORS -- 4.1. Passive features of SMRs compared with large evolutionary nuclear power plants -- 4.2. Common cause failures -- 4.3. Defence in depth -- 4.4. Graded approach -- 4.5. Performance and prescriptive based regulation -- 5. CONCLUSIONS AND RECOMMENDATIONS -- REFERENCES -- MEMBERS OF THE INTERNATIONAL NUCLEAR SAFETY ADVISORY GROUP -- PUBLICATIONS OF THE INTERNATIONAL NUCLEAR SAFETY ADVISORY GROUP |
| Record Nr. | UNINA-9911026145703321 |
| Havertown : , : International Atomic Energy Agency, , 2024 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Dinamica e schermatura dei reattori nucleari di potenza / ENEL
| Dinamica e schermatura dei reattori nucleari di potenza / ENEL |
| Pubbl/distr/stampa | Roma : ENEL, 1979 |
| Descrizione fisica | 1 volume (various pagings) : ill. ; 30 cm |
| Disciplina | 621.483 |
| Altri autori (Enti) | Ente nazionale per l'energia elettrica.Direzione studi e ricerche |
| Soggetto topico |
Nuclear reactors - Dynamics
Nuclear reactors - Shielding Nuclear reactors - Design and construction |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione |
ita
eng mul |
| Record Nr. | UNISALENTO-991004363820207536 |
| Roma : ENEL, 1979 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. del Salento | ||
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Enabling advanced reactors and a legislative hearing on S. 2795, the Nuclear Energy Innovation and Modernization Act : hearing before the Subcommittee on Clean Air and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Fourteenth Congress, second session, April 21, 2016
| Enabling advanced reactors and a legislative hearing on S. 2795, the Nuclear Energy Innovation and Modernization Act : hearing before the Subcommittee on Clean Air and Nuclear Safety of the Committee on Environment and Public Works, United States Senate, One Hundred Fourteenth Congress, second session, April 21, 2016 |
| Pubbl/distr/stampa | Washington : , : U.S. Government Publishing Office, , 2016 |
| Descrizione fisica | 1 online resource (iii, 131 pages) : illustrations |
| Collana | S. hrg. |
| Soggetto topico |
Fast reactors - Government policy - United States
Nuclear reactors - Design and construction Nuclear facilities - Licenses - Fees - United States Nuclear industry - Licenses - Fees - United States |
| Soggetto genere / forma | Legislative hearings. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Enabling Advanced Reactors and a Legislative Hearing on S. 2795, the Nuclear Energy Innovation and Modernization Act |
| Record Nr. | UNINA-9910708306103321 |
| Washington : , : U.S. Government Publishing Office, , 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Feasibility study preparation for new research reactor programmes
| Feasibility study preparation for new research reactor programmes |
| Pubbl/distr/stampa | Vienna : , : International Atomic Energy Agency, , [2018] |
| Descrizione fisica | 1 online resource (38 pages) |
| Disciplina | 621.483 |
| Collana | IAEA Nuclear Energy Series |
| Soggetto topico |
Nuclear reactors
Nuclear reactors - Design and construction Feasibility studies |
| Soggetto genere / forma | Electronic books. |
| ISBN | 92-0-146819-9 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910511704703321 |
| Vienna : , : International Atomic Energy Agency, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Feasibility study preparation for new research reactor programmes
| Feasibility study preparation for new research reactor programmes |
| Pubbl/distr/stampa | Vienna : , : International Atomic Energy Agency, , [2018] |
| Descrizione fisica | 1 online resource (38 pages) |
| Disciplina | 621.483 |
| Collana | IAEA Nuclear Energy Series |
| Soggetto topico |
Nuclear reactors
Nuclear reactors - Design and construction Feasibility studies |
| ISBN | 92-0-146819-9 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910793324003321 |
| Vienna : , : International Atomic Energy Agency, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Feasibility study preparation for new research reactor programmes
| Feasibility study preparation for new research reactor programmes |
| Pubbl/distr/stampa | Vienna : , : International Atomic Energy Agency, , [2018] |
| Descrizione fisica | 1 online resource (38 pages) |
| Disciplina | 621.483 |
| Collana | IAEA Nuclear Energy Series |
| Soggetto topico |
Nuclear reactors
Nuclear reactors - Design and construction Feasibility studies |
| ISBN | 92-0-146819-9 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910816975803321 |
| Vienna : , : International Atomic Energy Agency, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Final safety evaluation report related to the certification of the economic simplified boiling-water reactor standard design / / Office of New Reactors
| Final safety evaluation report related to the certification of the economic simplified boiling-water reactor standard design / / Office of New Reactors |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of New Reactors, , 2014 |
| Descrizione fisica | 1 online resource (6 volumes) : illustrations + + supplement |
| Soggetto topico |
Boiling water reactors
Nuclear reactors - Design and construction Nuclear reactors - Safety measures Nuclear power plants - Licenses Standardization |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Certification of the economic simplified boiling-water reactor standard design |
| Record Nr. | UNINA-9910705302403321 |
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of New Reactors, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Fundamentals of magnetic thermonuclear reactor design / / edited by Vasilij Glukhikh, Oleg Filatov, Boris Kolbasov
| Fundamentals of magnetic thermonuclear reactor design / / edited by Vasilij Glukhikh, Oleg Filatov, Boris Kolbasov |
| Pubbl/distr/stampa | Duxford, England : , : Woodhead Publishing, , [2018] |
| Descrizione fisica | 1 online resource (476 pages) |
| Disciplina | 621.4832 |
| Collana | Woodhead Publishing Series in Energy |
| Soggetto topico | Nuclear reactors - Design and construction |
| ISBN |
0-08-102471-1
0-08-102470-3 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910583046303321 |
| Duxford, England : , : Woodhead Publishing, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors : Volume 3: Procedures and Applications
| Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors : Volume 3: Procedures and Applications |
| Autore | D'Auria Francesco |
| Edizione | [2nd ed.] |
| Pubbl/distr/stampa | San Diego : , : Elsevier Science & Technology, , 2024 |
| Descrizione fisica | 1 online resource (818 pages) |
| Disciplina | 621.4834 |
| Altri autori (Persone) | HassanYassin A |
| Collana | Woodhead Publishing Series in Energy Series |
| Soggetto topico |
Nuclear reactors - Design and construction
Nuclear engineering |
| ISBN |
9780323856096
0323856098 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Front Cover -- Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors -- Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors: Volume 3: Procedures and Applications -- Copyright -- Dedication -- Contents -- List of contributors -- Contributors for volumes 1, 2 and 3 -- Foreword -- Glossary -- Preface to the first edition of the book -- Preface to the second edition of the book -- Acknowledgments (for the past) and wishes (for the future) -- 18 - Subchannel modeling and codes -- Foreword -- 18.1 Introduction -- 18.1.1 A historical perspective -- 18.2 The framework for subchannel analyses -- 18.2.1 Key approaches for modeling -- 18.2.2 The integration domain -- 18.3 The balance equations -- 18.4 The constitutive models -- 18.4.1 Flow regime map -- 18.4.2 Pressure drop -- 18.4.2.1 Two-phase flow pressure drop -- 18.4.3 Heat transfer models -- 18.4.3.1 CHF models -- 18.4.4 Inter-subchannel exchange mechanisms, decoupling, and modeling -- 18.4.4.1 Decoupling of single-phase flow inter-subchannel exchange terms -- Correlations having general applicability -- Phenomenology and correlations in single-phase flow considering the presence of spacer grids -- 18.4.4.2 Decoupling of two-phase flow inter-subchannel exchange terms -- Void drift -- Two-phase flow turbulent mixing -- Spacer forced two-phase cross-flow -- 18.5 The codes -- 18.5.1 Focus on LMR codes -- 18.6 The validation -- 18.6.1 Experimental challenges in subchannel analysis code validations -- 18.6.2 Specific validation cases and needs -- 18.6.2.1 Modeling and validation needs -- Scaling needs -- 18.7 Applications and achievements -- 18.7.1 The role of CFD modeling and codes -- 18.7.2 The role of system codes modeling -- 18.7.3 Application of subchannel analysis codes to the whole core -- 18.7.4 The ocean motion -- 18.8 Conclusions.
18.8.1 Chapter summary remarks: Subchannel analysis codes limitations -- Exercises and questions -- Acknowledgments -- 19 - Containment thermal hydraulics -- Foreword -- 19.1 Introduction (evolution and role of containment) -- 19.2 Containment in existing water-cooled nuclear reactors -- 19.2.1 PWR containment -- 19.2.2 Containment for BWR -- 19.2.3 Containment in VVER-1000, CANDU, and evolutionary PWR -- 19.2.4 Containment/confinement in VVER-440 -- 19.2.5 Containment/confinement in RBMK -- 19.3 Containment for advanced reactors (AP-1000 and ESBWR) -- 19.3.1 AP-1000 -- 19.3.2 ESBWR -- 19.4 Containment in SMR (NuScale, SMR160, CAREM, SMART, etc.) -- 19.5 Phenomena in the containment during transients -- 19.5.1 Hydrogen behavior in containment -- 19.6 Computer codes for simulation of containment -- 19.7 Scaling of containment phenomena -- 19.8 Test facilities for experimental investigation of containment phenomena -- 19.9 Summary and conclusions -- Exercises and questions -- Acknowledgment -- 20 - Numerical methods in nuclear thermal hydraulics -- Foreword -- 20.1 An introduction to numerical methods: basic concepts on the discretization of partial differential equations -- 20.1.1 Formulation of exact, discrete approximations (DA) -- 20.1.2 Truncation of exact difference approximations (DA) and the equations really solved, local truncation error (TE), and consis ... -- 20.1.3 The introduction of artificial viscosity -- 20.1.4 Phase error in the solution of DA -- 20.1.5 The meaning and control of numerical, non-physical solution oscillations -- 20.2 The solution of parabolic PDE -- 20.2.1 The approximation of the solution of time-dependent problems, step-by-step splitting -- 20.2.2 Explicit and implicit approximations in one and multiple space dimensions: alternating direction implicit (ADI) methods -- 20.3 The solution of elliptic PDE. 20.3.1 Characteristics of the linear system -- 20.3.2 Memory and computational time requirements for the solution of the linear system -- 20.3.3 Basic concepts on iterative methods -- 20.3.4 Stationary iterative methods -- 20.3.5 Krylov space-based iterative methods -- 20.3.5.1 The conjugate gradient method -- 20.3.5.2 Preconditioning -- 20.3.5.3 Matrix-free implementation -- 20.3.5.4 Non-SPD matrices: CG over normal equations -- 20.3.5.5 GMRES (Generalized Minimal Residual [method]) -- 20.3.5.6 Other methods for non-SPD matrices -- 20.3.5.7 Pure three-diagonal systems -- 20.3.5.8 Network three-diagonal systems -- 20.3.5.9 Solution of elliptic equations using ADI methods -- 20.3.6 Parallel implementation of direct and iterative methods -- 20.4 The solution of hyperbolic PDE -- 20.4.1 First-order equations, scalar transport -- 20.4.2 The method of characteristics -- 20.4.3 Numerical approximations to the solution of hyperbolic PDE -- 20.5 The validity of computer codes solutions -- 20.6 Automatic computation of sensitivities to parameters in TH codes -- Exercises and questions -- Acknowledgment -- 21 - Scaling in nuclear thermal hydraulics -- Foreword -- Part 1: Scaling background -- 21.1 Introduction -- 21.1.1 The regulatory role of scaling analyses -- 21.1.2 Scaling objectives and general design framework -- 21.1.3 The executive summary from S-SOAR4 -- 21.1.3.1 Scaling distortion -- 21.1.3.2 Scaling analysis for the safety review process -- 21.1.3.3 Scaling methods -- 21.1.3.4 Role of experiments in scaling -- 21.1.3.5 Counterpart test (CT) and similar test (ST) -- 21.1.3.6 Role and characteristics of the system code -- 21.1.3.7 Scaling in uncertainty methods -- 21.1.3.8 Scaling roadmaps -- 21.1.3.9 Role of CFD tools for multi-dimensional and multi-scale phenomena -- Part 2: Scaling techniques (approaches and methods) -- Outline placeholder. 21.2 Scaling techniques -- 21.2.1 Scaling approaches -- 21.2.2 Scaling methods -- 21.2.2.1 Scaling methods used to investigate system phenomena -- 21.2.3 H2TS, FSA, and DSS scaling methods -- 21.2.3.1 Theory -- 21.2.3.2 Hierarchical two-tiered scaling (H2TS) -- 21.2.3.3 Fractional scaling analysis (FSA) -- 21.2.3.4 Dynamical system scaling (DSS) -- Part 3: Scaling database -- 21.3 Scaling database of experiments -- 21.3.1 Roles and requirements for experiments in scaling -- 21.3.2 Scaling distortion -- 21.3.3 Introduction to SETF -- 21.3.4 Examples of SETF -- 21.3.5 Introduction to IETF -- 21.3.6 Examples of IETF -- 21.3.6.1 Current PWR-related facilities -- 21.3.6.2 Current BWR-related facilities -- 21.3.6.3 Current VVER-related facilities -- 21.3.6.4 Current designs related IETF scaling considerations -- Time scaling -- Height scaling -- Volumetric scaling -- Pressure scaling -- Nuclear core simulator scaling -- Number of loop scaling and main coolant lines scaling -- Fluid scaling -- Recirculation and jet-pump scaling -- 21.3.6.5 Advanced-design-related IETF scaling considerations -- 21.3.7 SETF and IETF for phenomena in containment -- 21.3.7.1 Scaling considerations related to the PCV-IETF PWR -- Time scaling -- Volumetric scaling -- Height scaling -- Material scaling -- Compartment subdivision and interconnection among compartments -- Compartment shape scaling -- Energy-release scaling into PCV -- 21.3.7.2 Advanced reactor design considerations -- Part 4: Scaling achievements -- 21.4 Scaling extrapolation methods -- 21.4.1 General remarks -- 21.4.2 Introduction -- 21.4.2.1 Scaling and integral test facilities -- 21.4.2.2 The scaling issue -- 21.4.2.3 The concept of Kv scaling -- 21.4.2.4 Goals and limitations of Kv scaling -- 21.4.2.5 A literature review of applications of Kv scaling -- 21.4.3 The Kv-scaled SCUP methodology. 21.4.3.1 Scaling of nodalizations -- 21.4.3.2 Validation of the methodology with a counterpart exercise at the PKL and LSTF facilities -- 21.4.4 Applications of the methodology -- 21.4.4.1 Application of the methodology for the qualification of a full NPP model -- 21.4.4.2 The impact of scale on the uncertainties -- 21.4.5 Forthcoming roles of Kv-scaled calculations -- 21.4.5.1 Support to test design using hybrid calculation results -- 21.4.5.2 The impact of scale on the figures of merit -- 21.4.5.3 Perfecting nuclear power plant model qualification -- 21.5 Conclusions and recommendations from S-SOAR6 -- 21.5.1 Key findings -- 21.5.2 Recommendations -- 21.6 Conclusions and achievements -- Exercises and questions -- 22 - Good practices in V& -- V for system thermal-hydraulic codes -- Foreword -- 22.1 Introduction -- 22.1.1 Framework -- 22.2 Scope for the SYS TH code and requirements -- 22.2.1 Domain of simulation -- 22.2.2 Precision objective -- 22.2.3 Attribute for safety analyses -- 22.2.3.1 Scaling requirements -- 22.3 SYS TH code development process -- 22.3.1 Physical models -- 22.3.1.1 Fundamental models for thermal hydraulics -- 22.3.1.2 Special thermal-hydraulics models -- 22.3.1.3 Physical models for non-thermal-hydraulics systems -- 22.3.2 Numerics -- 22.3.3 Code implementation -- 22.3.3.1 Code structure -- 22.3.3.2 Programming -- 22.3.3.3 Software quality engineering (SQE) -- 22.3.4 Code assessment strategy within the development process -- 22.3.4.1 State of the art -- 22.3.5 Code manual -- 22.3.6 Life cycle -- 22.3.6.1 Quality assurance -- 22.4 Verification -- 22.4.1 Numerical algorithm and numerical solution -- 22.4.1.1 Numerical scheme -- 22.4.1.2 Verification matrix for numerical algorithm and solution -- 22.4.1.3 Accuracy definition and numerical error estimation -- 22.4.1.4 Checklist for review and inspection -- 22.4.2 Source code. 22.4.2.1 Tools for verification. |
| Record Nr. | UNINA-9911045226403321 |
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D'Auria Francesco
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| San Diego : , : Elsevier Science & Technology, , 2024 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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