Nuclear Power in the Soviet Union by B.A
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Table 2.Iii.1. Fissionable Isotopes1
FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector. -
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. -
Nuclear Power Reactors in California
Nuclear Power Reactors in California As of mid-2012, California had one operating nuclear power plant, the Diablo Canyon Nuclear Power Plant near San Luis Obispo. Pacific Gas and Electric Company (PG&E) owns the Diablo Canyon Nuclear Power Plant, which consists of two units. Unit 1 is a 1,073 megawatt (MW) Pressurized Water Reactor (PWR) which began commercial operation in May 1985, while Unit 2 is a 1,087 MW PWR, which began commercial operation in March 1986. Diablo Canyon's operation license expires in 2024 and 2025 respectively. California currently hosts three commercial nuclear power facilities in various stages of decommissioning.1 Under all NRC operating licenses, once a nuclear plant ceases reactor operations, it must be decommissioned. Decommissioning is defined by federal regulation (10 CFR 50.2) as the safe removal of a facility from service along with the reduction of residual radioactivity to a level that permits termination of the NRC operating license. In preparation for a plant’s eventual decommissioning, all nuclear plant owners must maintain trust funds while the plants are in operation to ensure sufficient amounts will be available to decommission their facilities and manage the spent nuclear fuel.2 Spent fuel can either be reprocessed to recover usable uranium and plutonium, or it can be managed as a waste for long-term ultimate disposal. Since fuel re-processing is not commercially available in the United States, spent fuel is typically being held in temporary storage at reactor sites until a permanent long-term waste disposal option becomes available.3 In 1976, the state of California placed a moratorium on the construction and licensing of new nuclear fission reactors until the federal government implements a solution to radioactive waste disposal. -
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. -
Policy Basics - Nuclear Energy (PDF)
NRDC: Policy Basics - Nuclear Energy (PDF) FEBRUARY 2013 NRDC POLICY BASICS FS:13-01-O NUCLEAR ENERGY The U.S. generates about 19 percent of its electricity from nuclear power. Following a 30-year period in which few new reactors were completed, it is expected that four new units—subsidized by federal loan guarantees, an eight-year production tax credit, and early cost recovery from ratepayers—may come on line in Georgia and South Carolina by 2020. In total, 16 license applications have been made since mid-2007 to build 24 new nuclear reactors. The “nuclear renaissance” forecast in the middle of the last decade has not materialized due to the high capital cost of new plants; the severe 2008-2009 recession followed by sluggish electricity demand growth; low natural gas prices and the prospect of abundant future supplies; the failure to pass climate legislation that would have penalized fossil sources in the energy marketplace; and the increasing availability of cheaper, cleaner renewable energy alternatives. I. SELECTED STATUTES n PRICE-ANDERSON ACT First passed in 1957, the Price-Anderson Nuclear Industries n AtOMIC ENERGY ACT (AEA) Indemnity Act provides for additional taxpayer-funded liability Originally enacted in 1954, and periodically amended, the AEA coverage for the nuclear industry above that available in the is the fundamental law governing both civilian and military commercial marketplace to each individual reactor operator uses of nuclear materials. On the civilian side, the Act requires (this sum is $375 million in 2011). Under the Act, operators that civilian uses of nuclear materials and facilities be licensed, of nuclear reactors jointly commit in the event of a severe and it empowers the Nuclear Regulatory Commission (NRC) accident to contribute to a pool of self-insurance funds to establish and enforce standards to govern these uses in (currently set at $12.6 billion) to provide compensation to the order to protect health and safety and minimize danger to life public. -
Policy Brief Organisation for Economic Co-Operation and Development
OCTOBER 2008Policy Brief ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Nuclear Energy Today Can nuclear Introduction energy help make Nuclear energy has been used to produce electricity for more than half a development century. It currently provides about 15% of the world’s supply and 22% in OECD sustainable? countries. The oil crisis of the early 1970s provoked a surge in nuclear power plant orders How safe is and construction, but as oil prices stabilised and even dropped, and enough nuclear energy? electricity generating plants came into service to meet demand, orders tailed off. Accidents at Three Mile Island in the United States (1979) and at Chernobyl How best to deal in Ukraine (1986) also raised serious questions in the public mind about nuclear with radioactive safety. waste? Now nuclear energy is back in the spotlight as many countries reassess their energy policies in the light of concerns about future reliance on fossil fuels What is the future and ageing energy generation facilities. Oil, coal and gas currently provide of nuclear energy? around two-thirds of the world’s energy and electricity, but also produce the greenhouse gases largely responsible for global warming. At the same For further time, world energy demand is expected to rise sharply in the next 50 years, information presenting all societies worldwide with a real challenge: how to provide the energy needed to fuel economic growth and improve social development while For further reading simultaneously addressing environmental protection issues. Recent oil price hikes, blackouts in North America and Europe and severe weather events have Where to contact us? also focused attention on issues such as long-term price stability, the security of energy supply and sustainable development. -
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. -
Uranium (Nuclear)
Uranium (Nuclear) Uranium at a Glance, 2016 Classification: Major Uses: What Is Uranium? nonrenewable electricity Uranium is a naturally occurring radioactive element, that is very hard U.S. Energy Consumption: U.S. Energy Production: and heavy and is classified as a metal. It is also one of the few elements 8.427 Q 8.427 Q that is easily fissioned. It is the fuel used by nuclear power plants. 8.65% 10.01% Uranium was formed when the Earth was created and is found in rocks all over the world. Rocks that contain a lot of uranium are called uranium Lighter Atom Splits Element ore, or pitch-blende. Uranium, although abundant, is a nonrenewable energy source. Neutron Uranium Three isotopes of uranium are found in nature, uranium-234, 235 + Energy FISSION Neutron uranium-235, and uranium-238. These numbers refer to the number of Neutron neutrons and protons in each atom. Uranium-235 is the form commonly Lighter used for energy production because, unlike the other isotopes, the Element nucleus splits easily when bombarded by a neutron. During fission, the uranium-235 atom absorbs a bombarding neutron, causing its nucleus to split apart into two atoms of lighter mass. The first nuclear power plant came online in Shippingport, PA in 1957. At the same time, the fission reaction releases thermal and radiant Since then, the industry has experienced dramatic shifts in fortune. energy, as well as releasing more neutrons. The newly released neutrons Through the mid 1960s, government and industry experimented with go on to bombard other uranium atoms, and the process repeats itself demonstration and small commercial plants. -
Engineering Design of Aries-Iii*
PAPER ENGINEERING DESIGN OF ARIES-HI* O.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. Gierszewski, Canadian Fusion Fuels Tech. Prog., Mississauga, Ontario, Canada, L5J1K3 R. Hollies, Hollies Fluids Consulting, Pinawa, MB, ROE 1 L0 Canada and the ARIES Team M Z. <*• « (5 E B RECEIVE. AUG 2 6 1993 o M c -5 «3 OSTI Th« uibmitted manuscript has been authored by a contractor of the U. 5. Government under contract No. W-31-109-ENG-38- l Accordingly, the U. S. Government retains a nonexclusive, royalty-free license to publish or reproduce tha published form of this contribution, or allow others to do so, far U. 5. Government purposes. July 1993 •so * Work supported by the U.S. Department of Energy, Office of Fusion Energy, under Contract No. W-31-109-Eng-38. Paper to be presented at the Second Wisconsin Symposium on 3He and Fusion Power, University of Wisconsin, Madison, Wl, July 19-21,1993. DWTFMBUTION OF THIS DOOUMENT IS UNLIMITED ENGINEERING DESIGN OF ARIES-III* D.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, LA. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. -
Dr. Starr of Atomics International New Head of American Nuclear Societ Y Group Includes Members from 29 Countries Devoted to Ad- Vancement of Nuclear Scienc E
VOL. 1 NO. 2 ATOMICS INTERNATIONAL a division of North American Aviation, Inc . SEPTEMBER 1958 Dr. Starr Of Atomics International New Head Of American Nuclear Societ y Group Includes Members From 29 Countries Devoted To Ad- vancement Of Nuclear Scienc e At the annual meeting in June of the American Nuclear Society (ANS) . Dr. Chauncey Starr, general manager of Atomics International and vice president of North American Aviation, Inc., was elected president of the society to succeed Dr . Leland J . Haworth . Direc- tor of the Brookhaven National Laboratory . The American Nuclear Society was formed in 1955 to advance nuclear science and engineering . to encour- age research . establish scholarships. and to disseminate technical information . Membership of 3,000 Includes 29 Countries The organization's membership of 3 .000 includes about 140 members from 29 countries outside the United States representing many branches of science and technology . Members are associated with educa. tional , governmental, and research institutions, and with government contractors and industrial companies. First Student Award Establishe d In keeping with one of the objectives of the society, the first annual graduate student award has been estab- lished for the most outstanding graduate student work- ing in the nuclear sciences . NEW ANS OFFICERS-At the recent meeting of the URER ; Dr. Chauncey Starr, general manager of Atomics The award is the first of its kind by the society and American Nuclear Societe , new officers elected are : (felt International and vice-president of North American Avia- to right) John A . Swartnut, deputy director of Oak Ridge tion, Inc. PRESIDENT ; and Octave J. -
Exelon Nuclear Fact Sheet Exelon Nuclear, a Division of Exelon Generation, Is Headquartered in Kennett Square, Pa
Exelon Nuclear Fact Sheet Exelon Nuclear, a division of Exelon Generation, is headquartered in Kennett Square, Pa. and operates the largest U.S. fleet of carbon-free nuclear plants with more than 17,800 megawatts of capacity from 21 reactors at 12 facilities in Illinois, Maryland, New York and Pennsylvania. Dave Rhoades is President and Chief Nuclear Officer, Exelon Nuclear. There are more than 10,000 nuclear professionals working in Exelon Generation’s nuclear division. These professionals implement industry best practices to ensure safe, reliable operation throughout Exelon’s nuclear fleet. Exelon believes that clean, affordable energy is the key to a brighter, more sustainable future. Exelon’s nuclear power plants account for approximately 60 percent of Exelon’s power generation portfolio. Nuclear power plants are critical to the stability of the U.S. electrical grid because they can produce an uninterrupted flow of electricity for extended periods. This uninterrupted flow supplies the necessary level of baseload electricity for the grid to operate around-the-clock. Exelon’s nuclear stations Braidwood Generating Station Braceville, Illinois Byron Generating Station Byron, Illinois Calvert Cliffs Nuclear Power Plant Lusby, Maryland Clinton Power Station Clinton, Illinois Dresden Generating Station Morris, Illinois FitzPatrick Nuclear Power Plant Scriba, New York Ginna Nuclear Power Plant Ontario, New York LaSalle County Generating Station Marseilles, Illinois Limerick Generating Station Pottstown, Pennsylvania Nine Mile Point Nuclear Station Scriba, New York Peach Bottom Atomic Power Station Delta, Pennsylvania Quad Cities Generating Station Cordova, Illinois Updated: January 2021 .