Authors

Authors

Authors

Authors

Authors

Click to increase image sizeClick to decrease image size Additional informationNotes on contributorsCharles W. BagnalCharles W. Bagnal Jr. (BS, nuclear engineering, Georgia Institute of Technology, 1980) is a consulting engineer at GRP Consulting, Inc., currently engaged in reactor physics methods development and nuclear engineering support services. He has been involved in nuclear reactor design analysis and software development for six years. His experience includes advanced light water reactor (LWR) and heavy water reactor designs, including extended burnup fuel cycles using gadolinia burnable poison.Gerard P. CavanaughGerard P. Cavanaugh (BS, physics, Massachusetts Institute of Technology, 1969; MS, 1970, and PhD, 1976, nuclear engineering, University of Illinois, Urbana-Champaign) worked from 1973 to 1975 in the Neutronics Physics Division at Oak Ridge National Laboratory. He is currently supervisor of radiation physics and criticality analysis at Combustion Engineering, Inc. (C-E). His primary technical interests are in the areas of radiation transport, stochastic sampling methodologies, and computer applications ranging from mainframes to personal computers.Robert P. HarrisRobert P. Harris (BS, 1974, and MS, 1975, nuclear engineering, and MS, 1984, metallurgy, Rensselaer Polytechnic Institute) has worked in the core design, safety analysis, and licensing of C-E pressurized water reactors since 1973. He is currently involved in the neutronic design of advanced burnable poisons and fuel assemblies. He consults in the areas of core fuel management, safety analysis, and startup physics testing.Regis A. MatzieRegis A. Matzie (BS, physics, U.S. Naval Academy, 1965; MS, 1971, and PhD, 1976, nuclear engineering, Stanford University) is currently the manager of analog plants in the nuclear engineering department at C-E. His current technical interests include advanced LWR designs, methods of improving fuel utilization and fuel cycle costs in current design LWRs, and alternate fuel cycles for advanced converter reactors.Laszlo B. TarkoLaszlo B. Tarko (BS, physics, University of Connecticut, 1980) is currently the lead engineer in the radiation physics group at C-E. His current technical interests include radiation transport, ex-core radiation physics, dose rates, energy deposition, and associated computer techniques.Howard OckenHoward Ocken (D. Eng., metallurgy, Yale University, 1966) is a project manager in the Nuclear Power Division of the Electric Power Research Institute. He has managed projects that addressed materials performance in nuclear core components. His current interests include materials aspects associated with reducing radiation fields, especially replacing cobalt sources and decontamination and preconditioning technology.Per Hedemann JensenPer Hedemann Jensen (BSc, electronic engineering, Technical University, Aarhus, Denmark, 1970) is a senior health physicist at Ris0 National Laboratory, where he is head of the Section for Applied Health Physics. He has been involved in studies of radiological consequences from hypothetical core-melt accidents at nuclear power plants. His current technical interest is experimental work on internal dosimetry problems.Ian J. HastingsIan J. Hastings (PhD, metallurgical science, University of Queensland, 1968) is head of the Fuel Properties and Behaviour Group in the Fuel Materials Branch at the Chalk River Nuclear Laboratories (CRNL) of Atomic Energy of Canada Limited. His current interests are in oxide fuel behavior under irradiation, particularly release of short-lived fission products under normal and accident conditions, and in fusion ceramics.Elio MizzanElio Mizzan (BA Sc, chemical engineering, University of Toronto, 1949) is a supervisor at the Fuel Materials Branch Hot Cell Facility at CRNL. His interests have been in the areas of postirradiation examination of reactor fuels and materials, particularly postdefect handling of spent U02 fuel.Alan M. RossAlan M. Ross (BSc, general, University of London, 1953) is a supervisor at the Recycle Fuel Fabrication Laboratories of the Fuel Materials Branch of CRNL. His interests include the fabrication, nondestructive assay, properties, irradiation behavior, and neutron radiography of current and advanced thermal reactor fuels.John R. KelmJohn R. Kelm is a research technician in the Fuel Materials Branch at CRNL. His research responsibility is the operation of a special project hot cell. His current interest is U02 oxidation and stress corrosion cracking.Real J. ChenierReal J. Chenier is a research technician in the Fuel Materials Branch at CRNL. His current research responsibility is operation of the postirradiation metallographic facilities.D. H. RoseD. H. Rose is a research technologist in the Fuel Properties and Behaviour Group of the Fuel Materials Branch at CRNL. His current responsibility is fabrication and operation of instrumented in-reactor experiments.J. NovakJ. Novak (BASc, engineering science, University of Toronto, 1974) is employed in Central Nuclear Services, Nuclear Generation Division of Ontario Hydro. Since 1976 he has been engaged in the areas of nuclear fuel production and development. His current technical interests include behavior of irradiated fuel in air, U02 powder characteristics, and fuel performance improvement.Claudio RonchiClaudio Ronchi (Dr. rer. nat. phys., State University, Milan, Italy, 1965) is a research officer at the Joint Research Centre (JRC) of the Commission of European Communities. After having worked in the research and development of advanced fuels for fast breeders, he is now engaged in reactor safety studies.Jacques van de LaarJacques van de Laar (Ingenieur Fysische Techniek, H.T.S., Heerlen, The Netherlands, 1974) works in thec mathematical modeling department of JRC-Karlsruhe. He is currently involved in the development and execution of computer programs for reactor fuel performance and safety analysis.Hubert BlankHubert Blank (PhD, metal physics, Technical University of Stuttgart, 1957), head of the Physics Division of the European Institute for Transuranium Elements, Karlsruhe, has directed the “Swelling of Advanced Fuels” project at this institute since 1973.Tetsuo FukasawaTetsuo Fukasawa (BS, 1976; MS, 1978; and Dr. Eng., 1981, nuclear engineering, Tohoku University) is a researcher in the Energy Research Laboratory (ERL), Hitachi, Ltd. He has specialized in the radiochemistry of actinide elements and is currently working in the field of low-level radioactive waste treatment and spent fuel reprocessing.Koichi ChinoKoichi Chino (BS, 1972, and MS, 1974, mechanical engineering, Tokyo Institute of Technology) is a researcher at ERL. His primary areas of interest are transport phenomena and radioactive waste management.Osamu KuriyamaOsamu Kuriyama (BS, 1973, and MS, 1975, Tohoku University) is a researcher at ERL. His current interests include the radioactive waste management and chemistry of nuclear waste.Fumio KawamuraFumio Kawamura (BS, chemical engineering, Gunma University,1970; MS, 1972, and Dr. Eng., 1976, Tohoku University) is a researcher at ERL where he is involved in radioactive waste management and reactor water chemistry.Hideo YusaHideo Yusa (BS, physics, Tohoku University, 1959; Dr. Eng., Osaka University, 1969) is a chief researcher at ERL. He is responsible for the research and development of radioactive waste management systems.Bernard L. CohenBernard L. Cohen (BS, Case Institute of Technology, 1944; MS, University of Pittsburgh, 1948; DSc, Carnegie Institute of Technology, 1950) did basic research on nuclear structure using accelerators at Oak Ridge National Laboratory from 1950 to 1958 and at the University of Pittsburgh until the mid-1970s. He then turned his research efforts to the environmental impacts of energy generation, including studies of radioactive waste, health effects of radiation, risk and risk aversion, radon problems, and reactor safety. He is a professor of physics at the University of Pittsburgh and a former director (1965 to 1978) of its Scaife Nuclear Laboratories.K. TasakaK. Tasaka (PhD, nuclear engineering, University of Tokyo, 1976) first worked in breeder reactor safety and fission product characteristics research for ten years and in light water reactor (LWR) safety research for nine years at the Japan Atomic Energy Research Institute (JAERI). He is the project leader of the Rig of Safety Assessment (ROSA) program, and his current interests include analysis of thermal-hydraulic behavior during a loss-of-coolant accident (LOCA) and an anticipated transient without scram in LWRs.M. SuzukiM. Suzuki (MS, mechanical engineering, Kyoto University, 1971) has worked for the ROSA program since 1974. His current interests include safety evaluation of an LWR.Y. AnodaY. Anoda (PhD, mechanical engineering, University of Tokyo, 1979) is a research engineer for the ROSA program. His current interests include two-phase flow during a LOCA.Y. KoizumiY. Koizumi (PhD, mechanical engineering, University of Tokyo, 1977) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA with emphasis on two-phase flow characteristics and heat transfer.T. YonomotoT. Yonomoto (MS, nuclear engineering, University of Osaka, 1982) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA.H. KumamaruH. Kumamaru (PhD, nuclear engineering, University of Tokyo, 1980) is a research engineer for the ROSA program. His current interests include core heat transfer under LOCA conditions.H. NakamuraH. Nakamura (MS, crystalline material engineering, Nagoya University, 1981) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA.M. ShibaM. Shiba (MS, mechanical engineering, Waseda University, 1959) is the general manager of Reactor Safety Laboratory 1 at JAERI. He has worked for 22 years at JAERI in the field of reactor engineering and safety and is currently responsible for simulated LOCA experiments.Genichi MatsumotoGenichi Matsumoto (BS, physics, Tokyo University, 1946) has been an associate professor of nuclear engineering at Nagoya University from 1963 to the present, where he is responsible for research and education in nuclear reactor engineering. He worked as a member of the Scientific Research Institute of Tokyo following his graduation from Tokyo University, and from 1950 to 1963, he served on the technical staff of the Research Reactor Operation Division of the Japan Atomic Energy Research Institute. His current research field includes nuclear safety, neutron radiography (especially neutron television technology), and heat pipe technology.Soichi DoiSoichi Doi (BS, 1976, and MS, 1978, nuclear engineering, Nagoya University) has been employed by the Mitsubishi Atomic Power Industry Co. since 1978, where he is responsible for the nuclear fuel engineering of light water reactors.Kohei OhkuboKohei Ohkubo (BS, mechanical engineering, Aichi Institute of Technology, 1975) is a staff member of Nagoya University.Yasushi IkedaYasushi Ikeda (BS, physics, 1963, and PhD, nuclear engineering, 1982, Nagoya University) has been an assistant staff member of Nagoya University from 1964 to the present. He has investigated thermodynamics of nuclear materials using mass spectrometric technology; neutron radiography technology is also included in his research interests.Günther HesselGünther Hessel [BS, physics, Technical University Dresden, German Democratic Republic (GDR), 1970] is a research scientist at the Central Institute of Nuclear Research (CIN), Rossendorf. He is involved in experimental investigations and developments for technical diagnosis, especially at nuclear power plants.Hans-Erich KöppenHans-Erich Köppen (BS, computer science, Technical University Dresden, 1973) is a research scientist at the CIN. His area of expertise is microprocessor hard- and software and the construction of autonomously working monitors.Peter LiewersPeter Liewers (BS, physics, University of Halle, GDR, 1957; PhD, physics, University of Leipzig, GDR, 1962) is the scientific leader of the group for reactor diagnostics at the CIN. His interests and activities have shifted from reactor physics to technical diagnostics.Peter SchumannPeter Schumann (BS, nuclear engineering, Technical University Dresden, 1963; PhD, physics, Bergakademie Freiberg, GDR, 1970) is a staff scientist at the CIN where he is concerned with digital signal processing and computer software. Formerly he worked in the field of in-core measuring techniques and neutron spectrometryFrank-Peter WeiβFrank-Peter Weiβ (BS, physics, Technical University Dresden, 1973) is a research scientist in the group for technical diagnostics at the CIN. His current interest is the application of statistical pattern recognition to technical diagnostics.

"Spooner, Prof. Henry John, (14 June 1856–16 Dec. 1940), formerly Director and Professor of Mechanical and Civil Engineering, School of Engineering, The Polytechnic, Regent Street, W., 1882–1922, and President Polytechnic Engineering Society; Consulting Efficiency and Mechanical Engineer since 1884" published on by Oxford University Press.

In Memoriam: Dr. Clive L. Dym (1942–2016)

Potential evapotranspiration is one of basic parameter in hydrologic cycle that should be estimate in irrigation design and scheduling, watershed hydrology studies. Many applications in diverse disciplines require estimates of evapotranspiration (ET) at hourly or smaller time steps. The primary objectives of this study were to compare the American Society of Civil Engineers (ASCE) and FAO-56 Penman–Monteith equations for hourly ET0 (ET0,hourly,ASCE and ET0, hourly,FAO) estimations for semiarid climate conditions and to compare the 24 h sum of ASCE (ET0,24 h,ASCE) and FAO-56 hourly ET0 (ET0,24 h,FAO) with the daily ET0 (ET0,d,FAO) computed from the daily FAO-56 equation, which is identical to ASCE daily ET0 equation. 278-days, i.e., 2008–2009 continuous hourly and daily weather data from the automated internet weather station where placed in private Farm in fariman khorasan razavi province were used. It was evident that during the day, ET0,hourly,ASCE was higher than ET0, hourly ,FAO due to a lower surface resistance parameter value, while at night ET0, hourly,ASCE was lower than ET0, hourly,FAO due to a higher surface resistance parameter value. The ET0, hourly,FAO was about 18% less than ET0, hourly,ASCE and ET0,24 h,FAO was about 14% lower than ET0,24 h,ASCE. The difference between ET0, hourly,ASCE and ET0, hourly,FAO during the day and night was highly dependent on wind speed. For the entire year, ET0,24 h,FAO was 2.6% higher than ET0,d,FAO while ET0,24 h,ASCE was 17% higher than ET0,d,FAO. These results demonstrated that for applications that require hourly time steps or daily ET0 for the entire year, the use of ET0, hourly ,FAO and ET0,24 h,FAO, respectively, will yield more consistent outcomes. Keywords: Reference evapotranspiration, Surface resistance, ASCE penman-monteith, FAO-56Penman-Monteith, Summation of hourly, Fariman

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1994 (October 1993 through September 1994). This annual report is the eleventh for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has a research program in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. The ACL has four technical groups -- Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis -- which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL. The Chemical Analysis Group uses wet- chemical and instrumental methods for elemental, compositional, and isotopic determinations in solid, liquid, and gaseous samples and provides specialized analytical services. Major instruments in this group include an ion chromatograph (IC), an inductively coupled plasma/atomic emission spectrometer (ICP/AES), spectrophotometers, mass spectrometers (including gas-analysis and thermal-ionization mass spectrometers), emission spectrographs, autotitrators, sulfur and carbon determinators, and a kinetic phosphorescence uranium analyzer.

Differences in Atmospheric Persistent Organic Pollutant Concentrations at Two Locations in Chicago

This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design application. Capabilities required to establish and operate this center are found primarily in Argonne's Nuclear Engineering and Mathematics and Computer Science Divisions. Funding for the center would be sought from DOE-NE (GNEP/Advanced Burner Reactor and Generation IV programs), DOE-SC/ASCR, and the commercial nuclear industry. Having the above experimental and modeling capabilities at Argonne would constitute a national/international center of excellence for conducting the research and engineering and design tool development needed to support the DOE GNEP/ LM-ABR initiative in developing safe, high-performance reactors.

This chapter explains how a general contractor can obtain the benefits and what changes to construction processes are desirable. It begins with a discussion of the various types of contractors and how Building Information Modeling (BIM) can provide benefits for their specific needs. The chapter focuses on important application areas that apply to most contractors. These include: BIM support for process change, including lean construction; constructability analysis and clash detection; quantity takeoff and cost estimating; construction analysis and planning; integration with cost, schedule, quality, and safety control; off-site fabrication; BIM in the field; and improved handover of the completed building to the owner. The chapter discusses the contractual and organizational changes that are needed to fully exploit the benefits that BIM offers, and concludes with some thoughts on how BIM can be implemented in a construction company.

Photon shutter 1 (PS1) is one of the most critical elements on the front end of the beamlines at the Advanced Photon Source (APS) now under construction at Argonne National Laboratory (ANL). The PS1 uses an enhanced heat transfer tube developed at ANL. Due to large thermal loads on these components, inclined geometry is used in the design to spread the footprint of the x-ray beam. Even then, thermal loads are very critical. To address the thermal and thermo-mechanical issues, analytical studies have been applied to a simplified model of the shutter tube. The maximum temperature and maximum effective stress have been parametrically studied. Results for maximum temperatures and stresses are obtained and compared with the available strength/fatigue data for the materials proposed for the shutter design.

The efficiency and durability of proton exchange membrane fuel cells has come to the forefront of research and development efforts as sustainable transportation applications shift from passenger to heavy duty vehicles. Complementary research expertise and advanced instrumentation are required to accelerate materials discovery and degradation mitigation of fuel cell components, with significant attention on catalysts, ionomers and membranes. The scanning transmission electron microscope (STEM) is among the key characterization techniques for accelerating materials and device development, providing key insights into atomic scale structure. Automating STEM data acquisition and analysis enables large data sets with improved statistical relevance and throughput will expand the impact of this method in the rapid materials and accelerated stress test development.We will show how the latest instrument developments in automation and high speed detectors enable new insights into catalyst structure and electrode layer degradation. This includes correlative, multimodal STEM techniques, such as aberration-corrected imaging, secondary electron detection, energy dispersive X-ray spectroscopy, cryogenic microscopy and 4D-STEM, to build a more comprehensive view of the effect of particle size and composition on surface strain and durability. These results will be correlated with information obtained from X-ray scattering techniques and fuel cell performance testing to understand the type and degree of degradation occurring during accelerated stress tests under development for heavy duty applications. The prospect of automated electron tomography coupled with identical location (IL)-STEM to provide detailed three-dimensional information on catalyst-support interactions will also be discussed.This material is based on work performed by the Million Mile Fuel Cell Truck (M2FCT) Consortium, technology managers Greg Kleen and Dimitrios Papageorgopoulus, which is supported by the U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy, Hydrogen and Fuel Cell Technologies Office. Electron microscopy research was supported by the Center for Nanophase Materials Sciences (CNMS), which is a US Department of Energy, Office of Science User Facility at Oak Ridge National Laboratory. The X-ray scattering experiments were performed at beamline 9-ID-C at the Advanced Photon Source (APS) at Argonne National Laboratory (ANL). Use of the APS, an Office of Science user facility operated by ANL, is supported by the U.S. Department of Energy, Office of Science, Office of Basic Energy Sciences, under Contract No. DE-AS02-06CH11357

An experimental and computational effort was undertaken in order to evaluate the capability of the fluid-structure interaction (FSI) simulation tools to describe the deflection of a Missouri University Research Reactor (MURR) fuel element plate redesigned for conversion to lowenriched uranium (LEU) fuel due to hydrodynamic forces. Experiments involving both flat plates and curved plates were conducted in a water flow test loop located at the University of Missouri (MU), at conditions and geometries that can be related to the MURR LEU fuel element. A wider channel gap on one side of the test plate, and a narrower on the other represent the differences that could be encountered in a MURR element due to allowed fabrication variability. The difference in the channel gaps leads to a pressure differential across the plate, leading to plate deflection. The induced plate deflection the pressure difference induces in the plate was measured at specified locations using a laser measurement technique. High fidelity 3-D simulations of the experiments were performed at MU using the computational fluid dynamics code STAR-CCM+ coupled with the structural mechanics code ABAQUS. Independent simulations of the experiments were performed at Argonne National Laboratory (ANL) using the STAR-CCM+ code and its built-in structural mechanics solver. The simulation results obtained at MU and ANL were compared with the corresponding measured plate deflections.