Annex 21 - Glossary
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Study of Advanced Lwr Cores for Effective Use of Plutonium and Mox Physics Experiments
STUDY OF ADVANCED LWR CORES FOR EFFECTIVE USE OF PLUTONIUM AND MOX PHYSICS EXPERIMENTS T. YAMAMOTO, H. MATSU-URA*, M. UEJI, H. OTA XA9953266 Nuclear Power Engineering Corporation, Toranomon, Minato-ku, Tokyo T. KANAGAWA Mitsubishi Heavy Industries, Ltd, Nishi-ku, Yokohama K. SAKURADA Toshiba Corporation, Isogo-ku, Yokohama H.MARUYAMA Hitachi, Ltd, Hitachi-shi Japan Abstract Advanced technologies of full MOX cores have been studied to obtain higher Pu consumption based on the advanced light water reactors (APWRs and ABWRs). For this aim, basic core designs of high moderation lattice (H/HM ~5) have been studied with reduced fuel diameters in fuel assemblies for APWRs and those of high moderation lattice (H/HM ~6) with addition of extra water rods in fuel assemblies for ABWRs. The analysis of equilibrium cores shows that nuclear and thermal hydraulic parameters satisfy the design criteria and the Pu consumption rate increases about 20 %. An experimental program has been carried out to obtain the core parameters of high moderation MOX cores in the EOLE critical facility at the Cadarache Centre as a joint study of NUPEC, CEA and CEA's industrial partners. The experiments include a uranium homogeneous core, two MOX homogeneous cores of different moderation and a PWR assembly mock up core of MOX fuel with high moderation. The program was started from 1996 and will be completed in 2000. 1. INTRODUCTION In Japan, the MOX fuel demonstration programs have been performed successfully and reload size use of MOX fuel has been prepared. The recycling of plutonium in light water reactors is expected to continue in several decades. -
The Electronuclear Conversion of Fertile to Fissile Material
UCRL-52144 THE ELECTRONUCLEAR CONVERSION OF FERTILE TO FISSILE MATERIAL C. M. Van Atta J. D. Lee H. Heckrotto October 11, 1976 Prepared for U.S. Energy Research & Development Administration under contract No. W-7405-Eng-48 II\M LAWRENCE lUg LIVERMORE k^tf LABORATORY UnrmsilyotCatftxna/lJvofmofe s$ PC DISTRIBUTION OF THIS DOCUMENmmT IS UMUMWTED NOTICE Thii npoit WM prepared w u account of wot* •pomond by UM Uiilttd Stalwi GovcmiMM. Nittim Uw United Stain nor the United Statn Energy tUwardi it Development AdrnWrtrtUon, not «y of thei* employee!, nor any of their contricton, •ubcontrecton, or their employe*!, makti any warranty, expreai « Implied, or muMi any toga) liability oc reeponafctUty for the accuracy, completenni or uMfulntat of uy Information, apperatui, product or proem dlecloead, or repreienl. that tu UM would not *nfrkig» prrrtt*)}MWiwd r%hl». NOTICE Reference to a oompmy or product rum don not imply approval or nconm ndatjon of the product by the Untnrtity of California or the US. Energy Research A Devetopnient Administration to the uchvton of others that may be suitable. Printed In the United Stitei or America Available from National Technical Information Service U.S. Department of Commerce 528S Port Royal Road Springfield, VA 22161 Price: Printed Copy S : Microfiche $2.25 DMimtic P»t» Ranflt PHca *•#» Rtnft MM 001-025 $ 3.50 326-350 10.00 026-050 4.00 351-375 10.50 051-075 4.50 376-400 10.75 076-100 5.00 401-425 11.00 101-125 5.50 426-450 31.75 126-150 6.00 451-475 12.00 151-175 6.75 476-500 12.50 176-200 7.50 501-525 12.75 201-225 7.75 526-550 13.00 526-250 8.00 551-575 13.50 251-275 9.00 576-600 I3.7S 276-300 9.25 601 -up 301-325 9.75 *Ml J2.50 fot «ch iddltlOMl 100 pip tacmitMt from 601 ID 1,000 flfcK IM 54.50 for eicli iMUknal I0O plfe feenmMI om 1,000 p*o. -
Advanced Reactors with Innovative Fuels
Nuclear Science Advanced Reactors with Innovative Fuels Workshop Proceedings Villigen, Switzerland 21-23 October 1998 NUCLEAR•ENERGY•AGENCY OECD, 1999. Software: 1987-1996, Acrobat is a trademark of ADOBE. All rights reserved. OECD grants you the right to use one copy of this Program for your personal use only. Unauthorised reproduction, lending, hiring, transmission or distribution of any data or software is prohibited. You must treat the Program and associated materials and any elements thereof like any other copyrighted material. All requests should be made to: Head of Publications Service, OECD Publications Service, 2, rue AndrÂe-Pascal, 75775 Paris Cedex 16, France. OECD PROCEEDINGS Proceedings of the Workshop on Advanced Reactors with Innovative Fuels hosted by Villigen, Switzerland 21-23 October 1998 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. -
Detailed B Depletion in Control Rods Operating in a Nuclear Boiling
UPTEC K11 015 Examensarbete 30 hp Februari 2011 Detailed 10B depletion in control rods operating in a Nuclear Boiling Water Reactor John Johnsson Abstract Detailed 10B depletion in control rods operating in a Nuclear Boiling Water Reactor John Johnsson Teknisk- naturvetenskaplig fakultet UTH-enheten In a nuclear power plant, control rods play a central role to control the reactivity of the core. In an inspection campaign of three control rods (CR 99) operated in the Besöksadress: KKL reactor in Leibstadt, Switzerland, during 6 respectively 7 consecutive cycles, Ångströmlaboratoriet Lägerhyddsvägen 1 defects were detected in the top part of the control rods due to swelling caused by 10 Hus 4, Plan 0 depletion of the neutron-absorbing B isotope (Boron-10). In order to correlate these defects to control rod depletion, the 10B depletion has in this study been Postadress: calculated in detail for the absorber pins in the top node of the control rods. Box 536 751 21 Uppsala Today the core simulator PLOCA7 is used for predicting the behavior of the reactor Telefon: core, where the retrievable information from the standard control rod follow-up is 018 – 471 30 03 the average 10B depletion for clusters of 19 absorber holes i.e. one axial node. 10 Telefax: However, the local B depletion in an absorber pin may be significantly different 018 – 471 30 00 from the node average depletion that is re-ceived from POLCA7. To learn more, the 10B depletion has been simulated for each absorber hole in the uppermost node using Hemsida: the stochastic Monte Carlo 3D simulation code MCNP as well as an MCNP- based http://www.teknat.uu.se/student 2D-depletion code (McScram). -
Abundant Thorium As an Alternative Nuclear Fuel Important Waste Disposal and Weapon Proliferation Advantages
Energy Policy 60 (2013) 4–12 Contents lists available at SciVerse ScienceDirect Energy Policy journal homepage: www.elsevier.com/locate/enpol Abundant thorium as an alternative nuclear fuel Important waste disposal and weapon proliferation advantages Marvin Baker Schaffer n RAND Corporation, 1776 Main Street, Santa Monica, CA 90407, United States HIGHLIGHTS Thorium is an abundant nuclear fuel that is well suited to three advanced reactor configurations. Important thorium reactor configurations include molten salt, CANDU, and TRISO systems. Thorium has important nuclear waste disposal advantages relative to pressurized water reactors. Thorium as a nuclear fuel has important advantages relative to weapon non-proliferation. article info abstract Article history: It has long been known that thorium-232 is a fertile radioactive material that can produce energy in Received 10 May 2012 nuclear reactors for conversion to electricity. Thorium-232 is well suited to a variety of reactor types Accepted 26 April 2013 including molten fluoride salt designs, heavy water CANDU configurations, and helium-cooled TRISO- Available online 30 May 2013 fueled systems. Keywords:: Among contentious commercial nuclear power issues are the questions of what to do with long-lived Thorium radioactive waste and how to minimize weapon proliferation dangers. The substitution of thorium for Non-proliferation uranium as fuel in nuclear reactors has significant potential for minimizing both problems. Nuclear waste reduction Thorium is three times more abundant in nature than uranium. Whereas uranium has to be imported, there is enough thorium in the United States alone to provide adequate grid power for many centuries. A well-designed thorium reactor could produce electricity less expensively than a next-generation coal- fired plant or a current-generation uranium-fueled nuclear reactor. -
Candu Fuel-Cycle Vision Xa9953247
CANDU FUEL-CYCLE VISION XA9953247 P.G. BOCZAR Fuel and Fuel Cycle Division, Chalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, Ontario, Canada Abstract The fuel-cycle path chosen by a particular country will depend on a range of local and global factors. The CANDU® reactor provides the fuel-cycle flexibility to enable any country to optimize its fuel-cycle strategy to suit its own needs. AECL has developed the CANFLEX® fuel bundle as the near-term carrier of advanced fuel cycles. A demonstration irradiation of 24 CANFLEX bundles in the Point Lepreau power station, and a full-scale critical heat flux (CHF) test in water are planned in 1998, before commercial implementation of CANFLEX fuelling. CANFLEX fuel provides a reduction in peak linear element ratings, and a significant enhancement in thermalhydraulic performance. Whereas natural uranium fuel provides many advantages, the use of slightly enriched uranium (SEU) in CANDU reactors offers even lower fuel-cycle costs and other benefits, such as uprating capability through flattening the channel power distribution across the core. Recycled uranium (RU) from reprocessing spent PWR fuel is a subset of SEU that has significant economic promise. AECL views the use of SEU/RU in the CANFLEX bundle as the first logical step from natural uranium. High neutron economy enables the use of low-fissile fuel in CANDU reactors, which opens up a spectrum of unique fuel-cycle opportunities that exploit the synergism between CANDU reactors and LWRs. At one end of this spectrum is the use of materials from conventional reprocessing: CANDU reactors can utilize the RU directly without re-enrichment, the plutonium as conventional mixed-oxide (MOX) fuel, and the actinide waste mixed with plutonium in an inert-matrix carrier. -
The Impact of Partitioning and Transmutation on the Risk Assesment of a Spent Nuclear Fuel
h/e/-se SE0608415 The Impact of Partitioning and Transmutation on the Risk Assesment of a Spent Nuclear Fuel Naima Amrani and Ahmed Boucenna UFAS University Physics Department Faculty of sciences Setif 19000 ALGERIA I. INTRODUCTION Nuclear power produces steadily a mass of spent fuel which contains a part from the short lived fission products, a significant amount of actinides and fission products with height toxicity and long half-lives. These nuclides constitute the long-term radiotoxic inventory which remains as a hazard far beyond human perception. The reprocessing recycles most of the major actinides (Uranium and Plutonium), while the Minor Actinides (MA) (mainly Neptunium: Np, Americium: Am and Curium: Cm) with half lives up to 2 million years remain with the fission products which are vitrified before being buried in deep repositories. Partitioning of the minor actinides and some of the fission products is an efficient method to reduce the long term radiotoxicity of the residual waste components with a factor proportional to the separation yield. The improved minor actinide nuclides would be recycled into a fuel cycle activities and returned to the reactor inventory of fissile and fertile material for transmutation to short lived isotopes. Progressively the MAs and some long-lived fission product (LLFP) could be burn up out. This option would reduce the long term contamination hazard in the high-level waste and shorten the time interval necessary to keep the actinides containing wastes confined in a deep geologic repository. Partitioning and Transmutation (P&T) is, in principal, capable of reducing the radiotoxicity period, while a number of practical difficult remain to be surmounted. -
Boiling Water Reactor Control Rod CR 82M-1
Nuclear Fuel Boiling Water Reactor Control Rod CR 82M-1 Background CR 82M-1 Design The boiling water reactor (BWR) control rod of The hafnium tip of the CR 82M-1 design protects today must meet high operational demands and at the control rod from absorber material swelling the same time contribute to decreased operational when operated in the shutdown mode; i.e., costs for the plant operator. withdrawn from the core. The flexible B4C inventory allows for either matched or high- Description reactivity worth control rods. As structural material, American Iron and Steel Institute 316L stainless The Westinghouse BWR control rod design steel is an irradiation-resistant steel, not readily consists of four stainless steel sheets welded sensitized to irradiation-assisted stress corrosion together to form a cruciform-shaped rod. Each cracking. With an extremely low-cobalt content sheet has horizontally drilled holes to contain the (< 0.02%) in the wing material, these control rods absorber materials (B4C powder and hafnium). can play a significant role in as-low-as-reasonably- This design allows significantly more B4C to be achievable efforts. The design, with horizontally contained in the rod compared to the original drilled absorber holes, limits the washout of control rods of most reactors. B4C in the event of an anomaly in a wing, thus maintaining full reactivity worth. Westinghouse CR 82M-1 control rod for all types of BWRs Westinghouse BWR control rod CR 82M-1 Benefits CR 82M-1 is an evolutionary design based on 45 years of control rod operation -
Accident-Tolerant Control Rod
NEA/NSC/DOC(2013)9 Accident-tolerant control rod Hirokazu Ohta, Takashi Sawabe, Takanari Ogata Central Research Institute of Electric Power Industry (CRIEPI), Japan Boron carbide (B4C) and hafnium (Hf) metal are used for the neutron absorber materials of control rods in BWRs, and silver-indium-cadmium (Ag-In-Cd) alloy is used in PWRs. These materials are clad with stainless steel. The eutectic point of B4C and iron (Fe) is about 1 150°C and the melting point of Ag-In-Cd alloy is about 800°C, which are lower than the temperature of zircaloy – steam reaction increases rapidly (~1 200°C). Accordingly, it is possible that the control rods melt and collapse before the reactor core is significantly damaged in the case of severe accidents. Since the neutron absorber would be separated from the fuels, there is a risk of re-criticality, when pure water or seawater is injected for emergency cooling. In order to ensure sub-criticality and extend options of emergency cooling in the course of severe accidents, a concept of accident-tolerant control rod (ACT) has been derived. ACT utilises a new absorber material having the following properties: • higher neutron absorption than current control rod; • higher melting or eutectic temperature than 1 200°C where rapid zircaloy oxidation occurs; • high miscibility with molten fuel materials. The candidate of a new absorber material for ATC includes gadolinia (Gd2O3), samaria (Sm2O3), europia (Eu2O3), dysprosia (Dy2O3), hafnia (HfO2). The melting point of these materials and the liquefaction temperature with Fe are higher than the rapid zircaloy oxidation temperature. -
Lwv/L' I .D N. V/./ \Qev
Sept. 16, 1958 _ . I w, E, ABBOTT ETAL 2,852,460 FUEL-BREEDER FUEL ELEMENT FOR NUCLEAR REACTOR Filed Aug. 6, 1956 w//%////»;:/N \QE n.V////.//////////.Dv Lwv/l'I - ././4//. mm . 1M5.NLA TOT T T0 BY mm»/ /m m _ ATTORNEY , 2,852,460 United States Patent 0 . i Patented Sept. 16, 1958 1 23 power level, and in heterogeneous reactors this has been 2,852,460 ' set by the uranium temperature in the center of the rod._ To avoid this, and yet maintain a high ?ux, fuel elements FUEL-BREEDER FUEL ELEMENT FOR comprising a cluster of relatively small diameter uranium NUCLEAR REACTOR rods have been designed. However, this only aggravates William E. Abbott, East Pittsburgh, Pa., and Ralph fabricational and decontamination costs. Balent, Tarzana, Calif., assignors, by mesne assign An object of our invention, therefore, is to provide an ments, to the United States of America as represented improved fuel-breeder fuel element. .by the United States Atomic Energy Commission Another object is to provide a fuel-breeder fuel ele ment, wherein the fertile and ?ssionable materials are Application August 6, 1956, Serial No. 602,401 separated ‘and there is a minimum of cladding. 5 Claims. (Cl. 204-1931) Another object is to provide such a fuel element which permits fabrication and decontamination economies. Another object is to provide such a fuel element, where Our invention relates to an improved nuclear reactor 15 in a single, relatively large diameter fuel element is the fuel element, and more particularly to an improved fuel equivalent of a cluster of smaller diameter rods. -
Nuclear Fuel Cycles Technology Assessment
Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Carbon Dioxide Capture and Storage Clean Power Value-Added Options Carbon Dioxide Capture for Natural Gas and Industrial Applications Carbon Dioxide Capture Technologies Carbon Dioxide Storage Technologies Crosscutting Technologies in Carbon Dioxide Capture and Storage Fast-spectrum Reactors Geothermal Power High Temperature Reactors Hybrid Nuclear-Renewable Energy Systems Hydropower Light Water Reactors Marine and Hydrokinetic Power Nuclear Fuel Cycles Solar Power Stationary Fuel Cells Supercritical Carbon Dioxide Brayton Cycle U.S. DEPARTMENT OF Wind Power ENERGY Clean Power Quadrennial Technology Review 2015 Nuclear Fuel Cycles Chapter 4: Technology Assessments Introduction and Background The Nuclear Fuel Cycle (NFC) is defined as the total set of operations required to produce fission energy and manage the associated nuclear materials. It can have different attributes, including the extension of natural resources, or the minimization of waste disposal requirements. The NFC, as depicted in Figure 4.O.1, is comprised of a set of operations that include the extraction of uranium (U) resources from the earth (and possibly from seawater), uranium enrichment and fuel fabrication, use of the fuel in reactors, interim storage of used nuclear fuel, the optional recycle of the used fuel, and the final disposition of used fuel and waste forms from the recycling processes. Thorium (Th) fuel cycles have been proposed also, but have not been commercially implemented). Figure 4.O.1 Schematic of the uranium based Nuclear Fuel Cycle 1 Quadrennial Technology Review 2015 Clean Power TA 4.O: Nuclear Fuel Cycles The nuclear fuel cycle is often grouped into three classical components (front-end, reactor, and back-end): Front End: The focus of the front end of the nuclear fuel cycle is to deliver fabricated fuel to the reactor. -
Cumberland County, North Carolina Emergency Operations Plan
Cumberland County, North Carolina Emergency Operations Plan July 14, 2017 Prepared By Excelliant Services, Inc. 1201 Lee Branch Lane Birmingham, Al 35242 STATEMENT OF APPROVAL The undersigned approves the Cumberland County Emergency Operations Plan and agrees to the responsibilities assigned to their organization. _______________________________________ _________________ Chairman, County Board of Commissioners Date _______________________________________ _________________ County Manager, Cumberland County Date _______________________________________ _________________ Sheriff, Cumberland County Date _______________________________________ _________________ Assistant County Manager, Cumberland County Date _______________________________________ _________________ Director, Emergency Services, Cumberland County Date _______________________________________ _________________ Director, Emergency Medical Service Date of Cape Fear Valley Health Systems _______________________________________ _________________ Director, Finance Department, Cumberland County Date _______________________________________ _________________ Director, Health Department, Cumberland County Date _______________________________________ _________________ Director, Information Services, Cumberland County Date ______________________________________ _________________ Director, Parks and Recreation Department Date _______________________________________ _________________ Director, Personnel, Cumberland County Date _______________________________________ _________________ Director,