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Materials and Fuels Testing Techniques in the Advanced Test Reactor – from Simple to Complex
Materials and Fuels Testing Techniques in the Advanced Test Reactor – From Simple to Complex Raymond V. Furstenau 1), Frederick W. Ingram 2), John E. Brasier 2), Mark B. Hendrickson 2) 1) Idaho National Engineering and Environmental Laboratory, U.S. Dept. of Energy, USA 2) Idaho National Engineering and Environmental Laboratory, Bechtel BWXT Idaho, USA ABSTRACT The Advanced Test Reactor (ATR) is the third generation of test reactors built at the Test Reactor Area (TRA), Idaho National Engineering and Environmental Laboratory (INEEL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. ATR has a maximum power of 250MW and can provide maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second. This allows considerable acceleration of accumulated neutron fluence to materials and fuels over what would be seen in a typical power reactor. Since power operation of the ATR began in 1969, numerous testing methods have been developed to take advantage of the capabilities of the ATR. The wide range of experiment facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non- instrumented sealed capsule containing test specimens with no real-time monitoring and control capabilities. The Irradiation Test Vehicle, installed in 1999, is the newest testing apparatus in the ATR that accommodates up to fifteen separate tests, each with its own temperature control and monitoring capabilities as well as neutron spectral tailoring capability. More sophisticated testing facilities include pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. -
Reactor Physics Calculations in the Nordic Countries
ESPOO 2003 VTT SYMPOSIUM 230 The eleventh biennial meeting on reactor physics calculations in the Nordic VTT SYMPOSIUM 230 countries was arranged by VTT Processes in Otaniemi, Espoo and on board Tallink´s m/s Romantika on April 9–10, 2003. General reactor physics, calculational methods, a code system adapted for RBMK reactor analyses, and transmutation of nuclear waste were presented by representatives of universities and programme developers. Computer programmes are the most important tools of reactor physics. At the meeting there were presentations of VTT Processes’ new deterministic 3- dimensional radiation transport code MultiTrans and BWR simulator ARES based upon the AFEN model, and also of new features in internationally wellknown codes like CASMO-4E and POLCA (POLCA-T) together with Reactor physics calculations in the Nordic countries results obtained by these programmes. A code for PWR loading pattern search, called LP-fun, is being developed by Westinghouse and others. On the subject of code validation, measurements on SVEA-96+ fuel bundles in the PROTEUS facility had been analyzed with the PHOENIX4 code, reactor scram experiments in the Loviisa and Mochovce VVER reactors using CASMO-4, MCNP4B and HEXTRAN, results of gamma scanning by the PHOENIX4/POLCA7 combination. Some difficulties in predicting the power distribution in the reactor core with sufficiently good accuracy using any of the available code systems were reported by OKG. Heating of non-fuel regions by gamma radiation and neutrons had been investigated using the HELIOS lattice code. Calculational results for heat deposition from gamma radiation in the moderator tank of the Forsmark-1 reactor were reported by Risø. -
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. -
Vver and Rbmk Cross Section Libraries for Origen-Arp
VVER AND RBMK CROSS SECTION LIBRARIES FOR ORIGEN-ARP Germina Ilas, Brian D. Murphy, and Ian C. Gauld, Oak Ridge National Laboratory, USA Introduction An accurate treatment of neutron transport and depletion in modern fuel assemblies characterized by heterogeneous, complex designs, such as the VVER or RBMK assembly configurations, requires the use of advanced computational tools capable of simulating multi-dimensional geometries. The depletion module TRITON [1], which is part of the SCALE code system [2] that was developed and is maintained at the Oak Ridge National Laboratory (ORNL), allows the depletion simulation of two- or three-dimensional assembly configurations and the generation of burnup-dependent cross section libraries. These libraries can be saved for subsequent use with the ORIGEN-ARP module in SCALE. This later module is a faster alternative to TRITON for fuel depletion, decay, and source term analyses at an accuracy level comparable to that of a direct TRITON simulation. This paper summarizes the methodology used to generate cross section libraries for VVER and RBMK assembly configurations that can be employed in ORIGEN-ARP depletion and decay simulations. It briefly describes the computational tools and provides details of the steps involved. Results of validation studies for some of the libraries, which were performed using isotopic assay measurement data for spent fuel, are provided and discussed. Cross section libraries for ORIGEN-ARP Methodology The TRITON capability to perform depletion simulations for two-dimensional (2-D) configurations was implemented by coupling of the 2-D transport code NEWT with the point depletion and decay code ORIGEN-S. NEWT solves the transport equation on a 2-D arbitrary geometry grid by using an SN approach, with a treatment of the spatial variable that is based on an extended step characteristic method [3]. -
Nuclear Fuel Optimization and Problem of Xa9953256 Increasing Burnup and Cost Efficiency of Light Water Reactors in Russia
NUCLEAR FUEL OPTIMIZATION AND PROBLEM OF XA9953256 INCREASING BURNUP AND COST EFFICIENCY OF LIGHT WATER REACTORS IN RUSSIA M.I. SOLONIN, Yu. K. BIBLASHCVLI, F.G. RESHETNIKOV, F.F. SOKOLOV, A.A. BOCHVAR All-Russia Research Institute of Inorganic Materials, Moscow, Russia Abstract Brief analysis is given of the results of WWER-1000 and WWER-440 fuel assembly (FA) and fuel rod operation to the average burn-up of 44 and 34 MW-day/kg U, respectively. The reliable operation of the fuel is noted which made it possible to outline the paths of further improvements in their fuel cycles. Based on a series of improvements reactors are being switched on a 4-year cycle; a 5-year cycle is contemplated for the WWER- 440. The fuel cycle of the boiling RBMK reactors is subjected to essential alterations. Specifically, the use of erbium oxide as an integral burnable absorber allows a higher enrichment of uranium and bum-up. To extend the burn-up a new zirconium alloy E-635 is assumed to be used as fuel rod claddings and other FA components; the alloy has higher corrosion and irradiation resistance. INTRODUCTION The current technical level of the PWR and BWR fuel production and the perfected system of the reactor management have allowed to provide the successful operation of PWR NPP to the average burn-up of ~45 MW* day/kg U in all countries of developed nuclear power. The differences in the reliability and FA serviceability as well as in the number of leaky fuel rods are rather small and the attention is usually not focused on this issue. -
600 Technology (Applied Sciences)
600 600 Technology (Applied sciences) Class here inventions See also 303.48 for technology as a cause of cultural change; also 306.4 for sociology of technology; also 338.1–338.4 for economic aspects of industries based on specific technologies; also 338.9 for technology transfer, appropriate technology See Manual at 300 vs. 600; also at 363 vs. 302–307, 333.7, 570–590, 600; also at 363.1 vs. 600; also at 583–585 vs. 600 SUMMARY 601–609 Standard subdivisions and technical drawing, hazardous materials technology, patents 610 Medicine and health 620 Engineering and allied operations 630 Agriculture and related technologies 640 Home and family management 650 Management and auxiliary services 660 Chemical engineering and related technologies 670 Manufacturing 680 Manufacture of products for specific uses 690 Construction of buildings 601 Philosophy and theory 602 Miscellany Do not use for patents; class in 608 Class interdisciplinary works on trademarks and service marks in 929.9 Interdisciplinary collections of standards relocated to 389 .9 Commercial miscellany Class commercial miscellany of products and services used in individual and family living in 640.29; class commercial miscellany of manufactured products in 670.29; class interdisciplinary commercial miscellany in 381.029 603 Dictionaries, encyclopedias, concordances 604 Technical drawing, hazardous materials technology; groups of people 657 604 Dewey Decimal Classification 604 .2 Technical drawing Including arrangement and organization of drafting rooms, preservation and storage of drawings; specific drafting procedures and conventions (e.g., production illustration, dimensioning; lettering, titling; shades, shadows, projections); preparation and reading of copies Class here engineering graphics, mechanical drawing For architectural drawing, see 720.28. -
When Sex Offenders Leave Prison
BECOMING SCROOGE AT HALE THEATRE UTES ESCAPE TO WIN 8TH 1 MAN’S 48-YEAR STRAIGHT AGAINST BYU JOURNEY TO STAR COUGARS JUMP OUT TO 20-POINT AS THE MISER IN ‘A LEAD BUT CAN’T HOLD OFF UTAH’S CHRISTMAS CAROL’ 2ND-HALF SURGE ARTS C1 SPORTS D1 SUNDAY, NOVEMBER 25, 2018 SALT LAKE CITY, UTAH DESERETNEWS.COM When sex Unlocking science offenders in Idaho leave prison MOST AREN’TINCARCERATED FOR LIFE;WHAT UTAHIS DOING TO KEEPYOU SAFE BY PAT REAVY · DESERET NEWS UTAH STATE PRISON — The sex offender population at the Utah State Prison continues to grow at a staggering pace. In 1996, there were 248 sex offenders incarcerated by the Utah Department of Corrections. To - day, there are 10 times that num- ber, in the neighborhood of 2,500 at both the Point of the Mountain and the prison in Gunnison, mak- ing it by far the fastest-growing population at the prison. An additional 2,200 sex offend- ers are under the watch of Adult Probation and Parole. A Pew study in 2014 found that 31 percent of all inmates in Utah were serving time for a sex offense — far more than in 2004. KORT DUCE, IDAHO NATIONAL LABORATORY According to a Utah Sentencing Rows of concentrated solar arrays dot the landscape at Tooele Army Depot in the military’s quest to become more Commission report, the percent- self-sustaining from the traditional power grid. The Idaho National Laboratory works with the military in this endeavor. age of inmates in prison for sex offenses grew to nearly 34 percent in 2016 to over 35 percent in WHY UTAHNS SHOULD CARE ABOUT MYSTERIES Idaho National Laboratory WILLNUCLEAR POWERPOWER 2017. -
Idaho National Laboratory and Oak Ridge National Laboratory
United States Idaho National Laboratory and Oak Ridge National Laboratory ICERR Description 1. General Presentation of Idaho National Laboratory and Oak Ridge National Laboratory The International Atomic Energy Agency (IAEA) has established a designation for an International Centre based on Research Reactors (ICERR). The intention of this designation is to provide a vehicle for IAEA member-states to access international research reactor and ancillary nuclear research and development infrastructure. The U.S. Department of Energy (DOE) has made a commitment to world leadership in the development of advanced nuclear energy, science, and technology. To this end, DOE has established programs and initiatives to enhance this leadership role. The Idaho National Laboratory (INL), along with its partner laboratory Oak Ridge National Laboratory (ORNL) is leading these initiatives for DOE. Both INL and ORNL have a decades-long and storied history that supports nuclear research, development, and deployment both nationally and internationally. Both have a history of safe and efficient nuclear operations and have a demonstrated a track record of international collaboration and cooperation. 2. Short descriptions of facilities included in the U.S. ICERR designation INL’s Advanced Test Reactor (ATR): The Advanced Test Reactor supports nuclear science and engineering missions for the U.S. Department of Energy’s Office of Nuclear Energy research and development programs, Naval Reactors, universities, as well as other government and industry- sponsored commercial and international research. It is the only U.S. research reactor capable of providing large-volume, high-flux neutron irradiation in a prototypical (e.g. pressure, temperature and chemistry) environment. ATR makes it possible to study the effects of intense neutron and gamma radiation on reactor fuels and materials in a much shorter time frame, permitting accelerated research efforts. -
Beryllium – a Unique Material in Nuclear Applications
INEEL/CON-04-01869 PREPRINT Beryllium – A Unique Material In Nuclear Applications T. A. Tomberlin November 15, 2004 36th International SAMPE Technical Conference This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Government or the sponsoring agency. BERYLLIUM – A UNIQUE MATERIAL IN NUCLEAR APPLICATIONS T. A. Tomberlin Idaho National Engineering and Environmental Laboratory P.O. Box 1625 2525 North Fremont Ave. Idaho Falls, ID 83415 E-mail: [email protected] ABSTRACT Beryllium, due to its unique combination of structural, chemical, atomic number, and neutron absorption cross section characteristics, has been used successfully as a neutron reflector for three generations of nuclear test reactors at the Idaho National Engineering and Environmental Laboratory (INEEL). The Advanced Test Reactor (ATR), the largest test reactor in the world, has utilized five successive beryllium neutron reflectors and is scheduled for continued operation with a sixth beryllium reflector. -
July/August 2004 Newsletter
Environmental Defense Institute News on Environmental Health and Safety Issues ")··..--~~~~~~~~~-,-~~~~~~--"--~~~ I July/August 2004 Volume 15 Number 3 Idaho Cancer Rates Continue to Rise at Record Levels According to the Cancer Data Registry ofldaho Dr. Thomas Pigford which was commissioned by the US there is a steady increase in Idaho cancer rates from the District Court hearing the Hanford Downwinders suit, beginning of data collection through 2002 (the latest both showed that causation for the high rate of cancer in report issued by the Registry). The 2000 report notes an the Northern Idaho Panhandle and Health District 3 increase of 3 59 cancer cases in recent years. "This was (Lewiston area) can be attributed to Hanford emissions one. of the largest single-year increases in cancer following wind patterns up the Columbia and Snake incidence in the history of the Cancer Data Registry of River drainage canyons. Idaho. Cancer sites with notable increases from 1999 to The Hanford· Downwinder litigation won two 2000 were lung, melanoma (in-situ), oral cavity and significant legal wins; 1.) the US 9th District Court of pharynx cancer counts increased over 1999 levels. The Appeals overruled the 1998 Spokane District Court number ofin-situ melanoma cases is 65% higher than for ruling by Judge McDonald that previously rejected the any previous year. The prostate cancer incidence rate is claims of most of the plaintiffs, and remanded the case the highest it has been since the spike in prostate cancer back to District Court for trial, based on Plaintiffs rates in 1990-1993 due to prostate-specific antigen scientific briefs showing significantly more particulate screening. -
March 4, 1999 Calculated Radionuclide Inventories
WM'99 CONFERENCE, FEBRUARY 28 - MARCH 4, 1999 CALCULATED RADIONUCLIDE INVENTORIES FOR STRUCTURAL CORE COMPONENTS IN THE ADVANCED TEST REACTOR by J. W. Sterbentz, M. L. Carboneau, J. A. Logan Lockheed Martin Idaho Technologies, Inc. P.O. Box 1625 Idaho Falls, Idaho 83415-3885 ABSTRACT Reactor core physics and depletion/activation calculations were performed to evaluate radionuclide inventories in a wide variety of structural core components from the Advanced Test Reactor. All components were located in or near the active core environment and received significant neutron exposure resulting in the production of radionuclides from neutron activation. The calculated radionuclide inventory estimates are strongly dependent on the Beginning-of-Life (BOL) elemental constituent and impurity concentrations in the component materials. Therefore, significant effort has been devoted to the determination of best-estimate concentrations for each of the component materials. Materials include stainless steel-304,-347,-348, aluminum-6061, Inconel-600, Inconel-X750, natural hafnium metal, and beryllium metal. Specific radioactive isotopes of interest include 14C, 59Ni, 63Ni, 60Co, 99Tc, 90Sr, and 94Nb. Radionuclide inventory estimates are presented for a select number of components representing a variety of materials. INTRODUCTION Located at the Idaho National Engineering and Environmental Laboratory (INEEL), the Advanced Test Reactor (ATR) is a 250 MWth light water reactor designed specifically to study the effects of intense radiation on reactor fuels and materials. For more than 30 years, the primary role of the ATR has been to serve experimental investigations for the development of advanced nuclear fuels. A variety of test facilities, versatile control systems, and intense neutron flux levels allow for accelerated irradiation tests for a wide range of test specimens. -
Nuclear Propulsion
16 Nuclear Propulsion Claudio Bruno DIMA, University of Rome (La Sapienza), Roma Italy 1. Introduction Nuclear propulsion (NP) concepts go back to the very end of WW II. Scientists informed about the effects of the US atomic bomb thought of exploiting its energy release for applications like commercial electric power generation, but also rockets and space flight [Shepherd and Cleaver, 1948, 1949; Bussard and DeLauer, 1958]. However, space flight was still considered science fiction, and the military had to deal with more concrete things, like the Cold War. Thus, besides power generation, second stages of ICBM, submarine propulsion, long range and long duration airplanes and missiles became the focus of nuclear energy applications. It was the second-stage and airplane application that drove R&D in nuclear propulsion. With the advent of reliable ICBM (the Atlas missile) and lighter fission and thermonuclear warheads, a nuclear-powered second stage became no longer necessary. Airplane applications were found impractical: the Convair NB-36 required such a heavy lead shield for the crew that testing and operation were much restricted. Nuclear-powered missiles were easier to design, e.g., project PLUTO, but still far more complicated compared to conventional. The Soviets investigated airplanes and rockets powered by nuclear power as well, and discarded them too. The history of NP can be found in [Czysz and Bruno, 2009, Chapter 7; Lawrence, 2008; Lawrence et al, 1995; Gunn and Ehresman, 2003; Dewar, 2004] and will not be reported here. Basic technology is also discussed in the references above, in particular reactor design is in [Lawrence et al, 1995].