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小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
Fuel Geometry Options for a Moderated Low-Enriched Uranium Kilowatt-Class Space Nuclear Reactor T ⁎ Leonardo De Holanda Mencarinia,B,Jeffrey C
Nuclear Engineering and Design 340 (2018) 122–132 Contents lists available at ScienceDirect Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor T ⁎ Leonardo de Holanda Mencarinia,b,Jeffrey C. Kinga, a Nuclear Science and Engineering Program, Colorado School of Mines (CSM), 1500 Illinois St, Hill Hall, 80401 Golden, CO, USA b Subdivisão de Dados Nucleares - Instituto de Estudos Avançados (IEAv), Trevo Coronel Aviador José Alberto Albano do Amarante, n 1, 12228-001 São José dos Campos, SP, Brazil ABSTRACT A LEU-fueled space reactor would avoid the security concerns inherent with Highly Enriched Uranium (HEU) fuel and could be attractive to signatory countries of the Non-Proliferation Treaty (NPT) or commercial interests. The HEU-fueled Kilowatt Reactor Using Stirling Technology (KRUSTY) serves as a basis for a similar reactor fueled with LEU fuel. Based on MCNP6™ neutronics performance estimates, the size of a 5 kWe reactor fueled with 19.75 wt% enriched uranium-10 wt% molybdenum alloy fuel is adjusted to match the excess reactivity of KRUSTY. Then, zirconium hydride moderator is added to the core in four different configurations (a homogeneous fuel/moderator mixture and spherical, disc, and helical fuel geometries) to reduce the mass of uranium required to produce the same excess reactivity, decreasing the size of the reactor. The lowest mass reactor with a given moderator represents a balance between the reflector thickness and core diameter needed to maintain the multiplication factor equal to 1.035, with a H/D ratio of 1.81. -
Project Research on Nuclear Spectroscopy and Condensed Matter Physics Using Short-Lived Nuclei
PR12 Project Research on Nuclear Spectroscopy and Condensed Matter Physics Using Short-Lived Nuclei Y. Ohkubo annealed in vacuum at various temperatures. They observed no clear signal of such complexes in the Research Reactor Institute, Kyoto University TDPAC spectra. However, the TDPAC spectra indicate that Ce and He form complexes having a variety of geometrical structures. Comparison with TDPAC results Objective and Participating Research Subjects reported by another research group on 111Cd arising from The main objectives of this project research are the 111In in He-doped stainless steel shows that the parent investigation of the nuclear structure of unstable atoms (La and Ba) of 140Ce trap He atoms more neutron-rich nuclei and also the local properties of efficiently than In atoms do, indicating stronger bonding materials using short-lived nuclei. of He to the former atoms, while different from the This period is the first year of the project. present case, 111Cd (In)‒He complexes form a unique Unfortunately, no experiments in all six research subjects geometrical structure. A part of the results are described of the project (26P12) were executed owing to the in the following second page. suspension of the reactor operation. Here, we report some S. Komatsuda et al. (PRS-3) investigated thermal results which were obtained in previous periods and have behavior and interacting nature of 100-ppm Al and already been published in journals. ~100-ppt In impurities doped in a semiconductor ZnO The research subjects (PRS) reported here are as by means of the TDPAC technique with the 111In(→ follows: 111Cd) probe. -
Preparing for Nuclear Waste Transportation
Preparing for Nuclear Waste Transportation Technical Issues that Need to Be Addressed in Preparing for a Nationwide Effort to Transport Spent Nuclear Fuel and High-Level Radioactive Waste A Report to the U.S. Congress and the Secretary of Energy September 2019 U.S. Nuclear Waste Technical Review Board This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Preparing for Nuclear Waste Transportation Technical Issues That Need to Be Addressed in Preparing for a Nationwide Effort to Transport Spent Nuclear Fuel and High-Level Radioactive Waste A Report to the U.S. Congress and the Secretary of Energy September 2019 This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Jean M. Bahr, Ph.D., Chair University of Wisconsin, Madison, Wisconsin Steven M. Becker, Ph.D. Old Dominion University, Norfolk, Virginia Susan L. Brantley, Ph.D. Pennsylvania State University, University Park, Pennsylvania Allen G. Croff, Nuclear Engineer, M.B.A. Vanderbilt University, Nashville, Tennessee Efi Foufoula-Georgiou, Ph.D. University of California Irvine, Irvine, California Tissa Illangasekare, Ph.D., P.E. Colorado School of Mines, Golden, Colorado Kenneth Lee Peddicord, Ph.D., P.E. Texas A&M University, College Station, Texas Paul J. Turinsky, Ph.D. North Carolina State University, Raleigh, North Carolina Mary Lou Zoback, Ph.D. Stanford University, Stanford, California Note: Dr. Linda Nozick of Cornell University served as a Board member from July 28, 2011, to May 9, 2019. During that time, Dr. Nozick provided valuable contributions to this report. iii This page intentionally left blank. U.S. Nuclear Waste Technical Review Board Staff Executive Staff Nigel Mote Executive Director Neysa Slater-Chandler Director of Administration Senior Professional Staff* Bret W. -
Compilation and Evaluation of Fission Yield Nuclear Data Iaea, Vienna, 2000 Iaea-Tecdoc-1168 Issn 1011–4289
IAEA-TECDOC-1168 Compilation and evaluation of fission yield nuclear data Final report of a co-ordinated research project 1991–1996 December 2000 The originating Section of this publication in the IAEA was: Nuclear Data Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria COMPILATION AND EVALUATION OF FISSION YIELD NUCLEAR DATA IAEA, VIENNA, 2000 IAEA-TECDOC-1168 ISSN 1011–4289 © IAEA, 2000 Printed by the IAEA in Austria December 2000 FOREWORD Fission product yields are required at several stages of the nuclear fuel cycle and are therefore included in all large international data files for reactor calculations and related applications. Such files are maintained and disseminated by the Nuclear Data Section of the IAEA as a member of an international data centres network. Users of these data are from the fields of reactor design and operation, waste management and nuclear materials safeguards, all of which are essential parts of the IAEA programme. In the 1980s, the number of measured fission yields increased so drastically that the manpower available for evaluating them to meet specific user needs was insufficient. To cope with this task, it was concluded in several meetings on fission product nuclear data, some of them convened by the IAEA, that international co-operation was required, and an IAEA co-ordinated research project (CRP) was recommended. This recommendation was endorsed by the International Nuclear Data Committee, an advisory body for the nuclear data programme of the IAEA. As a consequence, the CRP on the Compilation and Evaluation of Fission Yield Nuclear Data was initiated in 1991, after its scope, objectives and tasks had been defined by a preparatory meeting. -
Global Fissile Material Report 2006 a Table of Contents
IPF M Global Fis sile Material Report Developing the technical basis for policy initiatives to secure and irreversibly reduce stocks of nuclear weapons and fissile materials 2006 Over the past six decades, our understanding of the nuclear danger has expanded from the threat posed by the vast nuclear arsenals created by the super- powers in the Cold War to encompass the prolifera- tion of nuclear weapons to additional states and now also to terrorist groups. To reduce this danger, it is essential to secure and to sharply reduce all stocks of highly enriched uranium and separated plutonium, the key materials in nuclear weapons, and to limit any further production. The mission of the IPFM is to advance the technical basis for cooperative international policy initiatives to achieve these goals. A report published by Global Fissile The International Panel on Fissile Materials (IPFM) www.fissilematerials.org Program on Science and Global Security Princeton University Material Report 2006 221 Nassau Street, 2nd Floor Princeton, NJ 08542, USA First report of the International Panel on Fissile Materials First report of the International Panel on Fissile Materials Developing the Technical Basis for Policy Initiatives to Secure and Irreversibly Reduce Stocks of Nuclear Weapons and Fissile Materials www.fissilematerials.org Global Fissile Material Report 2006 a Table of Contents About the IPFM 1 Summary 2 I. Background 5 1 Fissile Materials and Nuclear Weapons 6 2 Nuclear-Weapon and Fissile-Material Stocks 12 3 Production and Disposition of Fissile -
Nuclear Reactor Realities
Page 1 of 26 Nuclear Reactor Realities NUCLEAR REACTOR REALITIES (An Australian viewpoint) PREFACE Now that steam ships are no longer common, people tend to forget that nuclear power is just a replacement of coal, oil or gas for heating water to form steam to drive turbines, or of water (hydro) to do so directly. As will be shown in this tract, it is by far the safest way of doing so to generate electricity economically in large quantities – as a marine engineer of my acquaintance is fond of saying. Recently Quantum Market Research released its latest Australian Scan (The Advertiser, Saturday April 17, 2012, p 17). It has been tracking social change by interviewing 2000 Australians annually since 1992. In the concerns in the environment category, “[a]t the top of the list is nuclear accidents and waste disposal” (44.4 per cent), while “global warming” was well down the list of priorities at No 15, with only 27.7 per cent of people surveyed rating the issue as “extremely serious.” Part of the cause of such information must be that people are slowly realising that they have been deluded by publicity about unverified computer models which indicate that man’s emissions of CO2 play a major part in global warming. They have not yet realised that the history of the dangers of civilian nuclear power generation shows the reverse of their images. The topic of nuclear waste disposal is also shrouded in reactor physics mysteries, leading to a mis-placed general fear of the unknown. In this article only nuclear reactors are considered. -
Nuclear Engineering
Academic Program Review Self-Study Report February 8-11, 2015 Table of Contents I. Executive Summary of the Self-Study Report ..................................................... 1 A. Message from the Department Head and Graduate Program Adviser ................................ 1 B. Charge to the External Review Team .................................................................................. 2 II. Introduction to Department ..................................................................................3 A. Brief departmental history ................................................................................................... 3 B. Mission and goals ................................................................................................................ 3 C. Administrative structure ...................................................................................................... 4 D. Advisory Council ................................................................................................................. 7 E. Department and program resources ..................................................................................... 8 1. Facilities ........................................................................................................................... 8 2. Institutes and Centers ..................................................................................................... 11 3. Finances ........................................................................................................................ -
Redalyc.Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion-Fission Transm
Brazilian Journal of Physics ISSN: 0103-9733 [email protected] Sociedade Brasileira de Física Brasil Velasquez, Carlos E.; Barros, Graiciany de P.; Pereira, Claubia; Fortini Veloso, Maria A.; Costa, Antonella L. Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion-Fission Transmutation System Brazilian Journal of Physics, vol. 42, núm. 3-4, julio-diciembre, 2012, pp. 237-247 Sociedade Brasileira de Física Sâo Paulo, Brasil Available in: http://www.redalyc.org/articulo.oa?id=46423465009 How to cite Complete issue Scientific Information System More information about this article Network of Scientific Journals from Latin America, the Caribbean, Spain and Portugal Journal's homepage in redalyc.org Non-profit academic project, developed under the open access initiative Braz J Phys (2012) 42:237–247 DOI 10.1007/s13538-012-0081-2 NUCLEAR PHYSICS Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion–Fission Transmutation System Carlos E. Velasquez & Graiciany de P. Barros & Claubia Pereira & Maria A. Fortini Veloso & Antonella L. Costa Received: 28 August 2011 /Published online: 17 May 2012 # Sociedade Brasileira de Física 2012 Abstract A sub-critical advanced reactor based on Tokamak regions more suitable to transmutation were determined. The technology with a D–T fusion neutron source is an innovative results demonstrated that the best zone in which to place a type of nuclear system. Due to the large number of neutrons transmutation blanket is limited by the heat sink and the shield produced by fusion reactions, such a system could be useful in block. -
Fundamentals of Nuclear Reactor Physics
Fundamentals of Nuclear Reactor Physics E. E. Lewis Professor of Mechanical Engineering McCormick School of Engineering and Applied Science Northwestern University AMSTERDAM • BOSTON • HEIDELBERG • LONDON NEW YORK • OXFORD • PARIS • SAN DIEGO SAN FRANCISCO • SINGAPORE • SYDNEY • TOKYO ELSEVIER Academie Press is an imprint of Elsevier Contents Preface xiii 1 Nuclear Reactions 1 1.1 Introduction 1 1.2 Nuclear Reaction Fundamentals 2 Reaction Equations 3 Notation 5 Energetics 5 1.3 The Curve of Binding Energy 7 1.4 Fusion Reactions 8 1.5 Fission Reactions 9 Energy Release and Dissipation 10 Neutron Multiplication 12 Fission Products 13 1.6 Fissile and Fertile Materials 16 1.7 Radioactive Decay 18 Saturation Activity 20 Decay Chains 21 2 Neutron Interactions 29 2.1 Introduction 29 2.2 Neutron Cross Sections 29 Microscopic and Macroscopic Cross Sections 30 Uncollided Flux 32 Nuclide Densities 33 Enriched Uranium 35 Cross Section Calculation Example 36 Reaction Types 36 2.3 Neutron Energy Range 38 2.4 Cross Section Energy Dependence 40 Compound Nucleus Formation 41 Resonance Cross Sections 42 Threshold Cross Sections 46 Fissionable Materials 47 vii viii Contents 2.5 Neutron Scattering 48 Elastic Scattering 49 Slowing Down Decrement 50 Inelastic Scattering 52 3 Neutron Distributions in Energy 57 3.1 Introduction 57 3.2 Nuclear Fuel Properties 58 3.3 Neutron Moderators 61 3.4 Neutron Energy Spectra 63 Fast Neutrons 65 Neutron Slowing Down 66 Thermal Neutrons 70 Fast and Thermal Reactor Spectra 72 3.5 -
The Source Is Published Annually by the Department of Nuclear Engineering at the University of Tennessee
THESOURCE ALUMNI MAGAZINE • FALL 2018 The Right Stuff to Propel us to MARSpage 12 A Department on the Rise • Traveling to Mars • Nuclear Pinch Hitter From the Department Head Table of CONTENTS Department Head Message 1 Best of the Best 2 Department sets new record for PhD graduates in 2018 Before, During, and After the Bomb 6 John Auxier II prepares for the unthinkable Pinch-Hitter & Nuclear Grandpa 8 Lawrence Heilbronn is always on deck for students Moving On Up 10 Faculty and staff move up the Hill to make room for new facilities 2 On a Scientific Mission to Mars 12 Going nuclear to get to Mars PULSR Powers the Road to Mars 14 Senior design project powers a 20-year mission Coble Maintains Winning Faculty Energy 15 Coble recognized with university and ANS awards DEPARTMENTS This is a truly exciting time for us here on Rocky Top. When I say we grew out of our building, I really mean Faculty Notes 16 14 The university recently welcomed its largest freshman it. Last year, we had 368 students, our largest class Staff Notes 17 class and the quality of students is amazing. The Tickle ever. Our 132 PhD students was the largest nuclear Student Notes 18 College of Engineering also welcomed its largest- engineering PhD student class in the history of the ever freshman class, including a record percentage United States. Additionally, we graduated 24 PhDs, First Step Awards 20 of women. As for our department, we have 56 new which was the largest graduating class in US history, and Community Outreach 22 freshmen with 20 percent bringing in enough AP credits yes, they are all getting challenging jobs at government Around the Department 24 to make them sophomores and an average math ACT agencies, universities, and in industry. -
Nuclear Engineering
WHAT CAN I DO WITH A MAJOR IN … NUCLEAR ENGINEERING OCCUPATIONAL SUMMARY: The UNM Department of Chemical and Nuclear Engineering (2013) describes the field of nuclear engineering as “an exciting, rapidly-evolving field which requires engineers with an understanding of physical processes of nuclear energy and an ability to apply concepts in new and creative ways. Nuclear engineers are primarily concerned with the control, monitoring, and use of energy released in nuclear processes.” The department goes on to explain that, “some nuclear engineers work on the design and safety aspects of environmentally-sound, passively safe nuclear fission reactors. Others are looking to future energy solutions through development and implementation of nuclear fusion systems. Others are helping in the exploration and utilization of outer space by developing long term, reliable nuclear energy sources. With the renewed concern in environmental science, nuclear engineers are working on safe disposal concepts for radioactive waste and on methods for reduction of radiation releases from industrial facilities. They also work in developing a wide variety of applications for radioisotopes such as the treatment and diagnosis of diseases, food preservation, manufacturing development, processing and quality control, and biological and mechanical process tracers. For each of these fields there are numerous opportunities for nuclear engineers in basic research, applications, operations, and training.” EMPLOYMENT REQUIRMENTS: The Bureau of Labor Statistics (2012) explains that a bachelor's degree in nuclear engineering is the minimum formal education required to work as a nuclear engineer. BLS further explains that many employers value practical experience, making it important for nuclear engineering students to participate in internships and Co-ops while completing their degree.