Author: Mark David DeHart
Publisher: Frontiers Media SA
ISBN: 283253094X
Category : Technology & Engineering
Languages : en
Pages : 146
Book Description
Benchmark Experiments, Development and Needs in Support of Advanced Reactor Design
Author: Mark David DeHart
Publisher: Frontiers Media SA
ISBN: 283253094X
Category : Technology & Engineering
Languages : en
Pages : 146
Book Description
Publisher: Frontiers Media SA
ISBN: 283253094X
Category : Technology & Engineering
Languages : en
Pages : 146
Book Description
Nuclear Materials Safety Management Volume II
Author: Leslie J. Jardine
Publisher: Springer Science & Business Media
ISBN: 9401145016
Category : Science
Languages : en
Pages : 248
Book Description
LESLIE J. JARDINE Lmvrence Livermore National LaboratOlY Livermore, CA 94551 U. S. A. The Advanced Research Workshop (ARW) on Nuc1ear Materials Safety held lune 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 V. S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuc1ear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuc1ear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, inc1uding vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This AR W completed discussions by experts of the nuc1ear materials safety topics that were not covered in the previous, companion ARW on Nuc1ear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuc1ear material aspects of the storage and disposition operations required for excess HEV and plutonium (see Fig. 1, Opening Remarks).
Publisher: Springer Science & Business Media
ISBN: 9401145016
Category : Science
Languages : en
Pages : 248
Book Description
LESLIE J. JARDINE Lmvrence Livermore National LaboratOlY Livermore, CA 94551 U. S. A. The Advanced Research Workshop (ARW) on Nuc1ear Materials Safety held lune 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 V. S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuc1ear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuc1ear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, inc1uding vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This AR W completed discussions by experts of the nuc1ear materials safety topics that were not covered in the previous, companion ARW on Nuc1ear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuc1ear material aspects of the storage and disposition operations required for excess HEV and plutonium (see Fig. 1, Opening Remarks).
Nuclear Engineering Handbook
Author: Kenneth D. Kok
Publisher: CRC Press
ISBN: 1482215934
Category : Science
Languages : en
Pages : 978
Book Description
Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
Publisher: CRC Press
ISBN: 1482215934
Category : Science
Languages : en
Pages : 978
Book Description
Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
International Conference on Nuclear Data for Science and Technology
Author: Robert C. Haight
Publisher: American Institute of Physics
ISBN: 9780735402546
Category : Science
Languages : en
Pages : 734
Book Description
All papers were peer reviewed. This conference focused on the broad field of nuclear data, their production, dissemination, and testing, with the goal of providing reliable data for applications such a nuclear fission and fusion energy, accelerators, spallation neutron sources, nuclear medicine, environment, space, non-proliferation, nuclear safety, astrophysics and cosmology, and basic research.
Publisher: American Institute of Physics
ISBN: 9780735402546
Category : Science
Languages : en
Pages : 734
Book Description
All papers were peer reviewed. This conference focused on the broad field of nuclear data, their production, dissemination, and testing, with the goal of providing reliable data for applications such a nuclear fission and fusion energy, accelerators, spallation neutron sources, nuclear medicine, environment, space, non-proliferation, nuclear safety, astrophysics and cosmology, and basic research.
Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201192215
Category : Business & Economics
Languages : en
Pages : 364
Book Description
This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material (2018 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit, shipment after storage and receipt at the final destination of packages. The Advisory Material is not a stand-alone text. It is to be used concurrently as a companion to the IAEA Safety Standards Series No. SSR-6 (Rev. 1) and each paragraph of this guide is numbered correspondingly to the paragraph of the Regulations to which it most directly relates.
Publisher: International Atomic Energy Agency
ISBN: 9201192215
Category : Business & Economics
Languages : en
Pages : 364
Book Description
This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material (2018 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit, shipment after storage and receipt at the final destination of packages. The Advisory Material is not a stand-alone text. It is to be used concurrently as a companion to the IAEA Safety Standards Series No. SSR-6 (Rev. 1) and each paragraph of this guide is numbered correspondingly to the paragraph of the Regulations to which it most directly relates.
Criticality Safety in the Handling of Fissile Material
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201189222
Category : Technology & Engineering
Languages : en
Pages : 104
Book Description
The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.
Publisher: International Atomic Energy Agency
ISBN: 9201189222
Category : Technology & Engineering
Languages : en
Pages : 104
Book Description
The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.
Handbook of Nuclear Engineering
Author: Dan Gabriel Cacuci
Publisher: Springer Science & Business Media
ISBN: 0387981306
Category : Science
Languages : en
Pages : 3701
Book Description
This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
Publisher: Springer Science & Business Media
ISBN: 0387981306
Category : Science
Languages : en
Pages : 3701
Book Description
This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop
Author: Peter Rullhusen
Publisher: World Scientific
ISBN: 9814477796
Category : Science
Languages : en
Pages : 300
Book Description
This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.
Publisher: World Scientific
ISBN: 9814477796
Category : Science
Languages : en
Pages : 300
Book Description
This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.
Nuclear Data Needs for Generation IV Nuclear Energy Systems
Author: P. Rullhusen
Publisher: World Scientific
ISBN: 9812568301
Category : Science
Languages : en
Pages : 300
Book Description
This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.
Publisher: World Scientific
ISBN: 9812568301
Category : Science
Languages : en
Pages : 300
Book Description
This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.
BERRU Predictive Modeling
Author: Dan Gabriel Cacuci
Publisher: Springer
ISBN: 366258395X
Category : Technology & Engineering
Languages : en
Pages : 463
Book Description
This book addresses the experimental calibration of best-estimate numerical simulation models. The results of measurements and computations are never exact. Therefore, knowing only the nominal values of experimentally measured or computed quantities is insufficient for applications, particularly since the respective experimental and computed nominal values seldom coincide. In the author’s view, the objective of predictive modeling is to extract “best estimate” values for model parameters and predicted results, together with “best estimate” uncertainties for these parameters and results. To achieve this goal, predictive modeling combines imprecisely known experimental and computational data, which calls for reasoning on the basis of incomplete, error-rich, and occasionally discrepant information. The customary methods used for data assimilation combine experimental and computational information by minimizing an a priori, user-chosen, “cost functional” (usually a quadratic functional that represents the weighted errors between measured and computed responses). In contrast to these user-influenced methods, the BERRU (Best Estimate Results with Reduced Uncertainties) Predictive Modeling methodology developed by the author relies on the thermodynamics-based maximum entropy principle to eliminate the need for relying on minimizing user-chosen functionals, thus generalizing the “data adjustment” and/or the “4D-VAR” data assimilation procedures used in the geophysical sciences. The BERRU predictive modeling methodology also provides a “model validation metric” which quantifies the consistency (agreement/disagreement) between measurements and computations. This “model validation metric” (or “consistency indicator”) is constructed from parameter covariance matrices, response covariance matrices (measured and computed), and response sensitivities to model parameters. Traditional methods for computing response sensitivities are hampered by the “curse of dimensionality,” which makes them impractical for applications to large-scale systems that involve many imprecisely known parameters. Reducing the computational effort required for precisely calculating the response sensitivities is paramount, and the comprehensive adjoint sensitivity analysis methodology developed by the author shows great promise in this regard, as shown in this book. After discarding inconsistent data (if any) using the consistency indicator, the BERRU predictive modeling methodology provides best-estimate values for predicted parameters and responses along with best-estimate reduced uncertainties (i.e., smaller predicted standard deviations) for the predicted quantities. Applying the BERRU methodology yields optimal, experimentally validated, “best estimate” predictive modeling tools for designing new technologies and facilities, while also improving on existing ones.
Publisher: Springer
ISBN: 366258395X
Category : Technology & Engineering
Languages : en
Pages : 463
Book Description
This book addresses the experimental calibration of best-estimate numerical simulation models. The results of measurements and computations are never exact. Therefore, knowing only the nominal values of experimentally measured or computed quantities is insufficient for applications, particularly since the respective experimental and computed nominal values seldom coincide. In the author’s view, the objective of predictive modeling is to extract “best estimate” values for model parameters and predicted results, together with “best estimate” uncertainties for these parameters and results. To achieve this goal, predictive modeling combines imprecisely known experimental and computational data, which calls for reasoning on the basis of incomplete, error-rich, and occasionally discrepant information. The customary methods used for data assimilation combine experimental and computational information by minimizing an a priori, user-chosen, “cost functional” (usually a quadratic functional that represents the weighted errors between measured and computed responses). In contrast to these user-influenced methods, the BERRU (Best Estimate Results with Reduced Uncertainties) Predictive Modeling methodology developed by the author relies on the thermodynamics-based maximum entropy principle to eliminate the need for relying on minimizing user-chosen functionals, thus generalizing the “data adjustment” and/or the “4D-VAR” data assimilation procedures used in the geophysical sciences. The BERRU predictive modeling methodology also provides a “model validation metric” which quantifies the consistency (agreement/disagreement) between measurements and computations. This “model validation metric” (or “consistency indicator”) is constructed from parameter covariance matrices, response covariance matrices (measured and computed), and response sensitivities to model parameters. Traditional methods for computing response sensitivities are hampered by the “curse of dimensionality,” which makes them impractical for applications to large-scale systems that involve many imprecisely known parameters. Reducing the computational effort required for precisely calculating the response sensitivities is paramount, and the comprehensive adjoint sensitivity analysis methodology developed by the author shows great promise in this regard, as shown in this book. After discarding inconsistent data (if any) using the consistency indicator, the BERRU predictive modeling methodology provides best-estimate values for predicted parameters and responses along with best-estimate reduced uncertainties (i.e., smaller predicted standard deviations) for the predicted quantities. Applying the BERRU methodology yields optimal, experimentally validated, “best estimate” predictive modeling tools for designing new technologies and facilities, while also improving on existing ones.