Nuclear Back-End and Transmutation Technology for Waste Disposal : (Kayıt no. 15725)
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| Sabit Uzunluktaki Kontrol Alanı | 10898nam a22004333i 4500 |
| 001 - KONTROL NUMARASI | |
| Control Dosyası | EBC6422608 |
| 003 - KONTROL NUMARASI KİMLİĞİ | |
| Kontrol Alanı | MiAaPQ |
| 005 - EN SON İŞLEM TARİHİ ve ZAMANI | |
| Kontrol Alanı | 20220623112332.0 |
| 006 - FIXED-LENGTH DATA ELEMENTS--ADDITIONAL MATERIAL CHARACTERISTICS | |
| fixed length control field | m o d | |
| 007 - PHYSICAL DESCRIPTION FIXED FIELD--GENERAL INFORMATION | |
| fixed length control field | cr cnu|||||||| |
| 008 - SABİT UZUNLUKTAKİ VERİ ÖGELERİ - GENEL BİLGİ | |
| Sabit Alan | 220617s2014 xx o ||||0 eng d |
| 020 ## - ISBN - ULUSLARARASI STANDART KİTAP NUMARASI | |
| Isbn | 9784431551119 |
| -- | (electronic bk.) |
| 020 ## - ISBN - ULUSLARARASI STANDART KİTAP NUMARASI | |
| Cancelled/invalid ISBN | 9784431551102 |
| 035 ## - SİSTEM KONTROL NUMARASI | |
| Sistem Kontrol Numarası | (MiAaPQ)EBC6422608 |
| 035 ## - SİSTEM KONTROL NUMARASI | |
| Sistem Kontrol Numarası | (Au-PeEL)EBL6422608 |
| 035 ## - SİSTEM KONTROL NUMARASI | |
| Sistem Kontrol Numarası | (OCoLC)1231609988 |
| 040 ## - KATALOGLAMA KAYNAĞI | |
| Özgün Kataloglama Kurumu | MiAaPQ |
| Kataloglama Dili | eng |
| Açıklama Kuralları | rda |
| -- | pn |
| Çeviri Kurumu | MiAaPQ |
| Değiştiren Kurum | MiAaPQ |
| 050 #4 - SINIFLAMA ve YER NUMARASI | |
| Sınıflama Numarası | QC795.32.R3 |
| 100 1# - KİŞİ ADI | |
| Yazar Adı (Kişi adı) | Nakajima, Ken. |
| 245 10 - ESER ADI BİLDİRİMİ | |
| Başlık | Nuclear Back-End and Transmutation Technology for Waste Disposal : |
| Alt Eseradı vb. | Beyond the Fukushima Accident. |
| 264 #1 - PRODUCTION, PUBLICATION, DISTRIBUTION, MANUFACTURE, AND COPYRIGHT NOTICE | |
| Place of production, publication, distribution, manufacture | Tokyo : |
| Name of producer, publisher, distributor, manufacturer | Springer Japan, |
| Date of production, publication, distribution, manufacture, or copyright notice | 2014. |
| 264 #4 - PRODUCTION, PUBLICATION, DISTRIBUTION, MANUFACTURE, AND COPYRIGHT NOTICE | |
| Date of production, publication, distribution, manufacture, or copyright notice | �2015. |
| 300 ## - FİZİKSEL TANIMLAMA | |
| Sayfa, Cilt vb. | 1 online resource (331 pages) |
| 336 ## - CONTENT TYPE | |
| Content type term | text |
| Content type code | txt |
| Source | rdacontent |
| 337 ## - MEDIA TYPE | |
| Media type term | computer |
| Media type code | c |
| Source | rdamedia |
| 338 ## - CARRIER TYPE | |
| Carrier type term | online resource |
| Carrier type code | cr |
| Source | rdacarrier |
| 505 0# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | Intro -- Foreword -- Preface -- Cooperators -- Contents -- Part I: Basic Research for Nuclear Transmutation and Disposal: Physical and Chemical Studies Relevant to Nuclear Transmutation and Disposal Such as Measurement or Evaluation of Nuclear Cross-Section Data -- Chapter 1: Nuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical Ap... -- 1.1 Introduction -- 1.2 Calculation Method -- 1.2.1 Reaction via Giant Dipole Resonance -- 1.2.2 High-Energy Photons Obtained by Laser Compton Scattering -- 1.2.3 Setup of the Calculation for 137Cs -- 1.3 Results and Discussion -- 1.3.1 Nuclear Transmutation of 137Cs with Laser Compton Scattering -- 1.3.2 Comparison with Other Nuclides -- 1.4 Conclusion -- References -- Chapter 2: Recent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear M... -- 2.1 Introduction -- 2.2 Neutron Resonance Densitometry -- 2.2.1 The Concept of NRD -- 2.2.2 A Rough Draft of an NRD Facility -- 2.3 Development of a gamma-Ray Spectrometer for NRCA/PGA -- 2.4 Experiments for NRD Developments -- 2.5 Summary -- References -- Chapter 3: Development of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Ap... -- 3.1 Introduction -- 3.2 Experiment -- 3.3 Results and Discussion -- 3.4 Summary -- References -- Chapter 4: Development of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Appli... -- 4.1 Introduction -- 4.2 Calculational Model and Condition -- 4.3 Numerical Results and Discussion -- 4.4 Conclusion -- References -- Chapter 5: Precise Measurements of Neutron Capture Cross Sections for LLFPs and MAs -- 5.1 Introduction -- 5.2 Present Situation of Data for LLFPs and MAs -- 5.3 Measurement Activities by the Activation Method. |
| 505 8# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | 5.4 Measurement Activities at J-PARC/MLF/ANNRI -- 5.5 Summary -- References -- Chapter 6: Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9x9 Fuel -- 6.1 Introduction -- 6.2 Analytical Procedure -- 6.3 Future Plans -- 6.4 Conclusion -- References -- Part II: Development of ADS Technologies: Current Status of Accelerator-Driven System Development -- Chapter 7: Contribution of the European Commission to a European Strategy for HLW Management Through Partitioning and Transmut... -- 7.1 Introduction -- 7.2 MYRRHA: A Flexible Fast-Spectrum Irradiation Facility -- 7.3 The MYRRHA Accelerator -- 7.4 Design of the Core and Primary System -- 7.5 MYRRHA, A Research Tool in Support of the European Roadmap for PandT -- 7.6 Conclusions -- References -- Chapter 8: Design of J-PARC Transmutation Experimental Facility -- 8.1 Introduction -- 8.2 Outline of the Transmutation Experimental Facility -- 8.2.1 Outline of TEF-T -- 8.2.2 Outline of TEF-P -- 8.3 Design of Spallation Target for TEF-T -- 8.4 Conclusion -- References -- Chapter 9: Accelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI) -- 9.1 Introduction -- 9.2 Experimental Settings -- 9.2.1 Uranium-Loaded ADS Experiments -- 9.2.2 Thorium-Loaded ADS Benchmarks -- 9.3 Results and Discussion -- 9.3.1 Uranium-Loaded ADS Experiments -- 9.3.1.1 Static Experiments -- 9.3.1.2 Kinetic Experiments -- 9.3.2 Thorium-Loaded ADS Experiments -- 9.3.2.1 Static Experiments -- 9.3.2.2 Kinetic Experiments -- 9.4 Conclusions -- References -- Part III: Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material Engineering- Related Technologies for ADS and Other Advanced Reactor Systems. |
| 505 8# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | Chapter 10: Heat Transfer Study for ADS Solid Target: Surface Wettability and Its Effect on a Boiling Heat Transfer -- 10.1 Introduction -- 10.2 Surface Wettability Change by Irradiation -- 10.2.1 Sample and Irradiation Facility -- 10.2.1.1 Ultraviolet -- 10.2.1.2 Gamma Rays (gamma-Rays) -- 10.2.1.3 Proton Beam -- 10.2.2 Contact Angle Measurement -- 10.2.3 Effect of Irradiations on Surface Wettability -- 10.3 Effect of Boiling Heat Transfer on Surface Wettability -- 10.3.1 Experimental Setup and Procedure -- 10.3.2 Results and Discussion -- 10.4 Conclusions -- References -- Chapter 11: Experimental Study of Flow Structure and Turbulent Characteristics in Lead-Bismuth Two-Phase Flow -- 11.1 Introduction -- 11.2 Measurement Techniques -- 11.2.1 Four-Sensor Probe -- 11.2.2 Electromagnetic Probe -- 11.3 Experimental Setup -- 11.4 Results and Discussion -- 11.4.1 Radial Profiles of Two-Phase Flow Properties -- 11.4.2 Comparison of Interfacial Area Concentration -- 11.4.3 Bubble-Induced Turbulence -- 11.5 Conclusions -- References -- Part IV: Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADS -- Chapter 12: Theory of Power Spectral Density and Feynman-Alpha Method in Accelerator-Driven System and Their Higher-Order Mode... -- 12.1 Introduction -- 12.2 Theory of Feynman-(Sa(B Method in ADS -- 12.3 Theory of Power Spectral Density in ADS -- 12.4 Conclusions -- References -- Chapter 13: Study on Neutron Spectrum of Pulsed Neutron Reactor -- 13.1 Introduction -- 13.2 Experiment at KUCA and Measured Results -- 13.3 Analysis and Discussion of Neutron Flux -- 13.3.1 Neutron Flux Distribution -- 13.3.2 Neutron Spectrum -- 13.4 Conclusions -- References -- Part V: Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel Cycle. |
| 505 8# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | Chapter 14: Application of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy Supply -- 14.1 Introduction -- 14.2 RBWR System -- 14.2.1 Overview -- 14.2.2 Core Calculation Method -- 14.2.3 RBWR-AC -- 14.2.4 RBWR-TB -- 14.2.5 RBWR-TB2 -- 14.3 Conclusion -- References -- Chapter 15: Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core -- 15.1 Introduction -- 15.2 Issues and Measures Against the Uranium-Free TRU Metallic Fast Reactor Core -- 15.3 Parametric Analysis on the Effect of Measures -- 15.3.1 Parametric Analysis Methodology -- 15.3.2 Analysis Results for Doppler Feedback Enhancement -- 15.3.3 Analysis Results for Burnup Reactivity Swing Reduction -- 15.4 Developed Uranium-Free TRU Metallic Core -- 15.4.1 Specification Selected for Uranium-Free TRU Metallic Core -- 15.4.2 Performance of the Uranium-Free TRU Metallic Core -- 15.5 Conclusions -- References -- Chapter 16: Enhancement of Transmutation of Minor Actinides by Hydride Target -- 16.1 Introduction -- 16.2 Design of MA-Hydride Target -- 16.3 Design of Core with MA-Hydride Target -- 16.4 Transmutation Calculation -- 16.5 Discussion -- 16.6 Conclusions -- References -- Chapter 17: Method Development for Calculating Minor Actinide Transmutation in a Fast Reactor -- 17.1 Introduction -- 17.2 MA Transmutation Core Concept -- 17.3 MA Transmutation Rate -- 17.4 Sensitivity Calculation Method -- 17.4.1 Sensitivity to Infinite-Dilution Cross Section -- 17.4.2 Burn-up Sensitivity -- 17.4.3 Dependence of Sensitivities on Numbers of Energy Groups -- 17.5 Reduction of Prediction Uncertainty -- 17.6 Conclusion -- References -- Chapter 18: Overview of European Experience with Thorium Fuels -- 18.1 Introduction -- 18.2 Thorium European Research Programme History -- 18.3 Th-MOX Fuels Irradiated in LWR Conditions -- 18.4 The Molten Salt Reactor. |
| 505 8# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | 18.5 Conclusions -- References -- Part VI: Reactor Physics Studies for Post- Fukushima Accident Nuclear Energy: Studies from the Reactor Physics Aspect for Back-End Issues Such as Treatment of Debris from the Fukushima Accident -- Chapter 19: Transmutation Scenarios after Closing Nuclear Power Plants -- 19.1 Introduction -- 19.2 Methodology -- 19.2.1 Neutronics Calculation -- 19.2.2 Scenario Analysis -- 19.2.3 Transmutation Half-Life -- 19.3 ADS Design for Pu Transmutation -- 19.3.1 Reference ADS (MA-ADS) -- 19.3.2 Assumption of Pu Feed -- 19.3.3 Result of One-Batch Core -- 19.3.4 Result of six-Batch Core -- 19.4 Scenario Analysis -- 19.4.1 Result of LWR-OT -- 19.4.2 Result of LWR-PuT -- 19.4.3 Result of FR -- 19.4.4 Result of ADS -- 19.4.5 Result of FR+ADS -- 19.4.6 Impact on the Repository -- 19.4.7 Discussion -- 19.5 Conclusion -- Nomenclature -- References -- Chapter 20: Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Mater... -- 20.1 Introduction -- 20.2 Method of Calculating Sensitivity Coefficients -- 20.3 Sensitivity Analyses -- 20.3.1 Analyses Conditions -- 20.3.2 Target Nuclides of Sensitivity Analyses -- 20.3.3 Results of Sensitivity Analyses -- 20.3.4 Sensitivity Analysis Using the Initial Composition Based on Measured Data -- 20.4 Conclusion -- References -- Chapter 21: Options of Principles of Fuel Debris Criticality Control in Fukushima Daiichi Reactors -- 21.1 Introduction -- 21.2 Present Condition of 1FNPS Fuel Debris -- 21.3 Criticality Characteristics of Fuel Debris -- 21.4 Options of Criticality Control Principles -- 21.4.1 Prevention of Criticality by Poison or Dry Process -- 21.4.2 Prevention of Criticality by Monitoring -- 21.4.3 Prevention of Severe Consequence -- 21.4.4 Risk Assessment -- 21.5 Conclusions -- References. |
| 505 8# - İÇİNDEKİLER NOTU | |
| İçindekiler Notu | Chapter 22: Modification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality Control. |
| 590 ## - LOCAL NOTE (RLIN) | |
| Local note | Electronic reproduction. Ann Arbor, Michigan : ProQuest Ebook Central, 2022. Available via World Wide Web. Access may be limited to ProQuest Ebook Central affiliated libraries. |
| 655 #4 - INDEX TERM--GENRE/FORM | |
| Genre/form data or focus term | Electronic books. |
| 776 08 - ADDITIONAL PHYSICAL FORM ENTRY | |
| Display text | Print version: |
| Main entry heading | Nakajima, Ken |
| Title | Nuclear Back-End and Transmutation Technology for Waste Disposal |
| Place, publisher, and date of publication | Tokyo : Springer Japan,c2014 |
| International Standard Book Number | 9784431551102 |
| 797 2# - LOCAL ADDED ENTRY--CORPORATE NAME (RLIN) | |
| Corporate name or jurisdiction name as entry element | ProQuest (Firm) |
| 856 40 - ELEKTRONİK YER ve ERİŞİM | |
| Kaynak Tanımlayıcı (URL) | <a href="https://ebookcentral.proquest.com/lib/ostimteknik/detail.action?docID=6422608">https://ebookcentral.proquest.com/lib/ostimteknik/detail.action?docID=6422608</a> |
| Public note | Click to View |
| 588 ## - SOURCE OF DESCRIPTION NOTE | |
| Ekli Tam Metin | Description based on publisher supplied metadata and other sources. |
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