Sample records for nuclear generating units

  1. Maintenance practices for emergency diesel generator engines onboard United States Navy Los Angeles class nuclear submarines

    E-Print Network [OSTI]

    Hawks, Matthew Arthur

    2006-01-01T23:59:59.000Z

    The United States Navy has recognized the rising age of its nuclear reactors. With this increasing age comes increasing importance of backup generators. In addition to the need for decay heat removal common to all (naval ...

  2. California Nuclear Profile - San Onofre Nuclear Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    San Onofre Nuclear Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  3. Power conversion unit studies for the next generation nuclear plant coupled to a high-temperature steam electrolysis facility†

    E-Print Network [OSTI]

    Barner, Robert Buckner

    2007-04-25T23:59:59.000Z

    The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold: 1) efficient low cost...

  4. Nuclear Power Generating Facilities (Maine)

    Broader source: Energy.gov [DOE]

    The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in...

  5. Managing nuclear predominant generating capacity

    SciTech Connect (OSTI)

    Bouget, Y.H.; Herbin, H.C.; Carbonnier, D.

    1998-07-01T23:59:59.000Z

    The most common belief, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires various actions be taken, ranging from a daily to a multi-annual perspective. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary.

  6. UNITED STATES NUCLEAR REGULATORY COMMISSION

    E-Print Network [OSTI]

    UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS ON RADIATION THERAPY OVEREXPOSURES IN PANAMA Addressees All medical licensees. Purpose The U.S. Nuclear persons in your institution who are involved with radiation therapy should review this notice

  7. Power conversion unit studies for the next generation nuclear plant coupled to a high-temperature steam electrolysis facility

    E-Print Network [OSTI]

    Barner, Robert Buckner

    2007-04-25T23:59:59.000Z

    -cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium-cooled Fast Reactor (SFR), Supercritical-water-cooled Reactor (SCWR) and the Very-high-temperature Reactor (VHTR). An international effort to develop these new... and the hydrogen production plant4,5. Davis et al. investigated the possibility of helium and molten salts in the IHTL2. The thermal efficiency of the power conversion unit is paramount to the success of this next generation technology. Current light water...

  8. United States Nuclear Waste Technical Review Board

    E-Print Network [OSTI]

    Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries A Report to CongressUnited States Nuclear Waste Technical Review Board Experience Gained From Programs to Manage High

  9. Nuclear power generation and fuel cycle report 1997

    SciTech Connect (OSTI)

    NONE

    1997-09-01T23:59:59.000Z

    Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

  10. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    JEC187V3 UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 of Energy 1000 Independence Avenue, SW Washington, DC 20585 Dear Secretary O'Leary: At the Nuclear Waste UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington, VA

  11. Nuclear power industry in the United States: status and projections

    SciTech Connect (OSTI)

    Connolly, T.J.

    1988-01-01T23:59:59.000Z

    One sixth of the electricity in the United States is now being generated in nuclear power plants, a remarkable achievement for a technology whose basic nuclear reaction was not even known 50 years ago. On the other hand, many of the nation's electric utilities are experiencing great difficulties completing the construction of their nuclear plants; 41 partially constructed plants have been abandoned. Those abandoned plants plus about 110 in operation and 15 still to be completed comprise the first generation of nuclear power plants in the United States. When, and even if, there will be a second generation is much in doubt. Data are presented to show that the absence of a second generation of nuclear plants will place large demands on the fossil fuels, with attendant high energy prices and high environmental costs the expected outcome. It appears that the future will bring large economic forces to start new orders for nuclear plants. On the other hand, the opposing institutional forces appear equally strong. Among the problems creating these institutional forces are the difficulty the United States is having in finding a politically acceptable approach to nuclear waste disposal and the vulnerability of power plant builders and operators to litigation and high financial risk. At present, the issue of a second generation of nuclear plants is stalemated. 17 references.

  12. United States Government National Nuclear Security Administration...

    Broader source: Energy.gov (indexed) [DOE]

    United States Government National Nuclear Security Administration (NNSA) Savannah River Field Office (SRFO) Memorandum DATE: January 10, 2014 REPLY TO ATTN OF: sv (McAlhany,...

  13. The Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Dr. David A. Petti

    2009-01-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950įC) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

  14. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    con144vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Dear Speaker Hastert, Senator Thurmond, and Secretary Richardson: The Nuclear Waste Technical Review with provisions of the Nuclear Waste Policy Amendments Act of 1987, Public Law 100-203. The Act requires the Board

  15. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

  16. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington.C. 20585 Dear Speaker Hastert, Senator Stevens, and Secretary Bodman: The Nuclear Waste Technical Review Board was created by Congress in the Nuclear Waste Policy Amendments Act (NWPAA) of 1987 and charged

  17. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington Dear Speaker Pelosi, Senator Byrd, and Secretary Bodman: The Nuclear Waste Technical Review Board, and transporting high-level radioactive waste and spent nuclear fuel. The Board is required to report its findings

  18. EIS-0476: Vogtle Electric Generating Plant, Units 3 and 4

    Broader source: Energy.gov [DOE]

    This EIS evaluates the environmental impacts of construction and startup of the proposed Units 3 and 4 at the Vogtle Electric Generating Plant in Burke County, Georgia. DOE adopted two Nuclear Regulatory Commission EISs associated with this project (i.e., NUREG-1872, issued 8/2008, and NUREG-1947, issued 3/2011).

  19. Renewable Electricity Generation in the United States

    E-Print Network [OSTI]

    Schmalensee, Richard

    This paper provides an overview of the use of renewable energy sources to generate electricity in the United States and a critical analysis of the federal and state policies that have supported the deployment of renewable ...

  20. Kansas Nuclear Profile - Wolf Creek Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    April 2012" "Next Release Date: February 2013" "Wolf Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor...

  1. Washington Nuclear Profile - Columbia Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Columbia Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

  2. Illinois Nuclear Profile - Dresden Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Dresden Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

  3. Illinois Nuclear Profile - Braidwood Generation Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Braidwood Generation Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  4. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    of the overall system for managing spent fuel and defense high-level waste. The Board includes its findingsjlc029va UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, D.C. 20585 Dear Speaker Gingrich, Senator Thurmond, and Secretary PeŮa: The Nuclear Waste Technical

  5. Operating strategy generators for nuclear reactors

    SciTech Connect (OSTI)

    Solovyev, D. A., E-mail: and@est.mephi.ru; Semenov, A. A.; Shchukin, N. V. [National Research Nuclear University MEPhI (Russian Federation)

    2011-12-15T23:59:59.000Z

    Operating strategy generators, i.e., the software intended for increasing the efficiency of work of nuclear power plant operators, are discussed. The possibilities provided by the domestic and foreign operating-strategy generators are analyzed.

  6. Managing nuclear weapons in the United States

    SciTech Connect (OSTI)

    Miller, G.

    1993-03-16T23:59:59.000Z

    This report discusses the management and security of nuclear weapons in the post-cold war United States. The definition of what constitutes security is clearly changing in the US. It is now a much more integrated view that includes defense and the economy. The author tries to bring some semblance of order to these themes in this brief adaptation of a presentation.

  7. United States-Republic of Korea (ROK) International Nuclear Energy...

    Office of Environmental Management (EM)

    United States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting United States-Republic of Korea (ROK) International...

  8. Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:

    Broader source: Energy.gov [DOE]

    Nuclear power plants in the United States currently produce about 20 percent of the nationís electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit...

  9. Optimization of auxiliary power systems design for large generating units

    SciTech Connect (OSTI)

    Fabri, E.I.; Kang, E.K.; Dusterdick, R.W.

    1980-01-01T23:59:59.000Z

    Modern fossil and nuclear generating units require the support of a fairly large and complex electric auxiliary power system. The selection of an optimized and cost-effective auxiliary power transformer rating may be a difficult process, since the loading profile and coincident operation of the loads often cannot be firmly defined at an early stage of design. The authors believe that this important design process could be greatly aided by systematic field tests and recording of the actual auxiliary loading profiles during various modes of plant operations.

  10. The Fourth Generation of Nuclear Power

    SciTech Connect (OSTI)

    Lake, James Alan

    2000-11-01T23:59:59.000Z

    The outlook for nuclear power in the U.S. is currently very bright. The economics, operations and safety performance of U.S. nuclear power plants is excellent. In addition, both the safety and economic regulation of nuclear power are being changed to produce better economic parameters for future nuclear plant operations and the licenses for plant operations are being extended to 60 years. There is further a growing awareness of the value of clean, emissions-free nuclear power. These parameters combine to form a firm foundation for continued successful U.S. nuclear plant operations, and even the potential In order to realize a bright future for nuclear power, we must respond successfully to five challenges: ē Nuclear power must remain economically competitive, ē The public must remain confident in the safety of the plants and the fuel cycle. ē Nuclear wastes and spent fuel must be managed and the ultimate disposition pathways for nuclear wastes must be politically settled. ē The proliferation potential of the commercial nuclear fuel cycle must continue to be minimized, and ē We must assure a sustained manpower supply for the future and preserve the critical nuclear technology infrastructure. The Generation IV program is conceived to focus the efforts of the international nuclear community on responding to these challenges.

  11. Solving the Unit Commitment Problem in Power Generation by Primal and Dual Methods

    E-Print Network [OSTI]

    RŲmisch, Werner

    - storage hydro plants a large-scale mixed integer optimization model for unit commitment is developed optimal scheduling of on/o decisions and output levels for generating units in a power system over on the shares of nuclear, conventional thermal, hydro and pumped-storage hydro power in the underlying

  12. Generation IV Nuclear Energy Systems ...

    E-Print Network [OSTI]

    Kemner, Ken

    of electricity and total emissions of carbon dioxide (CO2 )--a greenhouse gas. According to the U.S. Environmental Protection Agency, electricity generation currently produces about 40 percent of our CO2 emissions in per capita use of electricity and total emissions of carbon dioxide (CO2 )--a greenhouse gas

  13. California Nuclear Profile - San Onofre Nuclear Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5 Tables July 1996 Energy Information Administration Office of Coal, Nuclear, Electric andIndustrialSan Onofre Nuclear Generating

  14. STOCHASTIC FLOW SEQUENCE GENERATION AND ASPINALL UNIT OPERATIONS

    E-Print Network [OSTI]

    to incorporate paleo #12;iv reconstructed data. The selected methods are then employed to generate syntheticSTOCHASTIC FLOW SEQUENCE GENERATION AND ASPINALL UNIT OPERATIONS By KENNETH C NOWAK B Flow Sequence Generation and Aspinall Unit Operations written by Kenneth C Nowak has been approved

  15. World Net Nuclear Electric Power Generation, 1980-2007 - Datasets...

    Open Energy Info (EERE)

    U.S. Energy Information ... World Net Nuclear Electric ... Dataset Activity Stream World Net Nuclear Electric Power Generation, 1980-2007 International data showing world net...

  16. UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

    E-Print Network [OSTI]

    Laughlin, Robert B.

    In the Matter of CALVERT CLIFFS 3 NUCLEAR PROJECT, LLC, and UNISTAR NUCLEAR OPERATING SERVICES, LLC (Combined, 2009 MEMORANDUM AND ORDER (Ruling on Joint Petitioners' Standing and Contentions) I. Introduction This case arises from an application by UniStar Nuclear Operating Services, LLC and Calvert Cliffs 3 Nuclear

  17. Nuclear power generation and fuel cycle report 1996

    SciTech Connect (OSTI)

    NONE

    1996-10-01T23:59:59.000Z

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

  18. Nuclear-fuel-cycle facility deployment and price generation

    SciTech Connect (OSTI)

    Andress, D.A.

    1981-04-01T23:59:59.000Z

    The enrichment process and how it is to be modeled in the International Nuclear Model (INM) is described. The details of enrichment production, planning, unit price generation, demand estimation and ordering are examined. The enrichment process from both the producer's and the utility's point of view is analyzed. The enrichment separative-work-unit (SWU) contracts are also discussed. The relationship of the enrichment process with other sectors of the nuclear fuel cycle, expecially uranium mining and milling is considered. There are portions of the enrichment process that are not completely understood at the present time. These areas, which require further study, will be pinpointed in the following discussion. In many cases, e.g., the advent of SMU brokerage activities, the answers will emerge only in time. In other cases, e.g., political trends, uncertainties will always remain. It is possible to cast the uncertainties in a probabilistic framework, but this is beyond the scope of this report. INM, a comprehensive model of the international nuclear industry, simulates the market decision process based on current and future price expectations under a broad range of scenario specifications. INM determines the proper reactor mix as well as the planning, operation, and unit price generation of the attendant nuclear fuel cycle facilities. The level of detail of many of the enrichment activities presented in this report, e.g., the enrichment contracts, is too fine to be incorporated into INM. Nevertheless, they are presented in a form that is ammendable to modeling. The reasons for this are two-fold. First, it shows the level of complexity that would be required to model the entire system. Second, it presents the structural framework for a detailed, stand-alone enrichment model.

  19. Salt disposal of heat-generating nuclear waste.

    SciTech Connect (OSTI)

    Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

    2011-01-01T23:59:59.000Z

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

  20. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    's mission, continuing role, and refocused goals as the U.S. approach to managing spent nuclear fuel and high an ongoing and integrated technical peer review of all DOE activities related to managing spent nuclear fuel, and the characteristics and quantities of waste associated with adopting alternatives for spent nuclear fuel management

  1. UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD

    E-Print Network [OSTI]

    and issues related to the waste- management system, including transportation of spent nuclear fuel and high of Energy, including the possible development of a repository for disposing of spent nuclear fuel and high activities related to the possible disposal, packaging, and transportation of the country's spent nuclear

  2. Minimal nuclear deterrence : a nuclear arsenal reduction plan for the United States

    E-Print Network [OSTI]

    Laderman, Sarah (Sarah Jane)

    2012-01-01T23:59:59.000Z

    The global political climate has called for reductions to nuclear arsenals around the world. This thesis researches how potential deep cuts to the United States' large strategic nuclear arsenal would affect its current ...

  3. New Jersey Nuclear Profile - PSEG Salem Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    PSEG Salem Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  4. New Jersey Nuclear Profile - PSEG Hope Creek Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    PSEG Hope Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  5. Illinois Nuclear Profile - LaSalle Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    LaSalle Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

  6. Nuclear steam-generator transplant total rises

    SciTech Connect (OSTI)

    Smock, R.

    1982-09-01T23:59:59.000Z

    Several utilities with pressurized water reactors (PWRs) are replacing leaking and corroded steam generators. Over half the PWRs face corrosion problems that will cost $50 million to $100 million per unit to correct. An alternative approach of installing new tube sleeves has only had one application. Corrosion prevention still eludes utilities, whose problems differ. Westinghouse units were the first to experience corrosion problems because they have almost all operated for a decade or more. Some advances in condenser and steam-generator technology should extend the component life of younger units, and some leaking PWR tubes can be plugged. Operating differences may explain why PWRs have operated for over 20 years on submarines using phosphate water chemistry, while the use of de-aerators in the secondary-systems of foreign PWRs may explain their better performance. Among the corrective steps recommended by Stone and Webster are tighter chemistry control, better plant layup practices, revamping secondary-system hardware, condensate polishing, and de-aerators. Research continues to find the long-term preventative. 2 tables. (DCK)

  7. EIS-0362: Colorado Springs Utilities' Next Generation CFB Coal Generating Unit, CO

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's decision to approve Colorado Springs Utilities design, construction, and operation of their Next- Generation Circulating Fluidized Bed (CFB) Coal Generating Unit demonstration plant near Fountain, El Paso County, Colorado.

  8. United States nuclear tests, July 1945 through September 1992

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

  9. Nuclear Power Overview

    Broader source: Energy.gov (indexed) [DOE]

    San Onofre Nuclear Generating Station San Onofre Nuclear Generating Station Bob Ashe-Everest Southern California Edison 10 Incoming New Fuel Inspecting New Fuel SONGS Unit 1 Fuel...

  10. Next Generation Rooftop Unit | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in Many DevilsForumEngines |NewStateDepartment of(BETO)Next Generation

  11. Ongoing Space Nuclear Systems Development in the United States

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Werner; S. Johnson; Michael G. Houts; Donald T. Palac; Lee S. Mason; David I. Poston; A. Lou Qualls

    2011-10-01T23:59:59.000Z

    Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for spacecraft power; and fission power systems for electric propulsion or direct thermal propulsion. Each of these areas has been investigated in the United States since the 1950s, achieving various stages of development. While some nuclear systems have achieved flight deployment, others continue to be researched today. This paper will provide a brief overview of historical space nuclear programs in the U.S. and will provide a summary of the ongoing space nuclear systems research, development, and deployment in the United States.

  12. Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana)

    Broader source: Energy.gov [DOE]

    The Incentive Cost Recovery Rule for Nuclear Power Generation establishes guidelines for any utility seeking to develop a nuclear power plant in Louisiana. The rule clarifies, as well as...

  13. Monthly Nuclear Utility Generation by State and Reactor, 2007

    U.S. Energy Information Administration (EIA) Indexed Site

    applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2007" "January through December 2007"...

  14. Monthly Nuclear Utility Generation by State and Reactor, 2004

    U.S. Energy Information Administration (EIA) Indexed Site

    applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2004" "January through December 2004"...

  15. Monthly Nuclear Utility Generation by State and Reactor, 2005

    U.S. Energy Information Administration (EIA) Indexed Site

    applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2005" "January through December 2005"...

  16. Monthly Nuclear Utility Generation by State and Reactor, 2003

    U.S. Energy Information Administration (EIA) Indexed Site

    applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2003" "January through December 2003"...

  17. Monthly Nuclear Utility Generation by State and Reactor, 2008

    U.S. Energy Information Administration (EIA) Indexed Site

    applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2008" "January through December 2008"...

  18. C Produced by Nuclear Power Reactors Generation and Characterization of

    E-Print Network [OSTI]

    Haviland, David

    14 C Produced by Nuclear Power Reactors ¬≠ Generation and Characterization of Gaseous, Liquid and process water from nuclear reactors ¬≠ A method for quantitative determination of organic and inorganic and Solid Waste √?sa Magnusson Division of Nuclear Physics Department of Physics 2007 Akademisk avhandling

  19. Computer Generation of Process Explanations in Nuclear Astrophysics

    E-Print Network [OSTI]

    Langley, Pat

    Computer Generation of Process Explanations in Nuclear Astrophysics Sakir Kocabas (uckoca describe Astra, a computational aid for generating process explanations in nuclear astrophysics. The system capture, as well as novel fusion reactions that produce neutrons and deuterium. The system has also

  20. Computer Generation of Process Explanations in Nuclear Astrophysics

    E-Print Network [OSTI]

    Langley, Pat

    Computer Generation of Process Explanations in Nuclear Astrophysics Sakir Kocabas (uckoca In this paper we describe Astra, a computational aid for generating process explanations in nuclear astrophysics and neutron capture, as well as novel fusion reactions that produce neutrons and deuterium. The system has

  1. Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.; DAgostino, A.

    2012-01-17T23:59:59.000Z

    The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

  2. Next Generation Nuclear Plant GAP Analysis Report

    SciTech Connect (OSTI)

    Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

    2008-12-01T23:59:59.000Z

    As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

  3. Evaluating Russian space nuclear reactor technology for United States applications

    SciTech Connect (OSTI)

    Polansky, G.F. [Phillips Lab., Albuquerque, NM (United States); Schmidt, G.L. [New Mexico Engineering Research Institute, Albuquerque, NM (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Lab., Laurel, MD (United States)

    1994-08-01T23:59:59.000Z

    Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch.

  4. Illinois Nuclear Profile - Byron Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Byron Generating Station" ,"Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  5. A Roadmap to Deploy New Nuclear Power Plants in the United States...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume...

  6. Fluorescent lamp unit with magnetic field generating means

    DOE Patents [OSTI]

    Grossman, M.W.; George, W.A.

    1989-08-08T23:59:59.000Z

    A fluorescent lamp unit having a magnetic field generating means for improving the performance of the fluorescent lamp is disclosed. In a preferred embodiment the fluorescent lamp comprises four longitudinally extending leg portions disposed in substantially quadrangular columnar array and joined by three generally U-shaped portions disposed in different planes. In another embodiment of the invention the magnetic field generating means comprises a plurality of permanent magnets secured together to form a single columnar structure disposed within a centrally located region defined by the shape of lamp envelope. 4 figs.

  7. Risk Framework for the Next Generation Nuclear Power Plant Construction

    E-Print Network [OSTI]

    Yeon, Jaeheum 1981-

    2012-12-11T23:59:59.000Z

    sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks...

  8. Risk Framework for the Next Generation Nuclear Power Plant Construction†

    E-Print Network [OSTI]

    Yeon, Jaeheum 1981-

    2012-12-11T23:59:59.000Z

    sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks...

  9. Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect

    E-Print Network [OSTI]

    Xu, T.

    2009-01-01T23:59:59.000Z

    Lying Repositories for Nuclear Waste, NAGRA Technical Reporthost rock formation for nuclear waste storage. EngineeringGas Generation in a Nuclear Waste Repository: Reactive

  10. NEXT GENERATION NUCLEAR PLANT PROJECT IMPLEMENTATION STRATEGY

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    include steam turbine generators, steam turbine mechanical drives, process steam, process heat exchangers and reactors, district energy systems, and thermal desalination processes....

  11. Fourth Generation Nuclear Weapons: Military effectiveness and collateral effects

    E-Print Network [OSTI]

    Gsponer, A

    2005-01-01T23:59:59.000Z

    The paper begins with a general introduction and update to Fourth Generation Nuclear Weapons (FGNW), and then addresses some particularly important military aspects on which there has been only limited public discussion so far. These aspects concern the unique military characteristics of FGNWs which make them radically different from both nuclear weapons based on previous-generation nuclear-explosives and from conventional weapons based on chemical-explosives: yields in the 1 to 100 tons range, greatly enhanced coupling to targets, possibility to drive powerful shaped charged jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

  12. Washington Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Columbia Generating Station Unit...

  13. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

    Powell, J.R.; Reich, M.; Ludewig, H.; Todosow, M.

    1999-02-09T23:59:59.000Z

    A particle accelerator generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer and a neutron filter are also used for preferentially degrading the secondary particles into a lower energy range if desired. 18 figs.

  14. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

    Powell, James R. (Shoreham, NY); Reich, Morris (Flushing, NY); Ludewig, Hans (Brookhaven, NY); Todosow, Michael (Miller Place, NY)

    1999-02-09T23:59:59.000Z

    A particle accelerator (12) generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target (14) is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target (14) produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer (44) and a neutron filter (42) are also used for preferentially degrading the secondary particles into a lower energy range if desired.

  15. Property:NbrGeneratingUnits | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal PwerPerkins County, Nebraska:PrecourtOid JumpEligSysSizeNbrGeneratingUnits Jump to: navigation,

  16. U.S. Nuclear Generation of Electricity

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening aTurbulence may be keyNuclearEconomic

  17. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Marra, J.

    2010-09-29T23:59:59.000Z

    Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  18. Status of Potential New Commercial Nuclear Reactors in the United Release Date: December 2007

    E-Print Network [OSTI]

    Noble, James S.

    1 Status of Potential New Commercial Nuclear Reactors in the United States Release Date: December for building new nuclear power reactors in the United States. Evidence of this includes press releases and conditionally operate new commercial nuclear reactors. Actual applications will also be included on future

  19. Illinois Nuclear Profile - Byron Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5 Tables July 1996 Energy Information Administration Office of Coal,Cubic Feet) Decade Year-0Elements)GasByron Generating

  20. Job Creation Due to Nuclear Power Resurgence in The United States

    SciTech Connect (OSTI)

    C. R. Kenley; R. D. Klingler; C. M. Plowman; R. Soto; R. J. Turk; R. L. Baker; S. A. Close; V. L. McDonnell; S. W. Paul; L. R. Rabideau; S. S. Rao; B. P. Reilly

    2009-11-01T23:59:59.000Z

    The recent revival of global interest in the next generation of nuclear power reactors is causing a reexamination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current U.S. industries to support a renewal of nuclear power plant deployment. Key among the many questions currently being asked is what potential exists for the creation of new jobs as a result of developing and operating these new plants? Idaho National Laboratory and Bechtel Power Corporation collaborated to perform a Department of Energy-sponsored study that evaluated the potential for job creation in the U.S. should these new next generation nuclear power plants be built. The study focused primarily on providing an initial estimate of the numbers of new manufacturing jobs that could be created, including those that could be repatriated from overseas, resulting from the construction of these new reactors. In addition to the growth in the manufacturing sector, the study attempted to estimate the potential increase in construction trades necessary to accomplish the new construction.

  1. Operable Generating Units in the United States by State and Energy Source, 2011

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15LiquidBGOperable Generating Units in the

  2. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

    SciTech Connect (OSTI)

    Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

    1993-03-01T23:59:59.000Z

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

  3. Active Interrogation Using Electronic Neutron Generators for Nuclear Safeguards Applications

    SciTech Connect (OSTI)

    David L. Chichester; Edward H. Seabury

    2008-08-01T23:59:59.000Z

    Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. The most commonly used technique for performing active interrogation is to use an electronic neutron generator as the probe radiation source. Exploiting the unique operating characteristics of these devices, including their monoenergetic neutron emissions and their ability to operate in pulsed modes, presents a number of options for performing prompt and delayed signature analyses using both photon and neutron sensors. A review of literature in this area shows multiple applications of the active neutron interrogation technique for performing nuclear nonproliferation measurements. Some examples include measuring the plutonium content of spent fuel, assaying plutonium residue in spent fuel hull claddings, assaying plutonium in aqueous fuel reprocessing process streams, and assaying nuclear fuel reprocessing facility waste streams to detect and quantify fissile material. This paper discusses the historical use of this technique and examines its context within the scope and challenges of next-generation nuclear fuel cycles and advanced concept nuclear fuel cycle facilities.

  4. Transient Testing of Nuclear Fuels and Materials in United States

    SciTech Connect (OSTI)

    Daniel M. Wachs

    2012-12-01T23:59:59.000Z

    The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation LWR fuel with enhanced performance and safety and reduced waste generation since 2010. This program, which has emphasized collaboration between the DOE, U.S. national laboratories and nuclear industry, was refocused from enhanced performance to enhanced accident tolerance following the events at Fukushima in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with standard UO2-Zircaloy, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022 .

  5. The future of nuclear power in the United States : economic and regulatory challenges

    E-Print Network [OSTI]

    Joskow, Paul L.

    2006-01-01T23:59:59.000Z

    This paper examines the economic and regulatory challenges that must be faced by potential investors in new nuclear power plants in the United States. The historical development of the existing fleet of over 100 nuclear ...

  6. Nuclear New Build in the United States 1990-2010: A Three State Analysis

    E-Print Network [OSTI]

    Heffron, Raphael J.

    2012-01-23T23:59:59.000Z

    This research examines nuclear energy policy across three states in the United States (US) - Georgia, Pennsylvania, and Texas - from 1990-2010. The main research question seeks to ascertain what the prerequisites are for successful nuclear new build...

  7. Viability of an expanded United States nuclear power program and its effects on energy markets

    E-Print Network [OSTI]

    Khan, Tanzeer S

    2006-01-01T23:59:59.000Z

    The four biggest energy sources in the United States are coal, crude oil, natural gas, and nuclear power. While coal and nuclear power are produced domestically, more than 70% of crude oil and 20% of natural gas is imported. ...

  8. New Generation Nuclear Plant -- High Level Functions and Requirements

    SciTech Connect (OSTI)

    J. M. Ryskamp; E. J. Gorski; E. A. Harvego; S. T. Khericha; G. A. Beitel

    2003-09-01T23:59:59.000Z

    This functions and requirements (F&R) document was prepared for the Next Generation Nuclear Plant (NGNP) Project. The highest-level functions and requirements for the NGNP preconceptual design are identified in this document, which establishes performance definitions for what the NGNP will achieve. NGNP designs will be developed based on these requirements by commercial vendor(s).

  9. Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1

    SciTech Connect (OSTI)

    None

    2005-03-01T23:59:59.000Z

    As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R&D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R&D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan.

  10. Hydrogen Production from the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    M. Patterson; C. Park

    2008-03-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

  11. CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS

    SciTech Connect (OSTI)

    Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

    2004-10-03T23:59:59.000Z

    The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

  12. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect (OSTI)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  13. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G. O. Hayner; E.L. Shaber

    2004-09-01T23:59:59.000Z

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  14. Test factoring with amock: generating readable unit tests from system tests

    E-Print Network [OSTI]

    Glasser, David Samuel

    2007-01-01T23:59:59.000Z

    Automated unit tests are essential for the construction of reliable software, but writing them can be tedious. If the goal of test generation is to create a lasting unit test suite (and not just to optimize execution of ...

  15. The Next Generation Air Particle Detectors for the United States Navy

    SciTech Connect (OSTI)

    Robert Hayes and Craig Marianno

    2007-06-24T23:59:59.000Z

    Design and testing of the United States Navyís next generation air particle detector (NGAPD) is presently underway. The NGAPD is intended for use in nuclear applications for the United States Navy and is being designed to detect airborne Co-60 with a reduction in false alarms and improved ease of use. Features being developed include gamma compensation, low maintenance, commercial off-the-shelf electronics, and spectrum simulation for quality assurance and functional testing applications. By supplying a spectrum simulator, the radon stripping algorithm can be running when a simulated anthropogenic source spectrum (e.g., from Co-60 or transuranics) is superimposed on the radon progeny spectrum. This will allow alarm levels to be tested when the air flow is running and the radon stripping algorithm is providing the instrument response output. Modern units evaluate source spectra with the air flow off and the radon spectrum absent thereby not testing the true system performance which comes out of the radon stripping algorithm. Testing results of the preliminary prototype show promise along with computer simulations of source spectra. Primary testing results taken to date include gamma compensation, thermal insults, vibration and spectrum simulation.

  16. United States and Japan Sign Joint Nuclear Energy Action Plan...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of a global nuclear energy infrastructure as envisioned in GNEP to develop innovative nuclear reactor and fuel cycle technologies. GNEP seeks to bring about a significant,...

  17. A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Edward J. Gorski; Charles V. Park; Finis H. Southworth

    2004-06-01T23:59:59.000Z

    Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the Presidentís Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project.

  18. An examination of the pursuit of nuclear power plant construction projects in the United States

    E-Print Network [OSTI]

    Guyer, Brittany (Brittany Leigh)

    2011-01-01T23:59:59.000Z

    The recent serious reconsideration of nuclear power as a means for U.S. electric utilities to increase their generation capacity provokes many questions regarding the achievable success of future nuclear power plant ...

  19. Iowa Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Duane Arnold Energy Center Unit...

  20. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    SciTech Connect (OSTI)

    BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

    2003-06-01T23:59:59.000Z

    OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficien

  1. Tool-Assisted Unit-Test Generation and Selection Based on Operational Abstractions

    E-Print Network [OSTI]

    Xie, Tao

    Tool-Assisted Unit-Test Generation and Selection Based on Operational Abstractions Tao Xie1 of Washington, Seattle, WA 98105 Abstract. Unit testing, a common step in software development, presents a chal- lenge. When produced manually, unit test suites are often insufficient to identify defects. The main

  2. Wisconsin Nuclear Profile - Point Beach Nuclear Plant

    U.S. Energy Information Administration (EIA) Indexed Site

    Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

  3. Tennessee Nuclear Profile - Watts Bar Nuclear Plant

    U.S. Energy Information Administration (EIA) Indexed Site

    Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

  4. Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

  5. Arkansas Nuclear Profile - Arkansas Nuclear One

    U.S. Energy Information Administration (EIA) Indexed Site

    Nuclear One" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  6. Alternative similarity renormalization group generators in nuclear structure calculations

    E-Print Network [OSTI]

    Nuiok M. Dicaire; Conor Omand; Petr Navratil

    2014-08-22T23:59:59.000Z

    The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.

  7. West European nuclear power generation research and development

    SciTech Connect (OSTI)

    Turinsky, P.J.; Baron, S.; Burch, W.D.; Corradini, M.L.; Lucas, G.E.; Matthews, R.B.; Uhrig, R.E.

    1991-09-01T23:59:59.000Z

    This report assesses the status of West European research and development (R&D) in support of nuclear power generation. The focus is on light-water reactors (LWRs), as they will likely be the only concept commerically implemented within the next decade. To a laser degree, alternative concepts such as the high-temperature gas cooled reactor and the liquid-metal reactor (LMR) are also assessed. To bound the study, only the fuel cycle stages of fuel fabrication, power generation, and fuel reprocessing are considered. Under the topic of power generation, the subtopics of core reactor physics, materials, instrumentation and control systems, nuclear power safety, and power plant fabrication and construction are addressed. The front-end fuel cycle stages of mining and milling, conversion and enrichment, and the back-end fuel cycle stages of waste conditioning and disposal and not considered. Most assessments for light-water reactor R&D are completed on a country-by-country basis since there is limited cooperation among the West European countries due to the commercial relevance of R&D in this area.

  8. West European nuclear power generation research and development

    SciTech Connect (OSTI)

    Turinsky, P.J.; Baron, S.; Burch, W.D.; Corradini, M.L.; Lucas, G.E.; Matthews, R.B.; Uhrig, R.E.

    1991-09-01T23:59:59.000Z

    This report assesses the status of West European research and development (R D) in support of nuclear power generation. The focus is on light-water reactors (LWRs), as they will likely be the only concept commerically implemented within the next decade. To a laser degree, alternative concepts such as the high-temperature gas cooled reactor and the liquid-metal reactor (LMR) are also assessed. To bound the study, only the fuel cycle stages of fuel fabrication, power generation, and fuel reprocessing are considered. Under the topic of power generation, the subtopics of core reactor physics, materials, instrumentation and control systems, nuclear power safety, and power plant fabrication and construction are addressed. The front-end fuel cycle stages of mining and milling, conversion and enrichment, and the back-end fuel cycle stages of waste conditioning and disposal and not considered. Most assessments for light-water reactor R D are completed on a country-by-country basis since there is limited cooperation among the West European countries due to the commercial relevance of R D in this area.

  9. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  10. Symstra: A Framework for Generating Object-Oriented Unit Tests Using Symbolic Execution

    E-Print Network [OSTI]

    Weimer, Westley

    Symstra: A Framework for Generating Object-Oriented Unit Tests Using Symbolic Execution Tao Xie1 write tests for every aspect of the classes they develop. However, manual test generation is time [12] to generate covering method sequences. But AsmLT requires the user to carefully choose

  11. Symstra: A Framework for Generating Object-Oriented Unit Tests using Symbolic Execution

    E-Print Network [OSTI]

    Xie, Tao

    Symstra: A Framework for Generating Object-Oriented Unit Tests using Symbolic Execution Tao Xie1 testers) who write tests for every aspect of the classes they develop. However, manual test generation] to generate covering method sequences. But AsmLT requires the user to carefully choose sufficiently large

  12. United States Nuclear Tests, July 1945 through September 1992, December 2000

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    2000-12-01T23:59:59.000Z

    This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

  13. NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 1

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01T23:59:59.000Z

    Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

  14. NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 2

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01T23:59:59.000Z

    Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

  15. Decision-support tool for assessing future nuclear reactor generation portfolios.

    E-Print Network [OSTI]

    Oosterlee, Cornelis W. "Kees"

    Decision-support tool for assessing future nuclear reactor generation portfolios. Shashi Jain, where especially capital costs are known to be highly uncertain. Differ- ent nuclear reactor types uncertainties in the cost elements of a nuclear power plant, to provide an optimal portfolio of nuclear reactors

  16. INL Director Discusses the Future for Nuclear Energy in the United States

    ScienceCinema (OSTI)

    Grossenbacher, John

    2013-05-28T23:59:59.000Z

    Idaho National Laboratory's Director John Grossenbacher explains that the United States should develop its energy policies based on an assessment of the current events at Japan's Fukushima nuclear reactors and the costs and benefits of providing electricity through various energy sources. For more information about INL's nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

  17. INL Director Discusses the Future for Nuclear Energy in the United States

    SciTech Connect (OSTI)

    Grossenbacher, John

    2011-01-01T23:59:59.000Z

    Idaho National Laboratory's Director John Grossenbacher explains that the United States should develop its energy policies based on an assessment of the current events at Japan's Fukushima nuclear reactors and the costs and benefits of providing electricity through various energy sources. For more information about INL's nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

  18. Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

    2011-01-01T23:59:59.000Z

    Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

  19. Kansas Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear net generation (percent)","Owner" "Wolf Creek Generating Station Unit 1","1,160","9,556",100.0,"Wolf Creek Nuclear Optg Corp" "1 Plant 1 Reactor","1,160","9,556",100.0...

  20. Evaluation of the Effectiveness of a New Technology for Extraction of Insoluble Impurities from Nuclear Power Plant Steam Generators with Purge Water

    SciTech Connect (OSTI)

    Bud'ko, I. O. [JSC NIITsE 'Tsentrenergo' (Russian Federation)] [JSC NIITsE 'Tsentrenergo' (Russian Federation); Zhukov, A. G. [Rostov Nuclear Power Plant (Russian Federation)] [Rostov Nuclear Power Plant (Russian Federation)

    2013-11-15T23:59:59.000Z

    An experimental technology for the removal of insoluble impurities from a horizontal steam generator with purge water during planned shutdowns of the power generating unit is improved through a more representative determination of the concentration of impurities in the purge water ahead of the water cleanup facility and a more precise effective time for the duration of the purge process. Tests with the improved technique at power generating unit No. 1 of the Rostov Nuclear Power Plant show that the efficiency with which insoluble impurities are removed from the steam generator volume was more than two orders of magnitude greater than under the standard regulations.

  1. Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

    2009-03-01T23:59:59.000Z

    The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

  2. Methodology The electricity generation and distribution network in the Western United States is

    E-Print Network [OSTI]

    Hall, Sharon J.

    Methodology The electricity generation and distribution network in the Western United States is comprised of power plants, electric utilities, electrical transformers, transmission and distribution infrastructure, etc. We conceptualize the system as a transportation network with resources (electricity

  3. Modeling Water Withdrawal and Consumption for Electricity Generation in the United States

    E-Print Network [OSTI]

    Strzepek, Kenneth M.

    2012-06-15T23:59:59.000Z

    Water withdrawals for thermoelectric cooling account for a significant portion of total water use in the United States. Any change in electrical energy generation policy and technologies has the potential to have a major ...

  4. Next Generation Nuclear Plant Resilient Control System Functional Analysis

    SciTech Connect (OSTI)

    Lynne M. Stevens

    2010-07-01T23:59:59.000Z

    Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

  5. NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER

    SciTech Connect (OSTI)

    Mark Holbrook

    2010-09-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

  6. Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

    SciTech Connect (OSTI)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

  7. Use of tangential filtration unit for processing liquid waste from nuclear laundries

    SciTech Connect (OSTI)

    Augustin, X.; Buzonniere, A. de [Technicatome, Gif-sur-Yvette (France); Barnier, H. [CEA Cadarache, St. Paul-lez-Durance (France)

    1993-12-31T23:59:59.000Z

    Nuclear facilities produce large quantities of weakly contaminated effluents charged with insoluble and soluble products. In collaboration with CEA, TECHNICATOME has developed an ultrafiltration process for liquid waste from nuclear facilities associated with prior insolubilization of radiochemical activity. This process, seeded ultrafiltration, is based on the use of a decloggable mineral filter media and combines very high separation efficiency with long membrane life. The efficiency of the tangential filtration unit which has been processing effluents from the Cadarache Nuclear Research Center (CEA-France) nuclear facility since mid-1988, has been confirmed on several sites.

  8. United States Nuclear Command and Control System Support Staff. Directive

    SciTech Connect (OSTI)

    Kennedy, R.

    1988-02-03T23:59:59.000Z

    The Directive establishes, pursuant to National Security Decision Directive, August 21, 1987, and the authority vested in the Secretary of Defense, the U.S. Nuclear Command and Control System Support Staff under the direction, authority, and control of the Secretary of Defense, who also serves as the Executive Agent for the Nuclear Command and Control System (NCCS) (hereafter referred to as Executive Agent). The Directive establishes the DoD NCCS Executive Review Committee (ERC) in support of the Secretary of Defense. It assigns the responsibilities, functions, relationships and authorities of the U.S. NCCS Support Staff (NSS) and its Director, and those of the ERC.

  9. Power Flow Analysis Algorithm for Islanded LV Microgrids Including Distributed Generator Units with

    E-Print Network [OSTI]

    Chaudhary, Sanjay

    Power Flow Analysis Algorithm for Islanded LV Microgrids Including Distributed Generator Units With larger portion of growing electricity demand which is being fed through distributed generation (DG power system. Being able to operate in both grid-connected and islanded mode, a microgrid manages

  10. Commercial Nuclear Power 1984: prospects for the United States and the World

    SciTech Connect (OSTI)

    Gielecki, M.; Diedrich, R.; Hewlett, J.; Murphy, T.

    1984-11-27T23:59:59.000Z

    This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). The report provides documentation of the US nuclear capacity and generation projections through 1995 that are presented in the Annual Energy Outlook 1983. Additionally, US nuclear capacity and generation projections through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982. The projections for foreign nuclear capacity through 1990 supplant the preliminary foreign WOCA projection presented in the Annual Energy Outlook 1983 and are supplemented by WOCA country-specific projections through 2000.

  11. Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels

    E-Print Network [OSTI]

    Hackemack, Michael Wayne

    2013-04-15T23:59:59.000Z

    , for generating individual fission event result channels and analyzing their specific response in the fuel. We utilized the nuclear reaction simulation tool, TALYS, to generate energy-dependent fission fragment yield distributions for different fissile/fissionable...

  12. Method and apparatus for steam mixing a nuclear fueled electricity generation system

    DOE Patents [OSTI]

    Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

    1996-01-01T23:59:59.000Z

    A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

  13. Method and apparatus for improving the performance of a nuclear power electrical generation system

    DOE Patents [OSTI]

    Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

    1995-01-01T23:59:59.000Z

    A method and apparatus for improving the efficiency and performance a of nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs.

  14. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    SciTech Connect (OSTI)

    L.E. Demick

    2011-10-01T23:59:59.000Z

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  15. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01T23:59:59.000Z

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

  16. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    None

    2005-01-01T23:59:59.000Z

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  17. Assessment of next generation nuclear plant intermediate heat exchanger design.

    SciTech Connect (OSTI)

    Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

    2008-10-17T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on shell and straight tube and printed circuit heat exchangers.

  18. Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

    SciTech Connect (OSTI)

    Abbott, L [ed.

    1985-09-01T23:59:59.000Z

    An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures.

  19. Threatened and endangered species evaluation for 75 licensed commercial nuclear power generating plants

    SciTech Connect (OSTI)

    Sackschewsky, M.R.

    1997-03-01T23:59:59.000Z

    The Endangered Species Act (ESA) of 1973, as amended, and related implementing regulations of the jurisdictional federal agencies, the U.S. Departments of Commerce and Interior, at 50 CFR Part 17. 1, et seq., require that federal agencies ensure that any action authorized, funded, or carried out under their jurisdiction is not likely to jeopardize the continued existence of any threatened or endangered species or result in the destruction or adverse modification of critical habitats for such species. The issuance and maintenance of a federal license, such as a construction permit or operating license issued by the U.S. Nuclear Regulatory Commission (NRC) for a commercial nuclear power generating facility is a federal action under the jurisdiction of a federal agency, and is therefore subject to the provisions of the ESA. The U.S. Department of the Interior (through the Fish and Wildlife Service), and the U.S. Department of Commerce, share responsibility for administration of the ESA. The National Marine Fisheries Service (NMFS) deals with species that inhabit marine environments and anadromous fish, while the U.S. Fish and Wildlife Service (USFWS) is responsible for terrestrial and freshwater species and migratory birds. A species (or other distinct taxonomic unit such as subspecies, variety, and for vertebrates, distinct population units) may be classified for protection as `endangered` when it is in danger of extinction within the foreseeable future throughout all or a significant portion of its range. A `threatened` classification is provided to those animals and plants likely to become endangered within the foreseeable future throughout all or a significant portion of their ranges. As of February 1997, there were about 1067 species listed under the ESA in the United States. Additionally there were approximately 125 species currently proposed for listing as threatened or endangered, and another 183 species considered to be candidates for formal listing proposals.

  20. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2007-01-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  1. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  2. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  3. Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress

    E-Print Network [OSTI]

    Rycroft, Chris H.

    Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress Chris H. Keywords: granular flow, dust generation, numerical methods 1. Introduction Pebble-bed nuclear reactors prototypes of pebble-bed reactors, significant quantities of graphite dust have been observed due to rubbing

  4. United States -Japan Joint Nuclear Energy Action Plan

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group current C3E AmbassadorsUS-EU-Japan-Japan Joint Nuclear Energy Action Plan

  5. United States -Japan Joint Nuclear Energy Action Plan | Department of

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group current C3E AmbassadorsUS-EU-Japan-Japan Joint Nuclear Energy Action

  6. United States and Italy Sign Nuclear Energy Agreements | Department of

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group current C3E AmbassadorsUS-EU-Japan-Japan JointGreen7/053/03Nuclear Damage

  7. National Nuclear Security Administration United States Department of Energy

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica Treaty Organization NCT Nuclear Counterterrorism

  8. National Nuclear Security Administration United States Department of Energy

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica Treaty Organization NCT Nuclear

  9. UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20556

    Office of Scientific and Technical Information (OSTI)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem Not FoundInformation DOEInformation Summary Big*Thee n0738F 241.3NUCLEAR

  10. Nuclear Navy United States Atomic Energy Commission Historical Advisory

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOilNEWResponse to Time-Based Rates from theLiability Nuclear Liability

  11. D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California.

    E-Print Network [OSTI]

    a cure-all, nuclear energy must have an important role in reducing the use of fossil fuels in the United--especiallywhenoneconsidersthatmanyofthetruecosts are obscured by government subsidies. Fortunately there are plenty of workable alternatives with low

  12. New York Nuclear Profile - Nine Mile Point Nuclear Station

    U.S. Energy Information Administration (EIA) Indexed Site

    Nine Mile Point Nuclear Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  13. Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant

    U.S. Energy Information Administration (EIA) Indexed Site

    Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

  14. New York Nuclear Profile - R E Ginna Nuclear Power Plant

    U.S. Energy Information Administration (EIA) Indexed Site

    R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License...

  15. Pseudo-random number generators for Monte Carlo simulations on Graphics Processing Units

    E-Print Network [OSTI]

    Vadim Demchik

    2010-03-09T23:59:59.000Z

    Basic uniform pseudo-random number generators are implemented on ATI Graphics Processing Units (GPU). The performance results of the realized generators (multiplicative linear congruential (GGL), XOR-shift (XOR128), RANECU, RANMAR, RANLUX and Mersenne Twister (MT19937)) on CPU and GPU are discussed. The obtained speed-up factor is hundreds of times in comparison with CPU. RANLUX generator is found to be the most appropriate for using on GPU in Monte Carlo simulations. The brief review of the pseudo-random number generators used in modern software packages for Monte Carlo simulations in high-energy physics is present.

  16. Databases and tools for nuclear astrophysics applications BRUSsels Nuclear LIBrary (BRUSLIB), Nuclear Astrophysics Compilation of REactions II (NACRE II) and Nuclear NETwork GENerator (NETGEN)

    E-Print Network [OSTI]

    Yi Xu; Stephane Goriely; Alain Jorissen; Guangling Chen; Marcel Arnould

    2012-12-04T23:59:59.000Z

    An update of a previous description of the BRUSLIB+NACRE package of nuclear data for astrophysics and of the web-based nuclear network generator NETGEN is presented. The new version of BRUSLIB contains the latest predictions of a wide variety of nuclear data based on the most recent version of the Brussels-Montreal Skyrme-HFB model. The nuclear masses, radii, spin/parities, deformations, single-particle schemes, matter densities, nuclear level densities, E1 strength functions, fission properties, and partition functions are provided for all nuclei lying between the proton and neutron drip lines over the 8reliability, and feasibility. In addition, these various ingredients are used to calculate about 100000 Hauser-Feshbach n-, p-, a-, and gamma-induced reaction rates based on the reaction code TALYS. NACRE is superseded by the NACRE II compilation for 15 charged-particle transfer reactions and 19 charged-particle radiative captures on stable targets with mass numbers A electronically at http://www.astro.ulb.ac.be/NuclearData. The nuclear material is presented in an extended tabular form complemented with a variety of graphical interfaces.

  17. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    P. E. MacDonald

    2005-01-01T23:59:59.000Z

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  18. United States, Russia Sign Agreement to Further Research and Development Collaboration in Nuclear Energy and Security

    Broader source: Energy.gov [DOE]

    U.S. Secretary of Energy Ernest Moniz and Director General of the Russian Federation State Corporation ďRosatomĒ Sergey Kirienko today signed the Agreement between the Government of the United States of America and the Government of the Russian Federation on Cooperation in Nuclear- and Energy-Related Scientific Research and Development

  19. Experience with Control Systems Modernization on Operating Nuclear Units (Kozloduy NPP VVER 1000)

    SciTech Connect (OSTI)

    Naydenov, Nayden [Kozloduy NPP (Bulgaria); Sechensky, Boyan [Westinghouse Energy Systems (Bulgaria)

    2006-07-01T23:59:59.000Z

    The paper describes the background, current implementation approach, design and testing strategy and experience on the largest ever modernization program for replacement of the Primary and Secondary Control Systems on operating units VVER 1000 (PWR) at Kozloduy Nuclear Power Plant in Bulgaria. (authors)

  20. Geothermal energy in the western United States and Hawaii: Resources and projected electricity generation supplies. [Contains glossary and address list of geothermal project developers and owners

    SciTech Connect (OSTI)

    Not Available

    1991-09-01T23:59:59.000Z

    Geothermal energy comes from the internal heat of the Earth, and has been continuously exploited for the production of electricity in the United States since 1960. Currently, geothermal power is one of the ready-to-use baseload electricity generating technologies that is competing in the western United States with fossil fuel, nuclear and hydroelectric generation technologies to provide utilities and their customers with a reliable and economic source of electric power. Furthermore, the development of domestic geothermal resources, as an alternative to fossil fuel combustion technologies, has a number of associated environmental benefits. This report serves two functions. First, it provides a description of geothermal technology and a progress report on the commercial status of geothermal electric power generation. Second, it addresses the question of how much electricity might be competitively produced from the geothermal resource base. 19 figs., 15 tabs.

  1. Air Pollution Control Regulations: No. 13- Particulate Emissions from Fossil Fuel Fired Steam or Hot Water Generating Units (Rhode Island)

    Broader source: Energy.gov [DOE]

    The purpose of this regulation is to limit emissions of particulate matter from fossil fuel fired and wood-fired steam or hot water generating units.

  2. Membranes for H2 generation from nuclear powered thermochemical cycles.

    SciTech Connect (OSTI)

    Nenoff, Tina Maria; Ambrosini, Andrea; Garino, Terry J.; Gelbard, Fred; Leung, Kevin; Navrotsky, Alexandra (University of California, Davis, CA); Iyer, Ratnasabapathy G. (University of California, Davis, CA); Axness, Marlene

    2006-11-01T23:59:59.000Z

    In an effort to produce hydrogen without the unwanted greenhouse gas byproducts, high-temperature thermochemical cycles driven by heat from solar energy or next-generation nuclear power plants are being explored. The process being developed is the thermochemical production of Hydrogen. The Sulfur-Iodide (SI) cycle was deemed to be one of the most promising cycles to explore. The first step of the SI cycle involves the decomposition of H{sub 2}SO{sub 4} into O{sub 2}, SO{sub 2}, and H{sub 2}O at temperatures around 850 C. In-situ removal of O{sub 2} from this reaction pushes the equilibrium towards dissociation, thus increasing the overall efficiency of the decomposition reaction. A membrane is required for this oxygen separation step that is capable of withstanding the high temperatures and corrosive conditions inherent in this process. Mixed ionic-electronic perovskites and perovskite-related structures are potential materials for oxygen separation membranes owing to their robustness, ability to form dense ceramics, capacity to stabilize oxygen nonstoichiometry, and mixed ionic/electronic conductivity. Two oxide families with promising results were studied: the double-substituted perovskite A{sub x}Sr{sub 1-x}Co{sub 1-y}B{sub y}O{sub 3-{delta}} (A=La, Y; B=Cr-Ni), in particular the family La{sub x}Sr{sub 1-x}Co{sub 1-y}Mn{sub y}O{sub 3-{delta}} (LSCM), and doped La{sub 2}Ni{sub 1-x}M{sub x}O{sub 4} (M = Cu, Zn). Materials and membranes were synthesized by solid state methods and characterized by X-ray and neutron diffraction, SEM, thermal analyses, calorimetry and conductivity. Furthermore, we were able to leverage our program with a DOE/NE sponsored H{sub 2}SO{sub 4} decomposition reactor study (at Sandia), in which our membranes were tested in the actual H{sub 2}SO{sub 4} decomposition step.

  3. Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan

    SciTech Connect (OSTI)

    J. K. Wright

    2010-09-01T23:59:59.000Z

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900įC and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Todayís high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760įC. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  4. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    SciTech Connect (OSTI)

    John Collins

    2009-01-01T23:59:59.000Z

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  5. Vermont Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    mwh)","Share of State nuclear net generation (percent)","Owner" "Vermont Yankee Unit 1",620,"4,782",100.0,"Entergy Nuclear Vermont Yankee" "1 Plant 1 Reactor",620,"4,782",100.0...

  6. Massachusetts Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    (percent)","Owner" "Pilgrim Nuclear Power Station Unit 1",685,"5,918",100.0,"Entergy Nuclear Generation Co" "1 Plant 1 Reactor",685,"5,918",100.0 "Note: Totals may not equal...

  7. Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

    2004-06-01T23:59:59.000Z

    This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

  8. Paving the path for next-generation nuclear energy | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    heat that could be used for industrial processes such as seawater desalination or plastics production. Today, China has begun construction of a prototype Generation-IV reactor,...

  9. Nuclear winter: smoke generation, deposition, and removal. Final report

    SciTech Connect (OSTI)

    Not Available

    1984-12-01T23:59:59.000Z

    The Nuclear Winter scenario predicts a major worldwide cooling arising from the large quantities of soot deposited in the atmosphere from fires ignited by the explosions in a large nuclear exchange. This document reviews the source function for smoke associated with urban and forest fires, addressing the smoke composition and predicted smoke cloud rise height. The interaction of the smoke cloud with the atmosphere is complex and depends on weather conditions. Results from past forest fires demonstrate what can actually happen to smoke clouds.

  10. Seismic risk assessment as applied to the Zion Nuclear Generating Station

    SciTech Connect (OSTI)

    Wells, J.

    1984-08-01T23:59:59.000Z

    To assist the US Nuclear Regulatory Commission (NRC) in its licensing and evaluation role, the NRC funded the Seismic Safety Margins Research Program (SSMRP) at Lawrence Livermore National Laboratory (LLNL) with the goal of developing tools and data bases to evaluate the risk of earthquake caused radioactive release from a commercial nuclear power plant. This paper describes the SSMRP risk assessment methodology and the results generated by applying this methodology to the Zion Nuclear Generating Station. In addition to describing the failure probabilities and risk values, the effects of assumptions about plant configuration, plant operation, and dependence will be given.

  11. Single-bridge unit-connected HVDC generation with increased pulse number

    SciTech Connect (OSTI)

    Villablanca, M.; Arrillaga, J. (Univ. of Canterbury, Christchurch (New Zealand))

    1993-04-01T23:59:59.000Z

    A true unit-connected generator-HVdc convertor scheme is proposed which removes the need to use two bridges in series to achieve twelve-pulse operation. Moreover, the combination of a single main bridge and an auxiliary feedback dc ripple reinjection bridge is shown to increase the pulse number from 6 to 18. This is achieved purely by natural commutation and is equally valid for rectification and inversion. The theoretical waveforms are validated by extensive experimental verification.

  12. Interim Project Results: United Parcel Service's Second-Generation Hybrid-Electric Delivery Vans (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-01-01T23:59:59.000Z

    This fact sheet describes the performance evaluation of United Parcel Service's second-generation hybrid-electric delivery vans. The Fleet Test and Evaluation Team at the National Renewable Energy Laboratory (NREL) is evaluating the 18-month, in-service performance of 11 of these vans along with 11 comparable conventional diesel vans operating in Minneapolis, Minnesota. As a complement to the field study, the team recently completed fuel economy and emissions testing at NREL's Renewable Fuels and Lubricants (ReFUEL) laboratory.

  13. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    SciTech Connect (OSTI)

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee [Korea Atomic Energy Research Institute, Deokjin-dong 150, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  14. Utilizing a Russian space nuclear reactor for a United States space mission: Systems integration issues

    SciTech Connect (OSTI)

    Reynolds, E.; Schaefer, E. [Johns Hopkins Univ., Laurel, MD (United States). Applied Physics Lab.; Polansky, G.; Lacy, J. [Phillips Lab., Albuquerque, NM (United States); Bocharov, A. [GDBMB, St. Petersburg (Russian Federation)

    1993-09-30T23:59:59.000Z

    The Nuclear Electric Propulsion Space Test Program (NEPSTP) has developed a cooperative relationship with several institutes of the former Soviet Union to evaluate Russian space hardware on a US spacecraft One component is the Topaz II Nuclear Power System; a built and flight qualified nuclear reactor that has yet to be tested in space. The access to the Topaz II reactor provides the NEPSTP with a rare opportunity; to conduct an early flight demonstration of nuclear electric propulsion at a relatively low cost. This opportunity, however, is not without challenges. Topaz II was designed to be compatible with Russian spacecraft and launch vehicles. It was manufactured and flight qualified by Russian techniques and standards and conforms to safety requirements of the former Soviet Union, not the United States. As it is desired to make minimal modifications to the Topaz II, integrating the reactor system with a United States spacecraft and launch vehicle presents an engineering challenge. This paper documents the lessons teamed regarding the integration of reactor based spacecraft and also some insight about integrating Russian hardware. It examines the planned integration flow along with specific reactor requirements that affect the spacecraft integration including American-Russian space system compatibility.

  15. 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation

    E-Print Network [OSTI]

    Search 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation to employ nuclear fusion technologies in power generation by 2050. China will adopt a three-step strategy with thermonuclear reactors; the second step aims to raise the utilization rate of nuclear fuels from the current 1

  16. Relevance of Generation Interconnection Procedures to Feed-in Tariffs in the United States

    SciTech Connect (OSTI)

    Fink, S.; Porter, K.; Rogers, J.

    2010-10-01T23:59:59.000Z

    Feed-in tariffs (FITs) have been used to promote renewable electricity development in over 40 countries throughout the past two decades. These policies generally provide guaranteed prices for the full system output from eligible generators for a fixed time period (typically 15-20 years). Due in part to the success of FIT policies in Europe, some jurisdictions in the United States are considering implementing similar policies, and a few have already put such policies in place. This report is intended to offer some guidance to policymakers and regulators on how generator interconnection procedures may affect the implementation of FITs and how state generator interconnection procedures can be formulated to support state renewable energy objectives. This report is based on a literature review of model interconnection procedures formulated by several organizations, as well as other documents that have reviewed, commented on, and in some cases, ranked state interconnection procedures.

  17. Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-05-01T23:59:59.000Z

    The United States Department of Energyís Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energyís lead laboratory for nuclear energy development. The ATR is one of the worldís premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

  18. Present and future nuclear power generation as a reflection of individual countries' resources and objectives

    SciTech Connect (OSTI)

    Borg, I.Y.

    1987-06-26T23:59:59.000Z

    The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option. The nuclear installations and future plans are reviewed on a country-by-country basis for 36 countries in the light of the resources and objectives of each. Because oil and gas for power production throughout the world are being phased out as much as possible, coal-fired generation currently tends to be the chosen alternative to nuclear power production. Exceptions occur in many of the less developed countries that collectively have a very limited operating experience with nuclear reactors. The Chernobyl accident in the USSR alarmed the public; however, national strategies and plans to build reactors have not changed markedly in the interim. Assuming that the next decade of nuclear power generation is uneventful, additional electrical demand would cause the nuclear power industry to experience a rejuvenation in Europe as well as in the US. 80 refs., 3 figs., 22 tabs.

  19. Potential growth of nuclear and coal electricity generation in the US

    SciTech Connect (OSTI)

    Bloomster, C.H.; Merrill, E.T.

    1989-08-01T23:59:59.000Z

    Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs.

  20. Raytheon explores thorium for next generation nuclear reactor

    SciTech Connect (OSTI)

    Crawford, M.

    1994-03-08T23:59:59.000Z

    Few new orders for nuclear power plants have been placed anywhere in the world in the last 20 years, but that is not discouraging Raytheon Engineers Constructors from making plans to explore new light water reactor technologies for commercial markets. The Lexington, Mass.-based company, which has extensive experience in nuclear power engineering and construction, has a vision for the light water reactor of the future - one that is based on the use of thorium-232, an element that decays over several steps to uranium-233. The use of thorium and a small amount of uranium that is 20 percent enriched is seen as providing operational, environmental, and safety advantages over reactors using the standard fuel mixture of uranium-238 and enriched uranium-235. According to Raytheon, the system could improve the economics of some reactors' operations by reducing fuel costs and lowering related waste volumes. At the same time, reactor safety could be improved by simpler control rod systems and the absence from reactor coolant of corrosive boric acid, which is used to slow neutrons in order to enhance reactions. Using thorium is also attractive because more of the fuel is burned up by the reactor, an estimated 12 percent as compared to about 4 percent for U-235. However, the technology's greatest attraction may well be its implications for nuclear proliferation. Growing plutonium inventories embedded in spent fuel rods from light water reactors have sparked concern worldwide. But according to Raytheon, using a thorium-based fuel core would alleviate this concern because it would produce only small quantities of plutonium. A thorium-based fuel system would produce 12 kilograms of plutonium over a decade versus 2,235 kilograms for an equivalent reactor operating with conventional uranium fuel.

  1. Missouri Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Callaway Unit 1","1,190","8,996",100.0,"Union...

  2. Mississippi Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Grand Gulf Unit 1","1,251","9,643",100.0,"Syste...

  3. Meeting the Next Generation of Nuclear Nonproliferation Specialists |

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.govSecurityMaintaining the StockpileNational Nuclear Security

  4. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR. GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  5. CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, jA.V.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  6. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

    SciTech Connect (OSTI)

    Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

    2007-03-21T23:59:59.000Z

    In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

  7. Historical Perspective on the United States Fusion Program Invited paper presented at American Nuclear Society 16th

    E-Print Network [OSTI]

    controlled thermonuclear reactions, or nuclear fusion as it is now more commonly called, has remained elusiveHistorical Perspective on the United States Fusion Program Invited paper presented at American Nuclear Society 16th Topical Meeting on the Technology of Fusion Energy 14-16 September, 2004 in Madison

  8. Impacts of a nuclear war in South Asia on soybean and maize production in the Midwest United States

    E-Print Network [OSTI]

    Robock, Alan

    Impacts of a nuclear war in South Asia on soybean and maize production in the Midwest United States conditions from war-related smoke. We combined observed climate conditions for the states of Iowa, Illinois phases also had an important effect. 1 Introduction In the event of nuclear war, targets in cities

  9. Impacts of a nuclear war in South Asia on soybean and maize production in the Midwest United States

    E-Print Network [OSTI]

    Robock, Alan

    Impacts of a nuclear war in South Asia on soybean and maize production in the Midwest United States and soybeans to cooler, drier, and darker conditions from war-related smoke. We combined observed climate had an important effect. 1 Introduction In the event of nuclear war, targets in cities and industrial

  10. Developing a tool to estimate water withdrawal and consumption in electricity generation in the United States.

    SciTech Connect (OSTI)

    Wu, M.; Peng, J. (Energy Systems); ( NE)

    2011-02-24T23:59:59.000Z

    Freshwater consumption for electricity generation is projected to increase dramatically in the next couple of decades in the United States. The increased demand is likely to further strain freshwater resources in regions where water has already become scarce. Meanwhile, the automotive industry has stepped up its research, development, and deployment efforts on electric vehicles (EVs) and plug-in hybrid electric vehicles (PHEVs). Large-scale, escalated production of EVs and PHEVs nationwide would require increased electricity production, and so meeting the water demand becomes an even greater challenge. The goal of this study is to provide a baseline assessment of freshwater use in electricity generation in the United States and at the state level. Freshwater withdrawal and consumption requirements for power generated from fossil, nonfossil, and renewable sources via various technologies and by use of different cooling systems are examined. A data inventory has been developed that compiles data from government statistics, reports, and literature issued by major research institutes. A spreadsheet-based model has been developed to conduct the estimates by means of a transparent and interactive process. The model further allows us to project future water withdrawal and consumption in electricity production under the forecasted increases in demand. This tool is intended to provide decision makers with the means to make a quick comparison among various fuel, technology, and cooling system options. The model output can be used to address water resource sustainability when considering new projects or expansion of existing plants.

  11. Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

    DOE Patents [OSTI]

    Bowman, Charles D. (Los Alamos, NM)

    1992-01-01T23:59:59.000Z

    Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

  12. Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

    DOE Patents [OSTI]

    Bowman, C.D.

    1992-11-03T23:59:59.000Z

    Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

  13. Project Overview: United Parcel Service's Second-Generation Hybrid-Electric Delivery Vans (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-11-01T23:59:59.000Z

    This fact sheet describes UPS second generation hybrid-electric delivery vehicles as compared to conventional delivery vehicles. Medium-duty commercial vehicles such as moving trucks, beverage-delivery trucks, and package-delivery vans consume almost 2,000 gal of fuel per year on average. United Parcel Service (UPS) operates hybrid-electric package-delivery vans to reduce the fuel use and emissions of its fleet. In 2008, the National Renewable Energy Laboratory's (NREL's) Fleet Test and Evaluation Team evaluated the first generation of UPS' hybrid delivery vans. These hybrid vans demonstrated 29%-37% higher fuel economy than comparable conventional diesel vans, which contributed to UPS' decision to add second-generation hybrid vans to its fleet. The Fleet Test and Evaluation Team is now evaluating the 18-month, in-service performance of 11 second-generation hybrid vans and 11 comparable conventional diesel vans operated by UPS in Minneapolis, Minnesota. The evaluation also includes testing fuel economy and emissions at NREL's Renewable Fuels and Lubricants (ReFUEL) Laboratory and comparing diesel particulate filter (DPF) regeneration. In addition, a followup evaluation of UPS' first-generation hybrid vans will show how those vehicles performed over three years of operation. One goal of this project is to provide a consistent comparison of fuel economy and operating costs between the second-generation hybrid vans and comparable conventional vans. Additional goals include quantifying the effects of hybridization on DPF regeneration and helping UPS select delivery routes for its hybrid vans that maximize the benefits of hybrid technology. This document introduces the UPS second-generation hybrid evaluation project. Final results will be available in mid-2012.

  14. Preservation and Implementation of Decommissioning Lessons Learned in the United States Nuclear Regulatory Commission

    SciTech Connect (OSTI)

    Rodriguez, Rafael L. [United States Nuclear Regulatory Commission, Office of Federal and State Materials and Environmental Management Programs, Washington, DC 20555 (United States)

    2008-01-15T23:59:59.000Z

    Over the past several years, the United States Nuclear Regulatory Commission (NRC) has actively worked to capture and preserve lessons learned from the decommissioning of nuclear facilities. More recently, NRC has involved industry groups, the Organization of Agreement States (OAS), and the Department of Energy (DOE) in the effort to develop approaches to capture, preserve and disseminate decommissioning lessons learned. This paper discusses the accomplishments of the working group, some lessons learned by the NRC in the recent past, and how NRC will incorporate these lessons learned into its regulatory framework. This should help ensure that the design and operation of current and future nuclear facilities will result in less environmental impact and more efficient decommissioning. In summary, the NRC will continue capturing today's experience in decommissioning so that future facilities can take advantage of lessons learned from today's decommissioning projects. NRC, both individually and collectively with industry groups, OAS, and DOE, is aggressively working on the preservation and implementation of decommissioning lessons learned. The joint effort has helped to ensure the lessons from the whole spectrum of decommissioning facilities (i.e., reactor, fuel cycle, and material facilities) are better understood, thus maximizing the amount of knowledge and best practices obtained from decommissioning activities. Anticipated regulatory activities at the NRC will make sure that the knowledge gained from today's decommissioning projects is preserved and implemented to benefit the nuclear facilities that will decommission in the future.

  15. Low-NO{sub x} combustion chamber for a power generation gas-turbine unit

    SciTech Connect (OSTI)

    Gutnik, M.N.; Tumanovsky, A.G.; Soudarev, A.V.; Vinogradov, E.D.; Zakharov, Y.I.; Lobanov, D.V.; Akulov, V.A.

    1998-07-01T23:59:59.000Z

    The findings of the experimental studies over major operating characteristics of a full-scale combustion chamber (CC) for a new power generation 25 MW gas turbine unit of the AO ``Turbomotorny Zavod'' (Ekaterinburg) production are presented. A technique of the pre-mixed lean combustion with the excess air coefficient being approximately equal to 1.9--2.2 underlies the low NO{sub x} combustor design. Interrelations between the major combustor characteristics and design and duty parameters in parallel with the optimum algorithm of the combustor loading ensuring the minimum toxic exhausts into atmosphere are also shown in the paper.

  16. Illinois Nuclear Profile - LaSalle Generating Station

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5 Tables July 1996 Energy Information Administration Office of Coal,Cubic Feet) Decade Year-0Elements)GasByronLaSalle Generating

  17. Acoustic emission monitoring of hot functional testing: Watts Bar Unit 1 Nuclear Reactor

    SciTech Connect (OSTI)

    Hutton, P.H.; Dawson, J.F.; Friesel, M.A.; Harris, J.C.; Pappas, R.A.

    1984-06-01T23:59:59.000Z

    Acoustic emission (AE) monitoring of selected pressure boundary areas at TVA's Watts Bar, Unit 1 Nuclear Power Plant during hot functional preservice testing is described in this report. The report deals with background, methodology, and results. The work discussed here is a major milestone in a program supported by NRC to develop and demonstrate application of AE monitoring for continuous surveillance of reactor pressure boundaries to detect and evaluate growing flaws. The subject work demonstrated that anticipated problem areas can be overcome. Work is continuing toward AE monitoring during reactor operation.

  18. DOE - Office of Legacy Management -- United Nuclear Corp - MO 0-03

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling Corp -K LeDowntownUnited Nuclear Corp - MO 0-03

  19. The effects of technological change, experience and environmental regulation on the construction of coal-burning generating units

    E-Print Network [OSTI]

    Joskow, Paul L.

    1984-01-01T23:59:59.000Z

    This paper provides an empirical analysis of the technological, regulatory and organizational factors that have influenced the costs of building coal-burning steam-electric generating units over the past twenty year. We ...

  20. EIS-0092: Conversion to Coal, Holyoke Water Power Company, Mt. Tom Generating Station Unit 1 Holyoke, Hampden County, Massachusetts

    Broader source: Energy.gov [DOE]

    The Economic Regulatory Administration prepared this statement to assess the environmental impacts of prohibiting Unit 1 of the Mt. Tom Generation Station Unit 1 from using either natural gas or petroleum products as a primary energy source, which would result in the utility burning low-sulfur coal.

  1. Qualification of Class 1E static battery charges and inverters for nuclear power generating stations

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    This standard describes methods for qualifying static battery chargers and inverters for Class 1E installations in environmentally controlled areas outside containment in nuclear power generating stations. The purpose of this standard is to provide specific procedures to meet the requirements of IEEE Std. 323-1974.

  2. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper

    SciTech Connect (OSTI)

    Pete Jordan

    2010-09-01T23:59:59.000Z

    This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

  3. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

  4. 1 hour, 59 minutes ago President Jacques Chirac announced plans to build a prototype fourth-generation nuclear reactor by 2020 as well as symbolic targets

    E-Print Network [OSTI]

    -generation nuclear reactor by 2020 as well as symbolic targets for cutting France's reliance on oil in the coming and is conducting research into several new models of nuclear reactor. Business leaders in the French energy sector-generation nuclear reactor 1/5/06 3:19 PMPrint Story: France to develop fourth-generation nuclear reactor on Yahoo

  5. Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors

    E-Print Network [OSTI]

    J. Marvin Herndon

    2007-09-27T23:59:59.000Z

    One of the most fundamental problems in physics has been to understand the nature of the mechanism that generates the geomagnetic field and the magnetic fields of other planets and satellites. For decades, the dynamo mechanism, thought to be responsible for generating the geomagnetic field and other planetary magnetic fields, has been ascribed to convection in each planet's iron-alloy core. Recently, I described the problems inherent in Earth-core convection and proposed instead that the geomagnetic field is produced by a dynamo mechanism involving convection, not in the fluid core, but in the electrically conductive, fluid, fission-product sub-shell of a natural nuclear fission reactor at the center of the Earth, called the georeactor. Here I set forth in detail the commonality in the Solar System of the matter like that of the inside of the Earth, which is my basis for generalizing the concept of planetary magnetic field generation by natural planetocentric nuclear fission reactors.

  6. A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats

    SciTech Connect (OSTI)

    Nelson, K; Sokkappa, P

    2008-10-29T23:59:59.000Z

    This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

  7. A practical design for an integrated HVDC unit - connected hydro-electric generating station

    SciTech Connect (OSTI)

    Ingram, L. (Manitoba HVDC Research Centre, Winnipeg (CA))

    1988-10-01T23:59:59.000Z

    To date, several authors (see reference list) have proclaimed benefits which can be achieved by integrating HVDC converter stations directly with generating units. The cost of a significant amount of plant and facilities found in conventional schemes is thereby eliminated. So far as is known however, no detailed studies have been done to quantify these benefits. This paper outlines the results of a study made recently by the Manitoba HVDC Research Centre to determine the practicality of such a scheme. To give credence to the results an actual hydro station design was used incorporating a HVDC thyristor valve scheme in a hypothetical situation. Financial and other benefits were determined for this example together with conclusions and recommendations for future specific projects and further areas of study.

  8. Technical cooperation on nuclear security between the United States and China : review of the past and opportunities for the future.

    SciTech Connect (OSTI)

    Pregenzer, Arian Leigh

    2011-12-01T23:59:59.000Z

    The United States and China are committed to cooperation to address the challenges of the next century. Technical cooperation, building on a long tradition of technical exchange between the two countries, can play an important role. This paper focuses on technical cooperation between the United States and China in the areas of nonproliferation, arms control and other nuclear security topics. It reviews cooperation during the 1990s on nonproliferation and arms control under the U.S.-China Arms Control Exchange, discusses examples of ongoing activities under the Peaceful Uses of Technology Agreement to enhance security of nuclear and radiological material, and suggests opportunities for expanding technical cooperation between the defense nuclear laboratories of both countries to address a broader range of nuclear security topics.

  9. Generation IV Nuclear Energy Systems Construction Cost Reductions Through the Use of Virtual Environments

    SciTech Connect (OSTI)

    Timothy Shaw; Vaugh Whisker

    2004-02-28T23:59:59.000Z

    The objective of this multi-phase project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. The project will test the suitability of immersive virtual reality technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups. This report presents the results of the completed project.

  10. Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants

    SciTech Connect (OSTI)

    Woo, H.H.; Lu, S.C.

    1981-09-15T23:59:59.000Z

    Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

  11. New Hampshire Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    total reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Seabrook Unit 1","1,247","10,910",100.0,"NextEr...

  12. Unit operations used to treat process and/or waste streams at nuclear power plants. [R

    SciTech Connect (OSTI)

    Godbee, H.W.; Kibbey, A.H.

    1980-01-01T23:59:59.000Z

    Estimates are given of the annual amounts of each generic type of LLW (i.e., Government and commerical (fuel cycle and non-fuel cycle)) that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials (liquids (e.g., oils or solvents) and/or solids), could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends.

  13. PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Koenig, R.; Davies, S.

    2009-06-01T23:59:59.000Z

    Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

  14. Compressor and Turbine Models of Brayton Units for Space Nuclear Power Systems

    SciTech Connect (OSTI)

    Gallo, Bruno M.; El-Genk, Mohamed S.; Tournier, Jean-Michel [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM, 87131 (United States); Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM, 87131 (United States)

    2007-01-30T23:59:59.000Z

    Closed Brayton Cycles with centrifugal flow, single-shaft turbo-machines are being considered, with gas cooled nuclear reactors, to provide 10's to 100's of electrical power to support future space exploration missions and Lunar and Mars outposts. Such power system analysis is typically based on the cycle thermodynamics, for given operating pressures and temperatures and assumed polytropic efficiencies of the compressor and turbine of the Brayton energy conversion units. Thus the analysis results not suitable for modeling operation transients such as startup and changes in the electric load. To simulate these transients, accurate models of the turbine and compressor in the Brayton rotating unit, which calculate the changes in the compressor and turbine efficiencies with system operation are needed. This paper presents flow models that account for the design and dimensions of the compressor impeller and diffuser, and the turbine stator and rotor blades. These models calculate the various enthalpy losses and the polytropic efficiencies along with the pressure ratios of the turbine and compressor. The predictions of these models compare well with reported performance data of actual hardware. In addition, the results of a parametric analysis to map the operations of the compressor and turbine, as functions of the rotating shaft speed and inlet Mach number of the gas working fluid, are presented and discussed. The analysis used a binary mixture of He-Xe with a molecular weight of 40 g/mole as the working fluid.

  15. Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report

    SciTech Connect (OSTI)

    Timothy Shaw; Anthony Baratta; Vaughn Whisker

    2005-02-28T23:59:59.000Z

    Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models.

  16. Proposed changes to generating capacity 1980-1989 for the contiguous United States: as projected by the Regional Electric Reliability Councils in their April 1, 1980 long-range coordinated planning reports to the Department of Energy

    SciTech Connect (OSTI)

    None

    1980-12-01T23:59:59.000Z

    The changes in generating capacity projected for 1980 to 1989 are summarized. Tabulated data provide summaries to the information on projected generating unit construction, retirements, and changes, in several different categories and groupings. The new generating units to be completed by the end of 1989 total 699, representing 259,490 megawatts. This total includes 10 wind power and one fuel cell installations totaling 48.5 MW to be completed by the end of 1989. There are 321 units totaling 13,222 MW to be retired. There are capacity changes due to upratings and deratings. Summary data are presented for: total requirement for electric energy generation for 1985; hydroelectric energy production for 1985; nuclear energy production for 1985; geothermal and other energy production for 1985; approximate non-fossil generation for 1985; range of fossil energy requirements for 1985; actual fossil energy sources 1974 to 1979; estimated range of fossil fuel requirements for 1985; coal capacity available in 1985; and computation of fuel use in 1985. Power plant capacity factors are presented. Extensive data on proposed generating capacity changes by individual units in the 9 Regional Electric Reliability Councils are presented.

  17. Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station

    SciTech Connect (OSTI)

    Wade C. Adams

    2006-10-25T23:59:59.000Z

    Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

  18. IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard.

  19. The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-09-01T23:59:59.000Z

    The United States Department of Energyís Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energyís lead laboratory for nuclear energy development. The ATR is one of the worldís premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

  20. Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis

    SciTech Connect (OSTI)

    Wells, J.E.; Lappa, D.A.; Bernreuter, D.L.; Chen, J.C.; Chuang, T.Y. [Lawrence Livermore National Lab., CA (United States); Johnson, J.J.; Campbell, R.D.; Hashimoto, P.S.; Maslenikov, O.R.; Tiong, L.W.; Ravindra, M.K.; Kincaid, R.H. [EQE, International, Irvine, CA (United States); Sues, R.H.; Putcha, C.S. [NTS Engineering, Long Beach, CA (United States)

    1993-11-01T23:59:59.000Z

    This report describes the methodology used and the results obtained from the application of a simplified seismic risk methodology to the LaSalle County Nuclear Generating Station Unit 2. This study is part of the Level I analysis being performed by the Risk Methods Integration and Evaluation Program (RMIEP). Using the RMIEP developed event and fault trees, the analysis resulted in a seismically induced core damage frequency point estimate of 6.OE-7/yr. This result, combined with the component importance analysis, indicated that system failures were dominated by random events. The dominant components included diesel generator failures (failure to swing, failure to start, failure to run after started), and condensate storage tank.

  1. Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

    SciTech Connect (OSTI)

    J. D. Bess; J. B. Briggs; A. S. Garcia

    2011-09-01T23:59:59.000Z

    One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

  2. Third Party Nuclear Liability: The Case of a Supplier in the United Kingdom

    E-Print Network [OSTI]

    Thomas, Anthony; Heffron, Raphael J.

    2012-02-27T23:59:59.000Z

    The law surrounding third party nuclear liability is important to all parties in the nuclear supply chain whether they are providing decommissioning services, project management expertise or a new reactor. This paper examines third party nuclear...

  3. Locating hot and cold-legs in a nuclear powered steam generation system

    DOE Patents [OSTI]

    Ekeroth, D.E.; Corletti, M.M.

    1993-11-16T23:59:59.000Z

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

  4. Locating hot and cold-legs in a nuclear powered steam generation system

    DOE Patents [OSTI]

    Ekeroth, Douglas E. (Delmont, PA); Corletti, Michael M. (New Kensington, PA)

    1993-01-01T23:59:59.000Z

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

  5. Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors

    SciTech Connect (OSTI)

    Simos, N.

    2011-05-01T23:59:59.000Z

    In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

  6. Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 6: Process Heat and Hydrogen Co-Generation PIRTs

    SciTech Connect (OSTI)

    Forsberg, Charles W [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL); Herring, S. [Idaho National Laboratory (INL); Pickard, P. [Sandia National Laboratories (SNL)

    2008-03-01T23:59:59.000Z

    A Phenomena Identification and Ranking Table (PIRT) exercise was conducted to identify potential safety-0-related physical phenomena for the Next Generation Nuclear Plant (NGNP) when coupled to a hydrogen production or similar chemical plant. The NGNP is a very high-temperature reactor (VHTR) with the design goal to produce high-temperature heat and electricity for nearby chemical plants. Because high-temperature heat can only be transported limited distances, the two plants will be close to each other. One of the primary applications for the VHTR would be to supply heat and electricity for the production of hydrogen. There was no assessment of chemical plant safety challenges. The primary application of this PIRT is to support the safety analysis of the NGNP coupled one or more small hydrogen production pilot plants. However, the chemical plant processes to be coupled to the NGNP have not yet been chosen; thus, a broad PIRT assessment was conducted to scope alternative potential applications and test facilities associated with the NGNP. The hazards associated with various chemicals and methods to minimize risks from those hazards are well understood within the chemical industry. Much but not all of the information required to assure safe conditions (separation distance, relative elevation, berms) is known for a reactor coupled to a chemical plant. There is also some experience with nuclear plants in several countries that have produced steam for industrial applications. The specific characteristics of the chemical plant, site layout, and the maximum stored inventories of chemicals can provide the starting point for the safety assessments. While the panel identified events and phenomena of safety significance, there is one added caveat. Multiple high-temperature reactors provide safety-related experience and understanding of reactor safety. In contrast, there have been only limited safety studies of coupled chemical and nuclear plants. The work herein provides a starting point for those studies; but, the general level of understanding of safety in coupling nuclear and chemical plants is less than in other areas of high-temperature reactor safety.

  7. Unit Commitment of Generator Sets During Dynamic Positioning Operation Based on

    E-Print Network [OSTI]

    Johansen, Tor Arne

    is large (Radan, 2008). A method for selecting the correct units must therefore be used, as testing all

  8. Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect

    SciTech Connect (OSTI)

    Xu, T.; Senger, R.; Finsterle, S.

    2008-10-15T23:59:59.000Z

    Corrosion of steel canisters, stored in a repository for spent fuel and high-level nuclear wastes, leads to the generation and accumulation of hydrogen gas in the backfilled emplacement tunnels, which may significantly affect long-term repository safety. Previous studies used H{sub 2} generation rates based on the volume of the waste or canister material and the stoichiometry of the corrosion reaction. However, iron corrosion and H{sub 2} generation rates vary with time, depending on factors such as amount of iron, water availability, water contact area, and aqueous and solid chemistry. To account for these factors and feedback mechanisms, we developed a chemistry model related to iron corrosion, coupled with two-phase (liquid and gas) flow phenomena that are driven by gas-pressure buildup associated with H{sub 2} generation and water consumption. Results indicate that by dynamically calculating H{sub 2} generation rates based on a simple model of corrosion chemistry, and by coupling this corrosion reaction with two-phase flow processes, the degree and extent of gas pressure buildup could be much smaller compared to a model that neglects the coupling between flow and reactive transport mechanisms. By considering the feedback of corrosion chemistry, the gas pressure increases initially at the canister, but later decreases and eventually returns to a stabilized pressure that is slightly higher than the background pressure. The current study focuses on corrosion under anaerobic conditions for which the coupled hydrogeochemical model was used to examine the role of selected physical parameters on the H{sub 2} gas generation and corresponding pressure buildup in a nuclear waste repository. The developed model can be applied to evaluate the effect of water and mineral chemistry of the buffer and host rock on the corrosion reaction for future site-specific studies.

  9. The maximum potential to generate wind power in the contiguous United States is more than three times

    E-Print Network [OSTI]

    The maximum potential to generate wind power in the contiguous United States is more than three) study. The new analysis is based on the latest computer models and examines the wind potential at wind responsible for the increased wind potential in the study. Developed in collaboration with renewable energy

  10. High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001

    SciTech Connect (OSTI)

    Brown, L.C.

    2002-11-01T23:59:59.000Z

    OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

  11. U.S. Job Creation Due to Nuclear Power Resurgence in The United States ó Volumes 1 and 2

    SciTech Connect (OSTI)

    Catherine M. Plowman

    2004-11-01T23:59:59.000Z

    The recent revival of interest in nuclear power is causing a reexamination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current U.S. industries to support a renewal of nuclear power plant deployment. This study was conducted to provide an initial estimate of jobs to be gained in the U.S. through the repatriation of the nuclear manufacturing industry. In the course of the study, related job categories were also modeled to provide an additional estimate of the potential expansion of existing industries (i.e., plant construction and operations) in conjunction with the repatriation of manufacturing jobs.

  12. Nuclear power plant construction activity, 1986

    SciTech Connect (OSTI)

    Not Available

    1987-07-24T23:59:59.000Z

    Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

  13. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    SciTech Connect (OSTI)

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01T23:59:59.000Z

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  14. EIS No. 20100312 EIS Comanche Peak Nuclear Power Plant Units 3 and 4

    SciTech Connect (OSTI)

    Bjornstad, David J [ORNL

    2010-08-01T23:59:59.000Z

    In accordance with Section 309(a) of the Clean Air Act, EPA is required to make its comments on EISs issued by other Federal agencies public. Historically, EPA has met this mandate by publishing weekly notices of availability of EPA comments, which includes a brief summary of EPA's comment letters, in the Federal Register. Since February 2008, EPA has been including its comment letters on EISs on its Web site at: http://www.epa.gov/compliance/nepa/eisdata.html. Including the entire EIS comment letters on the Web site satisfies the Section 309(a) requirement to make EPA's comments on EISs available to the public. Accordingly, on March 31, 2010, EPA discontinued the publication of the notice of availability of EPA comments in the Federal Register. EIS No. 20100312, Draft EIS, NRC, TX, Comanche Peak Nuclear Power Plant Units 3 and 4, Application for Combined Licenses (COLs) for Construction Permits and Operating Licenses, (NUREG-1943), Hood and Somervell Counties, TX, Comment Period Ends: 10/26/2010.

  15. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    SciTech Connect (OSTI)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle [Tish

    2012-01-31T23:59:59.000Z

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan for developing a regional CEUS SSC model. The work plan, formulated by the project manager and a

  16. Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report

    SciTech Connect (OSTI)

    Ball, Sydney J [ORNL

    2008-03-01T23:59:59.000Z

    A phenomena identification and ranking table (PIRT) process was conducted for the Next Generation Nuclear Plant (NGNP) design. This design (in the conceptual stage) is a modular high-temperature gas-cooled reactor (HTGR) that generates both electricity and process heat for hydrogen production. Expert panels identified safety-relevant phenomena, ranked their importance, and assessed the knowledge levels in the areas of accidents and thermal fluids, fission-product transport and dose, high-temperature materials, graphite, and process heat for hydrogen production. This main report summarizes and documents the process and scope of the reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings of the phenomena, plus a summary of each panel's findings, are presented. Individual panel reports for these areas are provided as attached volumes to this main report and provide considerably more detail about each panel's deliberations as well as a more complete listing of the phenomena that were evaluated.

  17. Nuclear power plant performance assessment pertaining to plant aging in France and the United States

    E-Print Network [OSTI]

    Guyer, Brittany (Brittany Leigh)

    2013-01-01T23:59:59.000Z

    The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant ...

  18. Site Selection & Characterization Status Report for Next Generation Nuclear Plant (NGNP)

    SciTech Connect (OSTI)

    Mark Holbrook

    2007-09-01T23:59:59.000Z

    In the near future, the US Department of Energy (DOE) will need to make important decisions regarding design and construction of the Next Generation Nuclear Plant (NGNP). One part of making these decisions is considering the potential environmental impacts that this facility may have, if constructed here at the Idaho National Laboratory (INL). The National Environmental Policy Act (NEPA) of 1969 provides DOE decision makers with a process to systematically consider potential environmental consequences of agency decisions. In addition, the Energy Policy Act of 2005 (Title VI, Subtitel C, Section 644) states that the 'Nuclear Regulatory Commission (NRC) shall have licensing and regulatory authority for any reactor authorized under this subtitle.' This stipulates that the NRC will license the NGNP for operation. The NRC NEPA Regulations (10 CFR Part 51) require tha thte NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power plant. The applicant is required to submit an Environmental report (ER) to aid the NRC in complying with NEPA.

  19. Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study

    SciTech Connect (OSTI)

    Timothy Shaw; Anthony Baratta; Vaughn Whisker

    2005-02-28T23:59:59.000Z

    Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning.

  20. NEXT GENERATION SOLVENT MATERIALS COMPATIBILITY WITH POLYMER COMPONENTS WITHIN MODULAR CAUSTIC-SIDE SOLVENT EXTRACTION UNIT

    SciTech Connect (OSTI)

    Fondeur, F.; Peters, T.; Fink, S.

    2011-09-29T23:59:59.000Z

    The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent for deployment at the Savannah River Site for removal of cesium from High Level Waste. The technical effort is collaboration between Oak Ridge National Laboratory (ORNL), Savannah River National Laboratory (SRNL), and Argonne National Laboratory. The first deployment target for the technology is within the Modular Caustic-Side Solvent Extraction Unit (MCU). Deployment of a new chemical within an existing facility requires verification that the chemical components are compatible with the installed equipment. In the instance of a new organic solvent, the primary focus is on compatibility of the solvent with organic polymers used in the facility. This report provides the data from exposing these polymers to the Next Generation Solvent (NGS). The test was conducted over six months. An assessment of the dimensional stability of polymers present in MCU (i.e., PEEK, Grafoil{reg_sign}, Tefzel{reg_sign} and Isolast{reg_sign}) in the modified NGS (where the concentration of the guanidine suppressor and MaxCalix was varied systematically) showed that guanidine (LIX{reg_sign}79) selectively affected Tefzel{reg_sign} (by an increase in size and lowering its density). The copolymer structure of Tefzel{reg_sign} and possibly its porosity allows for the easier diffusion of guanidine. Tefzel{reg_sign} is used as the seat material in some of the valves at MCU. Long term exposure to guanidine, may make the valves hard to operate over time due to the seat material (Tefzel{reg_sign}) increasing in size. However, since the physical changes of Tefzel{reg_sign} in the improved solvent are comparable to the changes in the CSSX baseline solvent, no design changes are needed with respect to the Tefzel{reg_sign} seating material. PEEK, Grafoil{reg_sign} and Isolast{reg_sign} were not affected by guanidine and MaxCalix within six months of exposure. The initial rapid weight gain observed in every polymer is assigned to the finite and limited uptake of Isopar{reg_sign} L/Modifier by the polymers probably due to the polymers porosity and rough surfaces. Spectroscopic data on the organic liquid and the polymer surfaces showed no preferential adsorption of any component in the NGS to the polymers and no leachate was observed in the NGS from any of the polymers studied.

  1. State Nuclear Profiles 2010

    U.S. Energy Information Administration (EIA) Indexed Site

    net generation, 2010 Wolf Creek Generating Station Unit 1 1,160 9,556 100.0 Wolf Creek Nuclear Optg Corp 1 Plant 1 Reactor 1,160 9,556 100.0 Owner Note: Totals may not equal sum...

  2. Life Cycle Greenhouse Gas Emissions of Nuclear Electricity Generation: Systematic Review and Harmonization

    SciTech Connect (OSTI)

    Warner, E. S.; Heath, G. A.

    2012-04-01T23:59:59.000Z

    A systematic review and harmonization of life cycle assessment (LCA) literature of nuclear electricity generation technologies was performed to determine causes of and, where possible, reduce variability in estimates of life cycle greenhouse gas (GHG) emissions to clarify the state of knowledge and inform decision making. LCA literature indicates that life cycle GHG emissions from nuclear power are a fraction of traditional fossil sources, but the conditions and assumptions under which nuclear power are deployed can have a significant impact on the magnitude of life cycle GHG emissions relative to renewable technologies. Screening 274 references yielded 27 that reported 99 independent estimates of life cycle GHG emissions from light water reactors (LWRs). The published median, interquartile range (IQR), and range for the pool of LWR life cycle GHG emission estimates were 13, 23, and 220 grams of carbon dioxide equivalent per kilowatt-hour (g CO{sub 2}-eq/kWh), respectively. After harmonizing methods to use consistent gross system boundaries and values for several important system parameters, the same statistics were 12, 17, and 110 g CO{sub 2}-eq/kWh, respectively. Harmonization (especially of performance characteristics) clarifies the estimation of central tendency and variability. To explain the remaining variability, several additional, highly influential consequential factors were examined using other methods. These factors included the primary source energy mix, uranium ore grade, and the selected LCA method. For example, a scenario analysis of future global nuclear development examined the effects of a decreasing global uranium market-average ore grade on life cycle GHG emissions. Depending on conditions, median life cycle GHG emissions could be 9 to 110 g CO{sub 2}-eq/kWh by 2050.

  3. Impacts of Renewable Generation on Fossil Fuel Unit Cycling: Costs and Emissions (Presentation)

    SciTech Connect (OSTI)

    Brinkman, G.; Lew, D.; Denholm, P.

    2012-09-01T23:59:59.000Z

    Prepared for the Clean Energy Regulatory Forum III, this presentation looks at the Western Wind and Solar Integration Study and reexamines the cost and emissions impacts of fossil fuel unit cycling.

  4. Autonomous Control of Inverter-Interfaced Distributed Generation Units for Harmonic Current Filtering and

    E-Print Network [OSTI]

    Chen, Zhe

    compensator consists of a virtual fundamental impedance loop for enhanced sharing of reactive power) units, and also provide a more reliable electricity service [2]. On the other hand, during the islanded

  5. Optimal Placement and Sizing of Distributed Generator Units using Genetic Optimization

    E-Print Network [OSTI]

    -scale production units (e.g. fuel cells, micro-CHPs, photovoltaic panels) and the liberalization of the energy reliability, etc. This optimization problem can be solved in different ways like exhaustive searches [14

  6. Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12:18 pm

    E-Print Network [OSTI]

    Danon, Yaron

    Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12 of nuclear reactors are designed to prevent exactly what we old Fukushima Daiichi plant. Which is good the world rush to reconsider their nuclear plans, nuclear experts look toward a future of smaller, safer

  7. Co-operation Agreement between the European Organization for Nuclear Research and the Department of Energy of the United States of America and the National Science Foundation of the United States of America concerning Scientific and Technical Co-operation in Nuclear and Particle Physics

    E-Print Network [OSTI]

    2015-01-01T23:59:59.000Z

    Co-operation Agreement between the European Organization for Nuclear Research and the Department of Energy of the United States of America and the National Science Foundation of the United States of America concerning Scientific and Technical Co-operation in Nuclear and Particle Physics

  8. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration

    E-Print Network [OSTI]

    Langerhans, Brian

    , for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL; determining rate of spread and social network for smallpox epidemic in Abakaliki, Nigeria (1972) ∑ Studying

  9. EVALUATION METHODOLOGY FOR PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION OF GENERATION IV NUCLEAR ENERGY SYSTEMS: AN OVERVIEW.

    SciTech Connect (OSTI)

    BARI, R.; ET AL.

    2006-03-01T23:59:59.000Z

    This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: (1) System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. (2) Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. (3) Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

  10. Evaluation Methodology For Proliferation Resistance And Physical Protection Of Generation IV Nuclear Energy Systems: An Overview

    SciTech Connect (OSTI)

    T. Bjornard; R. Bari; R. Nishimura; P. Peterson; J. Roglans; D. Bley; J. Cazalet; G.G.M. Cojazzi; P. Delaune; M. Golay; G. Rendad; G. Rochau; M. Senzaki; I. Therios; M. Zentner

    2006-05-01T23:59:59.000Z

    This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: 1.System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. 2.Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. 3.Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

  11. A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    IMPACTS OF FOSSIL-FUEL NUCLEAR, GEOTHERMAL, AND ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  12. POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  13. A REVIEW OF AIR QUALITY MODELING TECHNIQUES. VOLUME 8 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Rosen, L.C.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  14. Utility Integrated Resource Planning: An Emerging Driver of NewRenewable Generation in the Western United States

    SciTech Connect (OSTI)

    Bolinger, Mark; Wiser, Ryan

    2005-09-25T23:59:59.000Z

    In the United States, markets for renewable generation--especially wind power--have grown substantially in recent years. This growth is typically attributed to technology improvements and resulting cost reductions, the availability of federal tax incentives, and aggressive state policy efforts. But another less widely recognized driver of new renewable generation is poised to play a major role in the coming years: utility integrated resource planning (IRP). Common in the late-1980s to mid-1990s, but relegated to lesser importance as many states took steps to restructure their electricity markets in the late-1990s, IRP has re-emerged in recent years as an important tool for utilities and regulators, particularly in regions such as the western United States, where retail competition has failed to take root. As practiced in the United States, IRP is a formal process by which utilities analyze the costs, benefits, and risks of all resources available to them--both supply- and demand-side--with the ultimate goal of identifying a portfolio of resources that meets their future needs at lowest cost and/or risk. Though the content of any specific utility IRP is unique, all are built on a common basic framework: (1) development of peak demand and load forecasts; (2) assessment of how these forecasts compare to existing and committed generation resources; (3) identification and characterization of various resource portfolios as candidates to fill a projected resource deficiency; (4) analysis of these different ''candidate'' resource portfolios under base-case and alternative future scenarios; and finally, (5) selection of a preferred portfolio, and creation of a near-term action plan to begin to move towards that portfolio. Renewable resources were once rarely considered seriously in utility IRP. In the western United States, however, the most recent resource plans call for a significant amount of new wind power capacity. These planned additions appear to be motivated by the improved economics of wind power, an emerging understanding that wind integration costs are manageable, and a growing acceptance of wind by electric utilities. Equally important, utility IRPs are increasingly recognizing the inherent risks in fossil-based generation portfolios--especially natural gas price risk and the financial risk of future carbon regulation--and the benefits of renewable energy in mitigating those risks. This article, which is based on a longer report from Berkeley Lab,i examines how twelve investor-owned utilities (IOUs) in the western United States--Avista, Idaho Power, NorthWestern Energy (NWE), Portland General Electric (PGE), Puget Sound Energy (PSE), PacifiCorp, Public Service Company of Colorado (PSCo), Nevada Power, Sierra Pacific, Pacific Gas & Electric (PG&E), Southern California Edison (SCE), and San Diego Gas & Electric (SDG&E)--treat renewable energy in their most recent resource plans (as of July 2005). In aggregate, these twelve utilities supply approximately half of all electricity demand in the western United States. In reviewing these plans, our purpose is twofold: (1) to highlight the growing importance of utility IRP as a current and future driver of renewable generation in the United States, and (2) to suggest possible improvements to the methods used to evaluate renewable generation as a resource option. As such, we begin by summarizing the amount and types of new renewable generation planned as a result of these twelve IRPs. We then offer observations about the IRP process, and how it might be improved to more objectively evaluate renewable resources.

  15. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    SciTech Connect (OSTI)

    Saurwein, John

    2011-07-15T23:59:59.000Z

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  16. Integrated High Speed Intelligent Utility Tie Unit for Disbursed/Renewable Generation Facilities Worakarn Wongsaichua, Wei-Jen Lee Soontorn Oraintara Chiman Kwan Frank Zhang

    E-Print Network [OSTI]

    Oraintara, Soontorn

    Integrated High Speed Intelligent Utility Tie Unit for Disbursed/Renewable Generation Facilities is to rejuvenate the idea of integrated resource planning and promote the distributed generation via traditional or renewable generation facilities for the deregulated utility systems. Fuel cell and photovoltaic are the most

  17. World nuclear fuel cycle requirements 1991

    SciTech Connect (OSTI)

    Not Available

    1991-10-10T23:59:59.000Z

    The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

  18. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2010-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750įC, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

  19. Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project

    SciTech Connect (OSTI)

    Ian McKirdy

    2011-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

  20. A dynamic, dependent type system for nuclear fuel cycle code generation

    SciTech Connect (OSTI)

    Scopatz, A. [The University of Chicago 5754 S. Ellis Ave, Chicago, IL 60637 (United States)

    2013-07-01T23:59:59.000Z

    The nuclear fuel cycle may be interpreted as a network or graph, thus allowing methods from formal graph theory to be used. Nodes are often idealized as nuclear fuel cycle facilities (reactors, enrichment cascades, deep geologic repositories). With the advent of modern object-oriented programming languages - and fuel cycle simulators implemented in these languages - it is natural to define a class hierarchy of facility types. Bright is a quasi-static simulator, meaning that the number of material passes through a facility is tracked rather than natural time. Bright is implemented as a C++ library that models many canonical components such as reactors, storage facilities, and more. Cyclus is a discrete time simulator, meaning that natural time is tracked through out the simulation. Therefore a robust, dependent type system was developed to enable inter-operability between Bright and Cyclus. This system is capable of representing any fuel cycle facility. Types declared in this system can then be used to automatically generate code which binds a facility implementation to a simulator front end. Facility model wrappers may be used either internally to a fuel cycle simulator or as a mechanism for inter-operating multiple simulators. While such a tool has many potential use cases it has two main purposes: enabling easy performance of code-to-code comparisons and the verification and the validation of user input.

  1. Nonlinear Adaptive Control of Networked Power Generators with Remote Measurement Units

    E-Print Network [OSTI]

    Paris-Sud XI, Universitť de

    of view of Control Engineering the power systems urge for more modern and accurate techniques. Due provided by Phasor Measurement Units (PMU). The proposed control system is designed in a robust way measurements on control schemes. In the last three decades the power systems have been growing in complexity

  2. Impact of unit commitment constraints on generation expansion planning with renewables

    E-Print Network [OSTI]

    Palmintier, Bryan Stephen

    Growing use of renewables pushes thermal generators against operating constraints - e.g. ramping, minimum output, and operating reserves - that are traditionally ignored in expansion planning models. We show how including ...

  3. Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations

    SciTech Connect (OSTI)

    Blum, A.; Smith, R.J. [Public Service Electric and Gas Co., Hancocks Bridge, NJ (United States)

    1991-06-01T23:59:59.000Z

    Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment.

  4. Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project

    SciTech Connect (OSTI)

    L.E. Demick

    2010-09-01T23:59:59.000Z

    At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest Ė i.e., within the next 10-15 years.

  5. Bikini, Enewetak, and Rongelap Marshallese, and United States nuclear weapons testing in the Marshall Islands: A bibliography

    SciTech Connect (OSTI)

    Robison, W.L. (ed.) (Lawrence Livermore National Lab., CA (USA)); Schultz, V. (Washington State Univ., Pullman, WA (USA)); Schultz, S.C. (Oregon Univ., Eugene, OR (USA))

    1991-04-01T23:59:59.000Z

    A considerable literature exists on the Bikini, Enewetak, and Rongelap Marshallese and their atolls; however, this literature consists of a large number of governmental documents that are relatively unknown and difficult to locate. This is particularly true of the documents of the Trust Territory of the Pacific Islands and those related to nuclear weapons testing in the Marshall Islands. Because a comprehensive bibliography on the impact of nuclear weapons testing on the Marshallese and their atolls does not exist, the preparation of a bibliography that includes sufficient information to locate all types of reports seems justified. Primary sources of information in preparing this bibliography were bibliographies on Oceania, citations in published papers, CIS Index and Abstracts, Monthly Catalog of United States Government Publications, Nuclear Science Abstracts, Energy Research Abstracts, numerous bibliographies on radiation ecology, and suggestions by many individuals whom we contacted. One goal in this bibliography is to include complete documentation of the source of congressional reports and other government-related publications. In addition, page numbers for material in this bibliography are provided in parentheses when the subject matter of a book or document is not restricted to nuclear weapons testing in the Marshall Islands.

  6. EM Renews Information-Sharing Agreement with United Kingdom's Nuclear Decommissioning Authority

    Broader source: Energy.gov [DOE]

    PHOENIX Ė EMís top official this week renewed an agreement between DOE and the U.K.ís Nuclear Decommissioning Authority (NDA) that expands the scope of their information sharing.

  7. Generator, mechanical, smoke: For dual-purpose unit, XM56, Yuma Proving Ground, Yuma, Arizona

    SciTech Connect (OSTI)

    Driver, C.J.; Ligotke, M.W.; Moore, E.B. Jr. (Pacific Northwest Lab., Richland, WA (United States)); Bowers, J.F. (Dugway Proving Ground, UT (United States))

    1991-10-01T23:59:59.000Z

    The US Army Chemical Research, Development and Engineering Center (CRDEC) is planning to perform a field test of the XM56 smoke generator at the US Army Yuma Proving Ground (YPG), Arizona. The XM56, enabling the use of fog oil in combination with other materials, such as graphite flakes, is part of an effort to improve the efficiency of smoke generation and to extend the effectiveness of the resulting obscurant cloud to include the infrared spectrum. The plan field operation includes a road test and concurrent smoke- generation trials. Three M1037 vehicles with operation XM56 generators will be road-tested for 100 h. Smoke will be generated for 30 min from a single stationary XM56 four times during the road test, resulting in a total of 120 min of smoke generation. The total aerial release of obscurant materials during this test is expected to be 556 kg (1,220 lb) of fog oil and 547 kg (1,200 lb) of graphite flakes. This environmental assessment has evaluated the consequences of the proposed action. Air concentrations and surface deposition levels were estimated using an atmospheric dispersion model. Degradation of fog oil and incorporation of graphite in the soil column will limit the residual impacts of the planned action. No significant impacts to air, water, and soil quality are anticipated. risks to the environment posed by the proposed action were determined to be minimal or below levels previously found to pose measurable impacts. Cultural resources are present on YPG and have been identified in adjacent areas; therefore, off-road activities should be preceded by a cultural resource survey. A Finding of No Significant Impact is recommended. 61 refs., 1 fig.

  8. Regenerative Heater Optimization for Steam Turbo-Generation Cycles of Generation IV Nuclear Power Plants with a Comparison of Two Concepts for the Westinghouse International Reactor Innovative and Secure (IRIS)

    SciTech Connect (OSTI)

    Williams, W.C.

    2002-08-01T23:59:59.000Z

    The intent of this study is to discuss some of the many factors involved in the development of the design and layout of a steam turbo-generation unit as part of a modular Generation IV nuclear power plant. Of the many factors involved in the design and layout, this research will cover feed water system layout and optimization issues. The research is arranged in hopes that it can be generalized to any Generation IV system which uses a steam powered turbo-generation unit. The research is done using the ORCENT-II heat balance codes and the Salisbury methodology to be reviewed herein. The Salisbury methodology is used on an original cycle design by Famiani for the Westinghouse IRIS and the effects due to parameter variation are studied. The vital parameters of the Salisbury methodology are the incremental heater surface capital cost (S) in $/ft{sup 2}, the value of incremental power (I) in $/kW, and the overall heat transfer coefficient (U) in Btu/ft{sup 2}-degrees Fahrenheit-hr. Each is varied in order to determine the effects on the cycles overall heat rate, output, as well as, the heater surface areas. The effects of each are shown. Then the methodology is then used to compare the optimized original Famiani design consisting of seven regenerative feedwater heaters with an optimized new cycle concept, INRC8, containing four regenerative heaters. The results are shown. It can be seen that a trade between the complexity of the seven stage regenerative Famiani cycle and the simplicity of the INRC8 cycle can be made. It is desired that this methodology can be used to show the ability to evaluate modularity through the value of size a complexity of the system as well as the performance. It also shows the effectiveness of the Salisbury methodology in the optimization of regenerative cycles for such an evaluation.

  9. Quantity, quality, and availability of waste heat from United States thermal power generation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gingerich, Daniel B; Mauter, Meagan S

    2015-06-10T23:59:59.000Z

    Secondary application of unconverted heat produced during electric power generation has the potential to improve the life-cycle fuel efficiency of the electric power industry and the sectors it serves. This work quantifies the residual heat (also known as waste heat) generated by U.S. thermal power plants and assesses the intermittency and transport issues that must be considered when planning to utilize this heat. Combining Energy Information Administration plant-level data with literature-reported process efficiency data, we develop estimates of the unconverted heat flux from individual U.S. thermal power plants in 2012. Together these power plants discharged an estimated 18.9 billion GJthmore†Ľof residual heat in 2012, 4% of which was discharged at temperatures greater than 90 įC. We also characterize the temperature, spatial distribution, and temporal availability of this residual heat at the plant level and model the implications for the technical and economic feasibility of its end use. Increased implementation of flue gas desulfurization technologies at coal-fired facilities and the higher quality heat generated in the exhaust of natural gas fuel cycles are expected to increase the availability of residual heat generated by 10.6% in 2040.ę†less

  10. Quantity, quality, and availability of waste heat from United States thermal power generation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gingerich, Daniel B [Carnegie Mellon Univ., Pittsburgh, PA (United States); Mauter, Meagan S [Carnegie Mellon Univ., Pittsburgh, PA (United States)

    2015-06-10T23:59:59.000Z

    Secondary application of unconverted heat produced during electric power generation has the potential to improve the life-cycle fuel efficiency of the electric power industry and the sectors it serves. This work quantifies the residual heat (also known as waste heat) generated by U.S. thermal power plants and assesses the intermittency and transport issues that must be considered when planning to utilize this heat. Combining Energy Information Administration plant-level data with literature-reported process efficiency data, we develop estimates of the unconverted heat flux from individual U.S. thermal power plants in 2012. Together these power plants discharged an estimated 18.9 billion GJth of residual heat in 2012, 4% of which was discharged at temperatures greater than 90 įC. We also characterize the temperature, spatial distribution, and temporal availability of this residual heat at the plant level and model the implications for the technical and economic feasibility of its end use. Increased implementation of flue gas desulfurization technologies at coal-fired facilities and the higher quality heat generated in the exhaust of natural gas fuel cycles are expected to increase the availability of residual heat generated by 10.6% in 2040.

  11. Operation and Control of Distribution Systems with high level integration of Renewable Generation units

    E-Print Network [OSTI]

    Bak-Jensen, Birgitte

    models Probabilistic methodologies are being applied to power system analysis since 70' [9] becauseOperation and Control of Distribution Systems with high level integration of Renewable Generation. Diagonal 649 Pavellů A, 08028 Barcelona, Spain Summary Traditional power systems have a hierarchical

  12. METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

  13. Disparities in nuclear power plant performance in the United States and the Federal Republic of Germany

    E-Print Network [OSTI]

    Hansen, Kent F.

    1984-01-01T23:59:59.000Z

    This report presents data comparing the performance of light water reactors in the United States and the Federal Republic of Germany (FRG). The comparisons are made for the years 1980-1983 and include 21 Westinghouse ...

  14. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2008-04-01T23:59:59.000Z

    The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900įC and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2ľCr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

  15. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    SciTech Connect (OSTI)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

    1982-08-01T23:59:59.000Z

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

  16. Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report

    SciTech Connect (OSTI)

    L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

    2000-09-01T23:59:59.000Z

    OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

  17. Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498

    SciTech Connect (OSTI)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2008-09-01T23:59:59.000Z

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the ďhighly rankedĒ phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  18. Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report

    Broader source: Energy.gov [DOE]

    The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new...

  19. Property exempt from taxation: nuclear generation facility property: K.S.A. 79-230 (Kansas)

    Broader source: Energy.gov [DOE]

    This legislation would exempt from state property taxes any property purchased, constructed or installed to expand capacity at an existing nuclear plant or to build a new nuclear plant. A...

  20. MHK Technologies/OCGen turbine generator unit TGU | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, searchOfRose Bend < MHK ProjectsFlagshipNAREC < MHKOCGen turbine generator

  1. The Long-Life Core Encapsulated Nuclear Heat Source (ENHS) Generation IV Reactor

    SciTech Connect (OSTI)

    Greenspan, E.; Barak, A.; Saphier, D. [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Buongiorno, J. [Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Brown, N.W.; Hossain, Q. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA 94550 (United States); Carelli, M.D.; Conway, L.; Dzodzo, M. [Westinghouse Electric Co., Sci. and Tech., 1344 Beulah Rd., Pittsburgh, PA 15235 (United States); Feldman, E.; Sienicki, J.J.; Sofu, T.; Wade, D.C. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Hong, S.G.; Kim, Y.I. [Korea Atomic Energy Research Institute, Yusong, Taejon 305-600, Rep. of Korea (Korea, Republic of)

    2002-07-01T23:59:59.000Z

    The long-life core for the Encapsulated Nuclear Heat Source (ENHS) reactor has been redesigned so as to provide for fuel rod clad integrity up to the discharge burnup design goal. It was found feasible to design a nearly zero burnup reactivity swing long-life core that will maintain the fuel rod integrity up to the peak discharge burnup while enabling to handle the rated power using natural circulation. The core life is limited by radiation damage to its structural material. The core power shape is exceptionally constant throughout the core life. The new reference core design can deliver 125 MW{sub th} while having very generous margins for maximum acceptable temperatures or temperature differences. Using a cover-gas lift-pump it may be possible to design an ENHS module to deliver {approx}50% more power than the set goal. Briefly reviewed are unique features of the ENHS reactor along with the potential of this reactor to meet the goals set for Generation IV reactors. (authors)

  2. Study on the colloids generated from testing of high-level nuclear waste glasses

    SciTech Connect (OSTI)

    Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.J.

    1993-03-01T23:59:59.000Z

    The generation of colloids in the interaction of high-level nuclear waste glasses with groundwater at 90{degrees}C has been investigated. The stability of the colloidal suspensions has been characterized with respect to salt concentration, pH time, particle size, and zeta potential. The compositions and the morphology of the colloids have also been determined with transmission electron microscopy (TEM). From ourtest results combined with earlier ones, we conclude that the waste glass may contribute to the colloid formation by increasing ion concentration in groundwater, which causes nucleation of colloids; by releasing radionuclides that adsorb onto existing groundwater colloids; and by spalling colloidal-size fragments from the surface layer of the reacted glass. The colloids are silicon-rich particles, such as smectites and uranium silicates. When the salt concentration in the solution is high the colloidal suspensions agglomerate. However, the agglomerated particles can be resuspended if the salt concentration is lowered by dilution with groundwater. The colloids agglomerate quickly after the leachate is cooled to room temperature. Most of the colloids settle out of the solution within a few days at ambient temperature. The isoelectric point is at a pH of approximately 1.0. Between pH 1 and 10.5, the colloids are negatively charged, which suggests that they will deposit readily on, positively charged surfaces. The average particle size islargest at the isoelectric point and is smallest around pH 6.

  3. Characteristics of colloids generated during the corrosion of nuclear waste glasses in groundwater

    SciTech Connect (OSTI)

    Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.

    1993-10-01T23:59:59.000Z

    Aqueous colloidal suspensions were generated by reacting nuclear waste glasses with groundwater at 90{degrees}C at different ratios of the glass surface area to solution volume (S/V). The colloids have been characterized in terms of size, charge, identity, and stability with respect to salt concentration, pH, and time, by examination using dynamic light scattering, electrophoretic mobility, and transmission electron microscopy. The colloids are predominately produced by precipitation from solution, possibly with contribution from reacted layers that have spallated from the glass. These colloids are silicon-rich minerals. The colloidal suspensions agglomerate when the salinity of the solutions increase. The following implications for modeling the colloidal transport of contaminants have been derived from this study: (1) The sources of the colloids are not only solubility-limited real colloids and the pseudo colloids formed by adsorption of radionuclides onto a groundwater colloid, but also from the spalled surface layers of reacted waste glasses. (2) In a repository, the local environment is likely to be glass-reaction dominated and the salt concentration is likely to be high, leading to rapid colloid agglomeration and settling; thus, colloid transport may be insignificant. (3) If large volumes of groundwater contact the glass reaction site, the precipitated colloids may become resuspended, and colloid transport may become important. (4) Under most conditions, the colloids are negatively charged and will deposit readily on positively charged surfaces. Negatively charged surfaces will, in general, facilitate colloid stability and transport.

  4. Study on the colloids generated from testing of high-level nuclear waste glasses

    SciTech Connect (OSTI)

    Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.J.

    1993-01-01T23:59:59.000Z

    The generation of colloids in the interaction of high-level nuclear waste glasses with groundwater at 90[degrees]C has been investigated. The stability of the colloidal suspensions has been characterized with respect to salt concentration, pH time, particle size, and zeta potential. The compositions and the morphology of the colloids have also been determined with transmission electron microscopy (TEM). From ourtest results combined with earlier ones, we conclude that the waste glass may contribute to the colloid formation by increasing ion concentration in groundwater, which causes nucleation of colloids; by releasing radionuclides that adsorb onto existing groundwater colloids; and by spalling colloidal-size fragments from the surface layer of the reacted glass. The colloids are silicon-rich particles, such as smectites and uranium silicates. When the salt concentration in the solution is high the colloidal suspensions agglomerate. However, the agglomerated particles can be resuspended if the salt concentration is lowered by dilution with groundwater. The colloids agglomerate quickly after the leachate is cooled to room temperature. Most of the colloids settle out of the solution within a few days at ambient temperature. The isoelectric point is at a pH of approximately 1.0. Between pH 1 and 10.5, the colloids are negatively charged, which suggests that they will deposit readily on, positively charged surfaces. The average particle size islargest at the isoelectric point and is smallest around pH 6.

  5. Updated greenhouse gas and criteria air pollutant emission factors and their probability distribution functions for electricity generating units

    SciTech Connect (OSTI)

    Cai, H.; Wang, M.; Elgowainy, A.; Han, J. (Energy Systems)

    2012-07-06T23:59:59.000Z

    Greenhouse gas (CO{sub 2}, CH{sub 4} and N{sub 2}O, hereinafter GHG) and criteria air pollutant (CO, NO{sub x}, VOC, PM{sub 10}, PM{sub 2.5} and SO{sub x}, hereinafter CAP) emission factors for various types of power plants burning various fuels with different technologies are important upstream parameters for estimating life-cycle emissions associated with alternative vehicle/fuel systems in the transportation sector, especially electric vehicles. The emission factors are typically expressed in grams of GHG or CAP per kWh of electricity generated by a specific power generation technology. This document describes our approach for updating and expanding GHG and CAP emission factors in the GREET (Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation) model developed at Argonne National Laboratory (see Wang 1999 and the GREET website at http://greet.es.anl.gov/main) for various power generation technologies. These GHG and CAP emissions are used to estimate the impact of electricity use by stationary and transportation applications on their fuel-cycle emissions. The electricity generation mixes and the fuel shares attributable to various combustion technologies at the national, regional and state levels are also updated in this document. The energy conversion efficiencies of electric generating units (EGUs) by fuel type and combustion technology are calculated on the basis of the lower heating values of each fuel, to be consistent with the basis used in GREET for transportation fuels. On the basis of the updated GHG and CAP emission factors and energy efficiencies of EGUs, the probability distribution functions (PDFs), which are functions that describe the relative likelihood for the emission factors and energy efficiencies as random variables to take on a given value by the integral of their own probability distributions, are updated using best-fit statistical curves to characterize the uncertainties associated with GHG and CAP emissions in life-cycle modeling with GREET.

  6. Next Generation Nuclear Plant Intermediate Heat Exchanger Materials Research and Development Plan (PLN-2804)

    SciTech Connect (OSTI)

    J. K. Wright

    2008-04-01T23:59:59.000Z

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900įC and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Todayís high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760įC. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  7. Optimal sizing study of hybrid wind/PV/diesel power generation unit

    SciTech Connect (OSTI)

    Belfkira, Rachid; Zhang, Lu; Barakat, Georges [Groupe de Recherche en Electrotechnique et Automatique du Havre, University of Le Havre, 25 rue Philippe Lebon, BP 1123, 76063 Le Havre (France)

    2011-01-15T23:59:59.000Z

    In this paper, a methodology of sizing optimization of a stand-alone hybrid wind/PV/diesel energy system is presented. This approach makes use of a deterministic algorithm to suggest, among a list of commercially available system devices, the optimal number and type of units ensuring that the total cost of the system is minimized while guaranteeing the availability of the energy. The collection of 6 months of data of wind speed, solar radiation and ambient temperature recorded for every hour of the day were used. The mathematical modeling of the main elements of the hybrid wind/PV/diesel system is exposed showing the more relevant sizing variables. A deterministic algorithm is used to minimize the total cost of the system while guaranteeing the satisfaction of the load demand. A comparison between the total cost of the hybrid wind/PV/diesel energy system with batteries and the hybrid wind/PV/diesel energy system without batteries is presented. The reached results demonstrate the practical utility of the used sizing methodology and show the influence of the battery storage on the total cost of the hybrid system. (author)

  8. Generation IV Nuclear Energy Systems Construction Cost Reductions through the use of Virtual Environments: Task 1 Completion Report

    SciTech Connect (OSTI)

    Whisker, V.E.; Baratta, A.J.; Shaw, T.S.; Winters, J.W.; Trikouros, N.; Hess, C.

    2002-11-26T23:59:59.000Z

    OAK B204 The objective of this project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. Specifically, this project will test the suitability of Immersive Projection Display (IPD) technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups.

  9. ( )Ministers delay decision on site for 10-billion-dollar nuclear fusion reactor 20/12/2003 The European Union, the United States and four other countries failed in talks agree on a

    E-Print Network [OSTI]

    of transporting nuclear material and storing dangerous long-term radioactive waste. Nuclear fusion takes( )Ministers delay decision on site for 10-billion-dollar nuclear fusion reactor 20-dollar international nuclear fusion reactor. Delegates from the European Union, the United States, China, Japan, South

  10. An evaluation of the United Kingdom Clean Coal Power Generation Group`s air-blown gasification cycle

    SciTech Connect (OSTI)

    Wheeldon, J.M.; Brown, R.A. [Electric Power Research Inst., Palo Alto, CA (United States); McKinsey, R.R. [Bechtel Group, Inc., San Francisco, CA (United States); Dawes, S.G. [British Coal Corp., Cheltenham (United Kingdom)

    1996-12-31T23:59:59.000Z

    The Electric Power Research Institute (EPRI) is conducting an engineering and economic study of various pressurized fluidized-bed combustor (PFBC) designs. Studies have been completed on bubbling and circulating PFBC technologies and on an advanced PFBC power plant technology, in which the feed coal is partially gasified and the residual char burned in a PFBC. The United Kingdom Clean Coal Power Generation Group`s (CCPGG) air-blown gasification cycle (ABGC), known formerly as the British Coal Topping Cycle, also partially gasifies the feed coal, but uses a circulating atmospheric fluidized-bed combustor (AFBC) to burn the residual char. Although not a PFBC plant, the study was completed to effect a comparison with the advanced PFBC cycle.

  11. STARLIB: A NEXT-GENERATION REACTION-RATE LIBRARY FOR NUCLEAR ASTROPHYSICS

    SciTech Connect (OSTI)

    Sallaska, A. L. [National Institute of Standards and Technology, Gaithersburg, MD 20899-8462 (United States); Iliadis, C.; Champange, A. E. [University of North Carolina at Chapel Hill, Chapel Hill, NC 27599-3255 (United States); Goriely, S. [Institut d'Astronomie et d'Astrophysique, Universite Libre de Bruxelles, C.P. 226, B-1050 Brussels (Belgium); Starrfield, S.; Timmes, F. X., E-mail: anne.sallaska@nist.gov [Arizona State University, Tempe, AZ 85287-1504 (United States)

    2013-07-15T23:59:59.000Z

    STARLIB is a next-generation, all-purpose nuclear reaction-rate library. For the first time, this library provides the rate probability density at all temperature grid points for convenient implementation in models of stellar phenomena. The recommended rate and its associated uncertainties are also included. Currently, uncertainties are absent from all other rate libraries, and, although estimates have been attempted in previous evaluations and compilations, these are generally not based on rigorous statistical definitions. A common standard for deriving uncertainties is clearly warranted. STARLIB represents a first step in addressing this deficiency by providing a tabular, up-to-date database that supplies not only the rate and its uncertainty but also its distribution. Because a majority of rates are lognormally distributed, this allows the construction of rate probability densities from the columns of STARLIB. This structure is based on a recently suggested Monte Carlo method to calculate reaction rates, where uncertainties are rigorously defined. In STARLIB, experimental rates are supplemented with: (1) theoretical TALYS rates for reactions for which no experimental input is available, and (2) laboratory and theoretical weak rates. STARLIB includes all types of reactions of astrophysical interest to Z = 83, such as (p, {gamma}), (p, {alpha}), ({alpha}, n), and corresponding reverse rates. Strong rates account for thermal target excitations. Here, we summarize our Monte Carlo formalism, introduce the library, compare methods of correcting rates for stellar environments, and discuss how to implement our library in Monte Carlo nucleosynthesis studies. We also present a method for accessing STARLIB on the Internet and outline updated Monte Carlo-based rates.

  12. ASSESSMENT OF THE RADIONUCLIDE COMPOSITION OF "HOT PARTICLES" SAMPLED IN THE CHERNOBYL NUCLEAR POWER PLANT FOURTH REACTOR UNIT

    SciTech Connect (OSTI)

    Farfan, E.; Jannik, T.; Marra, J.

    2011-10-01T23:59:59.000Z

    Fuel-containing materials sampled from within the Chernobyl Nuclear Power Plant (ChNPP) 4th Reactor Unit Confinement Shelter were spectroscopically studied for gamma and alpha content. Isotopic ratios for cesium, europium, plutonium, americium, and curium were identified and the fuel burnup in these samples was determined. A systematic deviation in the burnup values based on the cesium isotopes, in comparison with other radionuclides, was observed. The conducted studies were the first ever performed to demonstrate the presence of significant quantities of {sup 242}Cm and {sup 243}Cm. It was determined that there was a systematic underestimation of activities of transuranic radionuclides in fuel samples from inside of the ChNPP Confinement Shelter, starting from {sup 241}Am (and going higher), in comparison with the theoretical calculations.

  13. United States-Russia Joint Statement on the Results of the Nuclear Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCOSystems Analysis Success|Sustainable EnergyMotorUncleStates-Japanand Nuclear

  14. United States and Japan Sign Joint Nuclear Energy Action Plan to Promote

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof Energy 2, 2015 -Helicopter-Japan Joint Nuclear Energy ActionEnergy Italy

  15. Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems

    SciTech Connect (OSTI)

    Todd R. Allen

    2009-06-30T23:59:59.000Z

    This project will use proton irradiation to further understand the microstructural stability of ceramics being considered as matrix material for advanced nuclear fuels.

  16. Geological Constraints on High-Level Nuclear Waste Disposal and their Relationship to Possible

    E-Print Network [OSTI]

    Polly, David

    nuclear energy. The U.S. government has recognized geologic disposal as a solution since the mid-1950s of plants produces about 20% of the United States' total energy consumption [EPA website, Nuclear Energy radioactivity produced in the process of electricity generation by nuclear fission [World Nuclear Association

  17. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 14

    SciTech Connect (OSTI)

    Tam, P.S.

    1994-12-01T23:59:59.000Z

    Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued.

  18. HOW MANY DID YOU SAY? HISTORICAL AND PROJECTED SPENT NUCLEAR FUEL SHIPMENTS IN THE UNITED STATES, 1964 - 2048

    SciTech Connect (OSTI)

    Halstead, Robert J.; Dilger, Fred

    2003-02-27T23:59:59.000Z

    No comprehensive, up-to-date, official database exists for spent nuclear fuel shipments in the United States. The authors review the available data sources, and conclude that the absence of such a database can only be rectified by a major research effort, similar to that carried out by Oak Ridge National Laboratory (ORNL) in the early 1990s. Based on a variety of published references, and unpublished data from the U.S. Nuclear Regulatory Commission (NRC), the authors estimate cumulative U.S. shipments of commercial spent fuel for the period 1964-2001. The cumulative estimates include quantity shipped, number of cask-shipments, and shipment-miles, by truck and by rail. The authors review previous estimates of future spent fuel shipments, including contractor reports prepared for the U.S. Department of Energy (DOE), NRC, and the State of Nevada. The DOE Final Environmental Impact Statement (FEIS) for Yucca Mountain includes projections of spent nuclear fuel and high-level radioactive was te shipments for two inventory disposal scenarios (24 years and 38 years) and two national transportation modal scenarios (''mostly legal-weight truck'' and ''mostly rail''). Commercial spent fuel would compromise about 90 percent of the wastes shipped to the repository. The authors estimate potential shipments to Yucca Mountain over 38 years (2010-2048) for the DOE ''mostly legal-weight truck'' and ''mostly rail'' scenarios, and for an alternative modal mix scenario based on current shipping capabilities of the 72 commercial reactor sites. The cumulative estimates of future spent fuel shipments include quantity shipped, number of cask-shipments, and shipment-miles, by legal-weight truck, heavy-haul truck, rail and barge.

  19. Offsite environmental monitoring report; radiation monitoring around United States nuclear test areas, Calendar Year 1996

    SciTech Connect (OSTI)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Huff, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1997-08-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs). No nuclear weapons testing was conducted in 1996 due to the continuing nuclear test moratorium. During this period, R and IE personnel maintained readiness capability to provide direct monitoring support if testing were to be resumed and ascertained compliance with applicable EPA, DOE, state, and federal regulations and guidelines. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no airborne radioactivity from diffusion or resuspension detected by the various EPA monitoring networks surrounding the NTS. There was no indication of potential migration of radioactivity to the offsite area through groundwater and no radiation exposure above natural background was received by the offsite population. All evaluated data were consistent with previous data history.

  20. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    average value for nuclear plants) aFinal Envir. Statement (Statement, Koshkonong Nuclear Plant, August 1976. U. S.rem; operation of the nuclear plants themselves only *Other

  1. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration

    E-Print Network [OSTI]

    Sidiropoulos, Nikolaos D.

    , for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94ALT i For example: #12;Semantic Graphs ∑ Different types of edges ∑ Attribute or relationship labels type of edge. DEDICOM PARAFAC Multilinear algebra Adjacency matrix Adjacency tensor #12;Using Tensors

  2. A Resurgence of United Kingdom Nuclear Power Research (2011 EFRC Forum)

    ScienceCinema (OSTI)

    Grimes, Robin W. (Imperial College, London, UK)

    2012-03-14T23:59:59.000Z

    Robin W. Grimes, Professor at Imperial College, London,was the third speaker in the the May 26, 2011 EFRC Forum session, "Global Perspectives on Frontiers in Energy Research." In his presentation, Professor Grimes discussed recent research endeavors in advanced nuclear energy systems being pursued in the UK. The 2011 EFRC Summit and Forum brought together the EFRC community and science and policy leaders from universities, national laboratories, industry and government to discuss "Science for our Nation's Energy Future." In August 2009, the Office of Science established 46 Energy Frontier Research Centers. The EFRCs are collaborative research efforts intended to accelerate high-risk, high-reward fundamental research, the scientific basis for transformative energy technologies of the future. These Centers involve universities, national laboratories, nonprofit organizations, and for-profit firms, singly or in partnerships, selected by scientific peer review. They are funded at $2 to $5 million per year for a total planned DOE commitment of $777 million over the initial five-year award period, pending Congressional appropriations. These integrated, multi-investigator Centers are conducting fundamental research focusing on one or more of several ?grand challenges? and use-inspired ?basic research needs? recently identified in major strategic planning efforts by the scientific community. The purpose of the EFRCs is to integrate the talents and expertise of leading scientists in a setting designed to accelerate research that transforms the future of energy and the environment.

  3. Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels†

    E-Print Network [OSTI]

    Hackemack, Michael Wayne

    2013-04-15T23:59:59.000Z

    of their species (charge, mass, and energy) and the large averaging of their relative yields in the nuclear data files. This work is our first iteration at developing a general methodology to characterize a procedure, based on Monte Carlo principles...

  4. Next Generation Rooftop Unit

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in Many DevilsForumEngines |NewStateDepartment of(BETO) 2015NextNext

  5. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    SciTech Connect (OSTI)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

  6. Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 4 Report: Virtual Mockup Maintenance Task Evaluation

    SciTech Connect (OSTI)

    Timothy Shaw; Anthony Baratta; Vaughn Whisker

    2005-02-28T23:59:59.000Z

    Task 4 report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. This report focuses on using Full-scale virtual mockups for nuclear power plant training applications.

  7. Determination of Nickel Species in Stack Emissions from Eight Residual Oil-Fired Utility Steam-Generating Units

    SciTech Connect (OSTI)

    F Huggins; K Galbreath; K Eylands; L Van Loon; J Olson; E Zillioux; S Ward; P Lynch; P Chu

    2011-12-31T23:59:59.000Z

    XAFS spectroscopy has been used to determine the Ni species in particulate matter collected on quartz thimble filters in the stacks of eight residual (No. 6 fuel) oil-burning electric utility steam-generating units. Proper speciation of nickel in emitted particulate matter is necessary to correctly anticipate potential health risks. Analysis of the spectroscopic data using least-squares linear combination methods and a newly developed method specific for small quantities of Ni sulfide compounds in such emissions show that potentially carcinogenic Ni sulfide compounds are absent within the detection limits of the method ({le}3% of the total Ni) in the particulate matter samples investigated. In addition to the major nickel sulfate phase (NiSO{sub 4} {center_dot} 6H{sub 2}O), lesser amounts of (Ni,Mg)O and/or NiFe{sub 2}O{sub 4} were also identified in most emission samples. On the basis of the results from these emission characterization studies, the appropriateness of the U.S. Environmental Protection Agency's assumption that the Ni compound mixture emitted from residual oil-fired power plants is 50% as carcinogenic as nickel subsulfide (Ni{sub 3}S{sub 2}) should be re-evaluated.

  8. A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons

    E-Print Network [OSTI]

    Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

    2002-01-01T23:59:59.000Z

    It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

  9. EIS-0105: Conversion to Coal, Baltimore Gas & Electric Company, Brandon Shores Generating Station Units 1 and 2, Anne Arundel County, Maryland

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energyís Economic Regulatory Administration Office of Fuels Program, Coal and Electricity Division prepared this statement to assess the potential environmental and socioeconomic impacts associated with prohibiting the use of petroleum products as a primary energy source for Units 1 and 2 of the Brandon Shores Generating Station, located in Anne Arundel County, Maryland.

  10. EIS-0086: Conversion to Coal, New England Power Company, Salem Harbor Generating Station Units 1, 2, and 3, Salem, Essex County, Massachusetts

    Broader source: Energy.gov [DOE]

    The Economic Regulatory Administration prepared this statement to assess the environmental impacts of prohibiting Units I, 2, and 3 of the Salem Harbor Generating Station from using either natural gas or petroleum products as a primary energy source, which would result in the utility burning low-sulfur coal.

  11. China's Nuclear Industry After Fukushima

    E-Print Network [OSTI]

    YUAN, Jingdong

    2013-01-01T23:59:59.000Z

    the previous year. NUCLEAR TECHNOLOGY AND FUEL CYCLES Chinaíthird-generation nuclear technology and reactor design, withs own third-generation nuclear technology. Westing- house,

  12. Application of simultaneous active and reactive power modulation of superconducting magnetic energy storage unit to damp turbine-generator subsynchronous oscillations

    SciTech Connect (OSTI)

    Wu, Chijui; Lee, Yuangshung (National Taiwan Inst. of Tech., Taipie (Taiwan, Province of China))

    1993-03-01T23:59:59.000Z

    An active and reactive power (P-Q) simultaneous control scheme which is based on a superconducting magnetic energy storage (SMES) unit is designed to damp out the subsynchronous resonant (SSR) oscillations of a turbine-generator unit. In order to suppress unstable torsional mode oscillations, a proportional-integral-derivative (PID) controller is employed to modulate the active and reactive power input/output of the SMES unit according to speed deviation of the generator shaft. The gains of the proposed PID controller are determined by pole assignment approach based on modal control theory. Eigenvalue analysis of the studied system shows that the PID controller is quite effective over a wide range of operating conditions. Dynamic simulations using the nonlinear system model are also performed to demonstrate the damping effect of the proposed control scheme under disturbance conditions.

  13. Electronic constant current and current pulse signal generator for nuclear instrumentation testing

    DOE Patents [OSTI]

    Brown, Roger A. (Amsterdam, NY)

    1994-01-01T23:59:59.000Z

    Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

  14. Electronic constant current and current pulse signal generator for nuclear instrumentation testing

    DOE Patents [OSTI]

    Brown, R.A.

    1994-04-19T23:59:59.000Z

    Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

  15. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

  16. Joint U.S./Russian Study on the Development of a Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1

    SciTech Connect (OSTI)

    SM Garrett

    1998-09-28T23:59:59.000Z

    The objectives of the two joint Russian/U.S. Leningrad Nuclear Power Plant (NPP) Unit #1 studies were the development of a safe, technically feasible, economically acceptable decom missioning strategy, and the preliminary cost evaluation of the developed strategy. The first study, resulting in the decommissioning strategy, was performed in 1996 and 1997. The preliminary cost estimation study, described in this report, was performed in 1997 and 1998. The decommissioning strategy study included the analyses of three basic RBM.K decommission- ing alternatives, refined for the Leningrad NPP Unit #1. The analyses included analysis of the requirements for the planning and preparation as well as the decommissioning phases.

  17. Risk perception & strategic decision making :general insights, a framework, and specific application to electricity generation using nuclear energy.

    SciTech Connect (OSTI)

    Brewer, Jeffrey D.

    2005-11-01T23:59:59.000Z

    The objective of this report is to promote increased understanding of decision making processes and hopefully to enable improved decision making regarding high-consequence, highly sophisticated technological systems. This report brings together insights regarding risk perception and decision making across domains ranging from nuclear power technology safety, cognitive psychology, economics, science education, public policy, and neural science (to name a few). It forms them into a unique, coherent, concise framework, and list of strategies to aid in decision making. It is suggested that all decision makers, whether ordinary citizens, academics, or political leaders, ought to cultivate their abilities to separate the wheat from the chaff in these types of decision making instances. The wheat includes proper data sources and helpful human decision making heuristics; these should be sought. The chaff includes ''unhelpful biases'' that hinder proper interpretation of available data and lead people unwittingly toward inappropriate decision making ''strategies''; obviously, these should be avoided. It is further proposed that successfully accomplishing the wheat vs. chaff separation is very difficult, yet tenable. This report hopes to expose and facilitate navigation away from decision-making traps which often ensnare the unwary. Furthermore, it is emphasized that one's personal decision making biases can be examined, and tools can be provided allowing better means to generate, evaluate, and select among decision options. Many examples in this report are tailored to the energy domain (esp. nuclear power for electricity generation). The decision making framework and approach presented here are applicable to any high-consequence, highly sophisticated technological system.

  18. A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report

    Broader source: Energy.gov [DOE]

    The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that...

  19. Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

    SciTech Connect (OSTI)

    Not Available

    1992-07-01T23:59:59.000Z

    Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility.

  20. METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    rights of way have been adequately established for all parts of the facility including: basic generation unit transmission

  1. 1052 IEEE TRANSACTIONS ON POWER SYSTEMS, VOL. 25, NO. 2, MAY 2010 Co-Optimization of Generation Unit Commitment

    E-Print Network [OSTI]

    Oren, Shmuel S.

    into electric network optimization models. Optimal transmission switching is a straight- forward way to leverage economics, power system reliability, power transmission control, power transmission economics. NOMENCLATURE. Generator. Set of generators at node . Transmission element (line or transformer). Set of transmission

  2. Automatic system for regulating the frequency and power of the 500 MW coal-dust power generating units at the Reftinskaya GRES

    SciTech Connect (OSTI)

    Bilenko, V. A.; Gal'perina, A. I.; Mikushevich, E. E.; Nikol'skii, D. Yu. [JSC 'Interavtomatka' (Russian Federation); Zhugrin, A. G.; Bebenin, P. A.; Syrchin, M. V. [JSC 'Reftinskaya GRES' (Russian Federation)

    2009-03-15T23:59:59.000Z

    The monitoring and control systems at the 500 MW coal-dust power generating units No. 7, 8, and 9 at the Reftinskaya GRES have been modernized using information-regulator systems. Layouts for instrumental construction of these systems and expanded algorithmic schemes for the automatic frequency and power control system and for the boiler supply and fuelling are discussed. Results from tests and normal operation of the automatic frequency and power control system are presented.

  3. POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    and Related Standards for Fossil-Fuel and Geo- thermal Powerposed Nuclear, Geothermal, and Fossil-Fuel Sites and Facili-NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN

  4. Monthly/Annual Energy Review - nuclear section

    Reports and Publications (EIA)

    2015-01-01T23:59:59.000Z

    Monthly and latest annual statistics on nuclear electricity capacity, generation, and number of operable nuclear reactors.

  5. In-Plant Reliability Data base for nuclear plant components. Interim report: diesel generators, batteries, chargers and inverters

    SciTech Connect (OSTI)

    Kahl, W.K.; Borkowski, R.J.

    1985-01-01T23:59:59.000Z

    The objective of the In-Plant Reliability Data (IPRD) program is to develop a comprehensive, component-specific reliability data base for probabilistic risk assessment and for other statistical analyses relevant to component reliability evaluations. This document is the product of a pilot study that was undertaken to demonstrate the methodology and feasibility of applying IPRDS techniques to develop and analyze the reliability characteristics of key electrical components in five nuclear power plants. These electrical components include diesel generators, batteries, battery chargers and inverters. The sources used to develop the data base and produce the component failure rates and mean repair times were the plant equipment lists, plant drawings, maintenance work requests, Final Safety Analysis Reports (FSARs), and interviews with plant personnel. The data spanned approximately 33 reactor-years of commercial operation.

  6. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L.

    1995-05-01T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  7. NEXT GENERATION SOLVENT-MATERIALS COMPATIBILITY WITH POLYMER COMPONENTS WITHIN MODULAR CAUSTIC-SIDE SOLVENT EXTRACTION UNIT (FINAL REPORT)

    SciTech Connect (OSTI)

    Fondeur, F.; Peters, T.; Fink, S.

    2012-01-17T23:59:59.000Z

    The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent for deployment at the Savannah River Site for removal of cesium from High Level Waste. The technical effort is collaboration between Oak Ridge National Laboratory (ORNL), Savannah River National Laboratory (SRNL), and Argonne National Laboratory. The first deployment target for the technology is within the Modular Caustic-Side Solvent Extraction Unit (MCU). Deployment of a new chemical within an existing facility requires verification that the chemical components are compatible with the installed equipment. In the instance of a new organic solvent, the primary focus is on compatibility of the solvent with organic polymers used in the facility. This report provides the data from exposing these polymers to the Next Generation Solvent (NGS). The test was conducted over six months. An assessment of the dimensional stability of polymers present in MCU (i.e., PEEK, Grafoil, Tefzel and Isolast) in the modified NGS (where the concentration of LIX{reg_sign}79 and MaxCalix was varied systematically) showed that LIX{reg_sign}79 selectively affected Tefzel and its different grades (by an increase in size and lowering its density). The copolymer structure of Tefzel and possibly its porosity allows for the easier diffusion of LIX{reg_sign}79. Tefzel is used as the seat material in some of the valves at MCU. Long term exposure to LIX{reg_sign}79, may make the valves hard to operate over time due to the seat material (Tefzel) increasing in size. However, since the physical changes of Tefzel in the improved solvent are comparable to the changes in the CSSX baseline solvent, no design changes are needed with respect to the Tefzel seating material. PEEK, Grafoil and Isolast were not affected by LIX{reg_sign}79 and MaxCalix within six months of exposure. The initial rapid weight gain observed in every polymer is assigned to the finite and limited uptake of Isopar{reg_sign} L/Modifier by the polymers probably due to the polymers porosity and rough surfaces. Spectroscopic data on the organic liquid and the polymer surfaces showed no preferential adsorption of any component in the NGS to the polymers and with the exception of CPVC, no leachate was observed in the NGS from any of the polymers studied. The testing shows no major concerns for compatibility over the short duration of these tests but does indicate that longer duration exposure studies are warranted, especially for Tefzel. However, the physical changes experienced by Tefzel in the improved solvent were comparable to the physical changes obtained when Tefzel is placed in CSSX baseline solvent. Therefore, there is no effect of the improved solvent beyond those observed in CSSX baseline solvent.

  8. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    Columbia University

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on Municipal Solid Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein of solid wastes and advance sustainable waste management in the U.S. to the level of several leading

  9. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

  10. Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems

    SciTech Connect (OSTI)

    Stephen M. Bruemmer; Peter L. Andersen; Gary Was

    2002-12-27T23:59:59.000Z

    The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

  11. Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Michael W. Patterson

    2008-05-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible. For integration purposes, an analysis comparing the design, cost and schedule impact of maintaining a technology neutral approach through conceptual design or making an early hydrogen process technology selection was performed. Early selection does not specifically eliminate a technology, but rather selects the first hydrogen technology for demonstration. A systems-engineering approach was taken to define decision-making criteria for selecting a hydrogen technology. The relative technical, cost and schedule risks of each approach were analyzed and risk mitigation strategies were recommended, including provisions to maintain close collaboration with the NHI. The results of these analyses are presented here.

  12. A holistic investigation of complexity sources in nuclear power plant control rooms

    E-Print Network [OSTI]

    Sasangohar, Farzan

    2011-01-01T23:59:59.000Z

    The nuclear power community in the United States is moving to modernize aging power plant control rooms as well as develop control rooms for new reactors. New generation control rooms, along with modernized control rooms, ...

  13. Nickel and Sulfur Speciation of Residual Oil Fly Ashes from Two Electric Utility Steam-Generating Units

    SciTech Connect (OSTI)

    Galbreath,K.; Schulz, R.; Toman, D.; Nyberg, C.; Huggins, F.; Huffman, G.; Zillioux, E.

    2005-01-01T23:59:59.000Z

    Representative duplicate fly ash samples were obtained from the stacks of 400- and 385-MW utility boilers (Unit A and Unit B, respectively) using a modified U.S. Environmental Protection Agency (EPA) Method 17 sampling train assembly as they burned 0.9 and 0.3 wt % S residual (No. 6 fuel) oils, respectively, during routine power plant operations. Residual oil fly ash (ROFA) samples were analyzed for Ni concentrations and speciation using inductively coupled plasma-atomic emission spectroscopy, X-ray absorption fine structure (XAFS) spectroscopy, and X-ray diffraction.

  14. KAOS/LIB-V: A library of nuclear response functions generated by KAOS-V code from ENDF/B-V and other data files

    SciTech Connect (OSTI)

    Farawila, Y.; Gohar, Y.; Maynard, C.

    1989-04-01T23:59:59.000Z

    KAOS/LIB-V: A library of processed nuclear responses for neutronics analyses of nuclear systems has been generated. The library was prepared using the KAOS-V code and nuclear data from ENDF/B-V. The library includes kerma (kinetic energy released in materials) factors and other nuclear response functions for all materials presently of interest in fusion and fission applications for 43 nonfissionable and 15 fissionable isotopes and elements. The nuclear response functions include gas production and tritium-breeding functions, and all important reaction cross sections. KAOS/LIB-V employs the VITAMIN-E weighting function and energy group structure of 174 neutron groups. Auxiliary nuclear data bases, e.g., the Japanese evaluated nuclear data library JENDL-2 were used as a source of isotopic cross sections when these data are not provided in ENDF/B-V files for a natural element. These are needed mainly to estimate average quantities such as effective Q-values for the natural element. This analysis of local energy deposition was instrumental in detecting and understanding energy balance deficiencies and other problems in the ENDF/B-V data. Pertinent information about the library and a graphical display of the main nuclear response functions for all materials in the library are given. 35 refs.

  15. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers.

    SciTech Connect (OSTI)

    Belle R. Upadhyaya; J. Wesley Hines

    2004-09-27T23:59:59.000Z

    The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001-September 2004. (1) Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. (2) Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. (3) Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. (4) Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. (5) Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. (6) Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform. (7) Implementation of a moving-window technique in the time domain for detecting and quantifying flaw types in tubular structures. A window zooming technique was also developed for flaw location in tubes. (8) Theoretical study of elastic wave propagation (longitudinal and shear waves) in metallic flat plates and tubing with and without flaws. (9) Simulation of the Lamb wave propagation using the finite-element code ABAQUS. This enabled the verification of the experimental results. The research tasks included both analytical research and experimental studies. The experimental results helped to enhance the robustness of fault monitoring methods and to provide a systematic verification of the analytical results. The results of this research were disseminated in scientific meetings. A journal manuscript was submitted for publication. The new findings of this research have potential applications in aerospace and civil structures. The report contains a complete bibliography that was developed during the course of the project.

  16. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2.

    SciTech Connect (OSTI)

    Upadhyaya, Belle R.; Hines, J. Wesley; Lu, Baofu; Huang, Xuedong; Penha, Rosani, L.; Perillo, Sergio, R.; Zhao, Ke

    2005-06-03T23:59:59.000Z

    The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001 √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬? September 2004. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. √?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬?√?¬∑ Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform

  17. POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    entry are u Table 4-6 GAS TURBINE FOR 1965-1974 (OUTAGES)AVERAGE utage Cause Code GAS TURBINE GENERATOR FORCED OUTAGEof fossil units, and for gas turbine units, the basic data

  18. Comparative analysis of United States and French nuclear power plant siting and construction regulatory policies and their economic consequences

    E-Print Network [OSTI]

    Golay, Michael Warren.

    1977-01-01T23:59:59.000Z

    Despite the substantial commitments of time and money which are devoted to the nuclear power plant siting process, the effectiveness of the system in providing a balanced evaluation of the technical, environmental and ...

  19. Proposed rulemaking on the storage and disposal of nuclear waste. Cross-statement of the United States Department of Energy

    SciTech Connect (OSTI)

    None

    1980-09-05T23:59:59.000Z

    The US DOE cross-statement in the matter of proposed rulemaking in the storage and disposal of nuclear wastes is presented. It is concluded from evidence contained in the document that: (1) spent fuel can be disposed of in a manner that is safe and environmentally acceptable; (2) present plans for establishing geological repositories are an effective and reasonable means of disposal; (3) spent nuclear fuel from licensed facilities can be stored in a safe and environmentally acceptable manner on-site or off-site until disposal facilities are ready; (4) sufficient additional storage capacity for spent fuel will be established; and (5) the disposal and interim storage systems for spent nuclear fuel will be integrated into an acceptable operating system. It was recommended that the commission should promulgate a rule providing that the safety and environmental implications of spent nuclear fuel remaining on site after the anticipated expiration of the facility licenses involved need not be considered in individual facility licensing proceedings. A prompt finding of confidence in the nuclear waste disposal and storage area by the commission is also recommeded. (DMC)

  20. Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!

    E-Print Network [OSTI]

    ! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW of solid wastes and advance sustainable waste management in the U.S. to the level of several leading-2010, the Earth Engineering Center (EEC) of Columbia University conducted a bi- annual survey on Municipal Solid

  1. Japan Atomic Energy Research Institute/United States Integral Neutronics Experiments and Analyses for tritium breeding, nuclear heating, and induced radioactivity

    SciTech Connect (OSTI)

    Abdou, M.A.; Youssef, M.; Kumar, A. [Univ. of California, Los Angeles, CA (United States)] [and others

    1995-08-01T23:59:59.000Z

    A large member of integral experiments for fusion blanket neutronics were performed using deuterium-tritium (D-T) neutrons at the Fusion Neutronics Source facility as part of a 10-yr collaborative program between the Japan Atomic Energy Research Institute and the United States. A number of measurement techniques were developed for tritium production, induced radioactivity, and nuclear heating. Transport calculations were performed using three-dimensional Monte Carlo and two-dimensional discrete ordinates codes and the latest nuclear data libraries in Japan and the United States. Significant differences among measurement techniques and calculation methods were found. To assure a 90% confidence level for tritium breeding calculations not to exceed measurements, designers should use a safety factor > 1.1 to 1.2, depending on the calculation method. Such a safety factor may not be affordable with most candidate blanket designs. Therefore, demonstration of tritium self-sufficiency is recommended as a high priority for testing in near-term fusion facilities such as the International Thermonuclear Experimental Reactor (ITER). The radioactivity measurements were performed for > 20 materials with the focus on gamma emitters with half-lives < 5 yr. Most discrepancies were attributed directly to deficiencies in the activation libraries, particularly errors in cross sections for certain reactions. 71 refs., 30 figs., 5 tabs.

  2. Modeling a Printed Circuit Heat Exchanger with RELAP5-3D for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Not Available

    2010-12-01T23:59:59.000Z

    The main purpose of this report is to design a printed circuit heat exchanger (PCHE) for the Next Generation Nuclear Plant and carry out Loss of Coolant Accident (LOCA) simulation using RELAP5-3D. Helium was chosen as the coolant in the primary and secondary sides of the heat exchanger. The design of PCHE is critical for the LOCA simulations. For purposes of simplicity, a straight channel configuration was assumed. A parallel intermediate heat exchanger configuration was assumed for the RELAP5 model design. The RELAP5 modeling also required the semicircular channels in the heat exchanger to be mapped to rectangular channels. The initial RELAP5 run outputs steady state conditions which were then compared to the heat exchanger performance theory to ensure accurate design is being simulated. An exponential loss of pressure transient was simulated. This LOCA describes a loss of coolant pressure in the primary side over a 20 second time period. The results for the simulation indicate that heat is initially transferred from the primary loop to the secondary loop, but after the loss of pressure occurs, heat transfers from the secondary loop to the primary loop.

  3. A Cargo Inspection System for Special Nuclear Material (SNM) Based on Associated Particle Neutron Generators and Liquid-Kr Detectors

    SciTech Connect (OSTI)

    Koltick, David S.; Kane, Steven Z. [Purdue University Applied Physics Laboratory 740 Navco Dr., Lafayette, IN 47906 (United States)

    2009-03-10T23:59:59.000Z

    A feasibility analysis is presented of a cargo inspection system based on neutron-induced fission followed by the coincident detection of multiple prompt fission gamma rays as a signature of Special Nuclear Material (SNM). The system does not require gamma ray spectroscopy and would be capable of distinguishing U-238 from U-235 using the ratio of signals from two modes of detection: thermal neutron capture induced fission and fast neutron-induced fission. The system utilizes two deuterium-tritium (DT) associated particle neutron generators, each capable of 10{sup 9} neutrons/s at 14.1 MeV, with sub-nanosecond timing resolution ZnO:Ga alpha detectors. The expected {approx}1 MeV prompt gamma rays are detected using liquid krypton (LKr) detectors with sub-nanosecond timing resolution ({approx}600 ps) and high detection efficiency. The expected SNM signal and randomly correlated background rates are discussed using Monte Carlo N-Particle (MCNP) code.

  4. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01T23:59:59.000Z

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  5. Virginia Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  6. Ohio Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  7. Arkansas Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  8. Michigan Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  9. Alabama Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  10. Texas Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  11. Tennessee Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  12. Georgia Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  13. Nebraska Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  14. Arizona Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  15. Maryland Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  16. Illinois Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  17. Florida Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Florida nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  18. Wisconsin Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  19. Minnesota Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  20. Southeast Regional Assessment Study: an assessment of the opportunities of solar electric power generation in the Southeastern United States

    SciTech Connect (OSTI)

    None

    1980-07-01T23:59:59.000Z

    The objective of this study was to identify and assess opportunities for demonstration and large scale deployment of solar electric facilities in the southeast region and to define the technical, economic, and institutional factors that can contribute to an accelerated use of solar energy for electric power generation. Graphs and tables are presented indicating the solar resource potential, siting opportunities, energy generation and use, and socioeconomic factors of the region by state. Solar electric technologies considered include both central station and dispersed solar electric generating facilities. Central stations studied include solar thermal electric, wind, photovoltaic, ocean thermal gradient, and biomass; dispersed facilities include solar thermal total energy systems, wind, and photovoltaic. The value of solar electric facilities is determined in terms of the value of conventional facilities and the use of conventional fuels which the solar facilities can replace. Suitable cost and risk sharing mechanisms to accelerate the commercialization of solar electric technologies in the Southeast are identified. The major regulatory and legal factors which could impact on the commercialization of solar facilities are reviewed. The most important factors which affect market penetration are reviewed, ways to accelerate the implementation of these technologies are identified, and market entry paths are identified. Conclusions and recommendations are presented. (WHK)

  1. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15

    SciTech Connect (OSTI)

    Tam, P.S.

    1995-06-01T23:59:59.000Z

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.

  2. Economics of nuclear power in Finland

    SciTech Connect (OSTI)

    Tarjanne, Risto; Luostarinen, Kari [Lappeenranta University of Technology, Department of Energy and Environmental Technology, PO Box 20, FIN-53851 Lappeenranta (Finland)

    2002-07-01T23:59:59.000Z

    The nuclear power generation fits perfectly with the long duration load profile of the Finnish power system. The good performance of the Finnish nuclear power has yielded benefits also to the consumers through its contribution to decreasing the electricity price. Furthermore, the introduction of nuclear power has resulted in a clear drop in carbon dioxide emissions from electricity generation in the shift of 1970's and 1980's. In the year 2001 the four Finnish nuclear power units at Loviisa and Olkiluoto generated 22.8 TWh electricity, equivalent to 28 per cent of the total consumption. Loviisa power station has a net output capacity of 2 x 488 MW, and Olkiluoto 2 x 840 MW. The capacity factors of the four nuclear units have been above 90 per cent, which are among the highest in the world. The energy-intensive process industries in particular have strong belief in nuclear power. In November 2000, Teollisuuden Voima company (TVO) submitted to the Finnish Government an application for decision in principle concerning the construction of a new nuclear power plant unit. The arguments were among other things to guarantee for the Finnish industry the availability of cheap electric energy and to meet the future growth of electricity consumption in Finland. The carbon-free nuclear power also represents the most efficient means to meet the Greenhouse Gas abatement quota of Finland. Simultaneously, the energy policy of the Government includes intensive R and D and investment support for the renewable energy sources and energy conservation, and the objective is also to replace coal with natural gas as much as reasonably possible. The fifth nuclear unit would be located in one of the existing Finnish nuclear sites, i.e. Olkiluoto or Loviisa. The size of the new nuclear unit would be in the range of 1000 to 1600 MW electric. The ready infrastructure of the existing site could be utilised resulting in lower investment cost for the new unit. The Finnish Government accepted the application of TVO Company on January 17, 2002, but the final word will be said by the Parliament. During the spring 2002 there will be intensive discussion on all levels, whether nuclear power is for or against 'the total benefit of the society'. The Parliament decision is expected to be made by the summer 2002. In this paper, firstly a financial comparison of the new base-load power plant alternatives is carried out in the Finnish circumstances, and secondly the actual power production costs of the existing Olkiluoto nuclear power plant based on the operating history of about 20 years will be referred. (authors)

  3. Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999

    SciTech Connect (OSTI)

    Rutherford, D.

    1994-03-01T23:59:59.000Z

    This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board`s Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department`s needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation.

  4. Some aspects of the decommissioning of nuclear power plants

    SciTech Connect (OSTI)

    Khvostova, M. S., E-mail: marinakhvostova@list.ru [St. Petersburg State Maritime Technical University (Sevmashvtuz), Severodvinsk Branch (Russian Federation)

    2012-03-15T23:59:59.000Z

    The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

  5. Walk the Line: The Development of Route Selection Standards for Spent Nuclear Fuel and High-level Radioactive Waste in the United States - 13519

    SciTech Connect (OSTI)

    Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States)] [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)] [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)] [Department of Sociology, California State University, Northridge, CA 91330 (United States)

    2013-07-01T23:59:59.000Z

    Although storage facilities for spent nuclear fuel (SNF) and high-level radioactive waste (HLRW) are widely dispersed throughout the United States, these materials are also relatively concentrated in terms of geographic area. That is, the impacts of storage occur in a very small geographic space. Once shipments begin to a national repository or centralized interim storage facility, the impacts of SNF and HLRW will become more geographically distributed, more publicly visible, and almost certainly more contentious. The selection of shipping routes will likely be a major source of controversy. This paper describes the development of procedures, regulations, and standards for the selection of routes used to ship spent nuclear fuel and high-level radioactive waste in the United States. The paper begins by reviewing the circumstances around the development of HM-164 routing guidelines. The paper discusses the significance of New York City versus the Department of Transportation and application of HM-164. The paper describes the methods used to implement those regulations. The paper will also describe the current HM-164 designated routes and will provide a summary data analysis of their characteristics. This analysis will reveal the relatively small spatial scale of the effects of HM 164. The paper will then describe subsequent developments that have affected route selection for these materials. These developments include the use of 'representative routes' found in the Department of Energy (DOE) 2008 Supplemental Environmental Impact Statement for the formerly proposed Yucca Mountain geologic repository. The paper will describe recommendations related to route selection found in the National Academy of Sciences 2006 report Going the Distance, as well as recommendations found in the 2012 Final Report of the Blue Ribbon Commission on America's Nuclear Future. The paper will examine recently promulgated federal regulations (HM-232) for selection of rail routes for hazardous materials transport. The paper concludes that while the HM 164 regime is sufficient for certain applications, it does not provide an adequate basis for a national plan to ship spent nuclear fuel and high-level radioactive waste to centralized storage and disposal facilities over a period of 30 to 50 years. (authors)

  6. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . ē . . . .

  7. Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment

    SciTech Connect (OSTI)

    Martin, G.F.; Hickey, E.E.; Moeller, M.P.; Schultz, D.H.; Bethke, G.W.

    1986-03-01T23:59:59.000Z

    A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

  8. INSTRUCTIONS FOR SUBMITTING NUCLEAR

    E-Print Network [OSTI]

    waste management proceedings. Keywords Nuclear, nuclear power plant, spent fuel, nuclear waste, data of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C. Spent Nuclear Fuel Storage 9 D. Spent Nuclear Fuel Transport and Disposal Issues 10 E. Interim Spent

  9. The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12) Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    DOMAIN SIMULATIONS FOR THE TWO-PHASE FLOW ENERGY BALANCE OF THE CLOTAIRE STEAM GENERATOR MOCK-UP Michel computation of the energy balance equation of a nuclear component. Considering the steam generator Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburg, Pennsylvania : United States (2007

  10. Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU (Korea Nuclear Unit) No. 1 Plant

    SciTech Connect (OSTI)

    Chung, Bud-Dong; Kim, Hho-Jung (Korea Advanced Energy Research Inst., Daeduk-Danji (Republic of Korea). Korea Nuclear Safety Center); Lee, Young-Jin (Seoul National Univ. (Republic of Korea))

    1990-04-01T23:59:59.000Z

    This report presents a code assessment study based on a real plant transient that occurred on June 9, 1981 at the KNU {number sign}1 (Korea Nuclear Unit Number 1). KNU {number sign}1 is a two-loop Westinghouse PWR plant of 587 Mwe. The loss of offsite power transient occurred at the 77.5% reactor power with 0.5%/hr power ramp. The real plant data were collected from available on-line plant records and computer diagnostics. The transient was simulated by RELAP5/MOD2/36.05 and the results were compared with the plant data to assess the code weaknesses and strengths. Some nodalization studies were performed to contribute to developing a guideline for PWR nodalization for the transient analysis. 5 refs., 18 figs., 3 tabs.

  11. Environmental Assessment for DOE permission for off-loading activities to support the movement of Millstone Unit 2 steam generator sub-assemblies across the Savannah River Site

    SciTech Connect (OSTI)

    Not Available

    1992-10-01T23:59:59.000Z

    The Department of Energy (DOE) has prepared an Environmental Assessment (EA), for the proposed granting of DOE permission of offloading activities to support the movement Millstone Unit 2 steam generator sub-assemblies (SGSAs) across the Savannah River Site (SRS). Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an environmental impact statement is not required, and the Department is issuing this Finding of No Significant Impact. On the basis of the floodplain/wetlands assessment in the EA, DOE has determined that there is no practicable alternative to the proposed activities and that the proposed action has been designed to minimize potential harm to or within the floodplain of the SRS boat ramp. No wetlands on SRS would be affected by the proposed action.

  12. United States-Russian laboratory-to-laboratory cooperation on protection, control, and accounting for naval nuclear materials

    SciTech Connect (OSTI)

    Sukhoruchkin, V. [Kurchatov Inst., Moscow (Russian Federation); Yurasov, N.; Goncharenko, Y. [Russian Navy, Moscow (Russian Federation); Mullen, M. [Los Alamos National Lab., NM (United States); McConnell, D. [Sandia National Labs., Albuquerque, NM (United States)

    1996-12-31T23:59:59.000Z

    In March 1995, the Russian Navy contacted safeguards experts at the Kurchatov Institute (KI) and proposed the initiation of work to enhance nuclear materials protection, control, and accounting (MPC and A) at Russian Navy facilities. Because of KI`s successful experience in laboratory-to-laboratory MPC and A cooperation with US Department of Energy Laboratories, the possibility of US participation in the work with the Russian Navy was explored. Several months later, approval was received from the US Government and the Russian Navy to proceed with this work on a laboratory-to-laboratory basis through Kurchatov Institute. As a first step in the cooperation, a planning meeting occurred at KI in September, 1995. Representatives from the US Department of Energy (DOE), the US Department of Defense (DOD), the Russian Navy, and KI discussed several areas for near-term cooperative work, including a vulnerability assessment workshop and a planning study to identify and prioritize near-term MPC and A enhancements that might be implemented at Russian facilities which store or handle unirradiated highly enriched uranium fuel for naval propulsion applications. In subsequent meetings, these early proposals have been further refined and extended. This MPC and A cooperation will now include enhanced protection and control features for storage facilities and refueling service ships, computerized accounting systems for naval fuel, methods and equipment for rapid inventories, improved security of fresh fuel during truck transportation, and training. This paper describes the current status and future plans for MPC and A cooperation for naval nuclear materials.

  13. Global Nuclear Energy Partnership Programmatic Environmental Impact Statement

    SciTech Connect (OSTI)

    R.A. Wigeland

    2008-10-01T23:59:59.000Z

    Abstract: The proposed Global Nuclear Energy Partnership (GNEP) Program, which is part of the Presidentís Advanced Energy Initiative, is intended to support a safe, secure, and sustainable expansion of nuclear energy, both domestically and internationally. Domestically, the GNEP Program would promote technologies that support economic, sustained production of nuclear-generated electricity, while reducing the impacts associated with spent nuclear fuel disposal and reducing proliferation risks. The Department of Energy (DOE) proposed action envisions changing the United States nuclear energy fuel cycle from an open (or once-through) fuel cycleóin which nuclear fuel is used in a power plant one time and the resulting spent nuclear fuel is stored for eventual disposal in a geologic repositoryóto a closed fuel cycle in which spent nuclear fuel would be recycled to recover energy-bearing components for use in new nuclear fuel. At this time, DOE has no specific proposed actions for the international component of the GNEP Program. Rather, the United States, through the GNEP Program, is considering various initiatives to work cooperatively with other nations. Such initiatives include the development of grid-appropriate reactors and the development of reliable fuel services (to provide an assured supply of fresh nuclear fuel and assist with the management of the used fuel) for nations who agree to employ nuclear energy only for peaceful purposes, such as electricity generation.

  14. Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 4: High-Temperature Materials PIRTs

    SciTech Connect (OSTI)

    Corwin, William R [ORNL; Ballinger, R. [Massachusetts Institute of Technology (MIT); Majumdar, S. [Argonne National Laboratory (ANL); Weaver, K. D. [Idaho National Laboratory (INL)

    2008-03-01T23:59:59.000Z

    The Phenomena Identification and Ranking Table (PIRT) technique was used to identify safety-relevant/safety-significant phenomena and assess the importance and related knowledge base of high-temperature structural materials issues for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled reactor (VHTR). The major aspects of materials degradation phenomena that may give rise to regulatory safety concern for the NGNP were evaluated for major structural components and the materials comprising them, including metallic and nonmetallic materials for control rods, other reactor internals, and primary circuit components; metallic alloys for very high-temperature service for heat exchangers and turbomachinery, metallic alloys for high-temperature service for the reactor pressure vessel (RPV), other pressure vessels and components in the primary and secondary circuits; and metallic alloys for secondary heat transfer circuits and the balance of plant. These materials phenomena were primarily evaluated with regard to their potential for contributing to fission product release at the site boundary under a variety of event scenarios covering normal operation, anticipated transients, and accidents. Of all the high-temperature metallic components, the one most likely to be heavily challenged in the NGNP will be the intermediate heat exchanger (IHX). Its thin, internal sections must be able to withstand the stresses associated with thermal loading and pressure drops between the primary and secondary loops under the environments and temperatures of interest. Several important materials-related phenomena related to the IHX were identified, including crack initiation and propagation; the lack of experience of primary boundary design methodology limitations for new IHX structures; and manufacturing phenomena for new designs. Specific issues were also identified for RPVs that will likely be too large for shop fabrication and transportation. Validated procedures for on-site welding, post-weld heat treatment (PWHT), and inspections will be required for the materials of construction. High-importance phenomena related to the RPV include crack initiation and subcritical crack growth; field fabrication process control; property control in heavy sections; and the maintenance of high emissivity of the RPV materials over their service lifetime to enable passive heat rejection from the reactor core. All identified phenomena related to the materials of construction for the IHX, RPV, and other components were evaluated and ranked for their potential impact on reactor safety.

  15. Shutdown and low-power operation at commercial nuclear power plants in the United States. Final report

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The report contains the results of the NRC Staff`s evaluation of shutdown and low-power operations at US commercial nuclear power plants. The report describes studies conducted by the staff in the following areas: Operating experience related to shutdown and low-power operations, probabilistic risk assessment of shutdown and low-power conditions and utility programs for planning and conducting activities during periods the plant is shut down. The report also documents evaluations of a number of technical issues regarding shutdown and low-power operations performed by the staff, including the principal findings and conclusions. Potential new regulatory requirements are discussed, as well as potential changes in NRC programs. A draft report was issued for comment in February 1992. This report is the final version and includes the responses to the comments along with the staff regulatory analysis of potential new requirements.

  16. Confirmation of the seismic resistance of nuclear power plant equipment after assembly

    SciTech Connect (OSTI)

    Kaznovsky, P. S.; Kaznovsky, A. P.; Saakov, E. S.; Ryasnyj, S. I. [JSC 'Atomtehenergo' (Russian Federation)

    2013-05-15T23:59:59.000Z

    It is shown that the natural frequencies and damping decrements of nuclear power plant equipment can only be determined experimentally and directly at the power generation units (reactors) of nuclear power plants under real disassembly conditions for the equipment, piping network, thermal insulation, etc. A computational experimental method is described in which the natural frequencies and damping decrements are determined in the field and the seismic resistance is reevaluated using these values. This method is the basis of the standards document 'Methods for confirming the dynamic characteristics of systems and components of the generating units of nuclear power plants which are important for safety' prepared and introduced in 2012.

  17. Energy Management in Olefins Units

    E-Print Network [OSTI]

    Wells, T. A.

    1982-01-01T23:59:59.000Z

    to the point where waste heat from pyrolysis generates more than enough steam to power the olefins unit recovery section. Furthermore, incorporating gas turbine driven electrical generators or process compressors adds to the utility export potential of the unit...

  18. Energy Management in Olefins Units

    E-Print Network [OSTI]

    Wells, T. A.

    1982-01-01T23:59:59.000Z

    to the point where waste heat from pyrolysis generates more than enough steam to power the olefins unit recovery section. Furthermore, incorporating gas turbine driven electrical generators or process compressors adds to the utility export potential of the unit...

  19. Inventory of Power Plants in the United States, October 1992

    SciTech Connect (OSTI)

    Not Available

    1993-10-27T23:59:59.000Z

    The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. The report is organized into the following chapters: Year in Review, Operable Electric Generating Units, and Projected Electric Generating Unit Additions. Statistics presented in these chapters reflect the status of electric generating units as of December 31, 1992.

  20. Inventory of power plants in the United States 1989. [Contains glossary

    SciTech Connect (OSTI)

    Not Available

    1990-09-21T23:59:59.000Z

    This document is prepared annually by the Electric Power Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units in operation and to provide a 10-year outlook of future generating unit additions by electric utilities in the United States (the 50 states and the District of Columbia). Data summarized in this report are useful to a wide audience including Congress, federal and state agencies, the electric utility industry, and the general public. The data presented in this report were assembled and published by the EIA, to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. The report is organized into the following chapters: Summary Statistics; Operable Electric Generating Units; and Projected Electric Generating Unit Additions.

  1. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors

    E-Print Network [OSTI]

    Terrani, Kurt Amir

    2010-01-01T23:59:59.000Z

    electricity generation capacity and operating efficiency of nuclear plants [Nuclear Plant Capacity Factor Nuclear Electricity Generationelectricity generation capacity and operating efficiency of nu- clear plants [

  2. Environmental assessment for the manufacture and shipment of nuclear reactor fuel from the United States to Canada

    SciTech Connect (OSTI)

    Rangel, R.C.

    1999-02-01T23:59:59.000Z

    The US Department of Energy (DOE) has declared 41.9 tons (38 metric tons) of weapons-usable plutonium surplus to the United States` defense needs. A DOE Programmatic Environmental Impact Statement analyzed strategies for plutonium storage and dispositioning. In one alternative, plutonium as a mixed oxide (MOX) fuel would be irradiated (burned) in a reengineered heavy-water-moderated reactor, such as the Canadian CANDU design. In an Environmental Assessment (EA), DOE proposes to fabricate and transport to Canada a limited amount of MOX fuel as part of the Parallex (parallel experiment) Project. MOX fuel from the US and Russia would be used by Canada to conduct performance tests at Chalk River Laboratories. MOX fuel would be fabricated at Los Alamos National Laboratory and transported in approved container(s) to a Canadian port(s) of entry on one to three approved routes. The EA analyzes the environmental and human health effects from MOX fuel fabrication and transportation. Under the Proposed Action, MOX fuel fabrication would not result in adverse effects to the involved workers or public. Analysis showed that the shipment(s) of MOX fuel would not adversely affect the public, truck crew, and environment along the transportation routes.

  3. A compilation of the electricity generated and low-level radioactive wastes shipped for disposal by US nuclear power plants, 1959-1985

    SciTech Connect (OSTI)

    Kibbey, A.H.; DePaoli, S.M.

    1987-12-01T23:59:59.000Z

    The LWRDATA data base contains both volume and radioactivity data on nearly all the low-level radioactive waste (LLW) shipments from commercial boiling-water reactor (BWR) and pressurized-water reactor (PWR) nuclear power plants from 1959 through 1985. The corresponding net electrical output is also included in the data base. This report compares the various physical forms of LLW (i.e., wet; dry, compressible; irradiated, non-fuel core component; and miscellaneous) generated by BWR and PWR plants on the basis of their annual net electricity generation. Further comparisons are made of three specific categories of BWRs based on their size and condensate polishing systems: (1) small deep-bed plants, (2) large deep-bed plants, and (3) filter-demineralizer plants. The various types and volumes of PWR wastes generated per net megawatt (electrical)-year are also compared by nuclear steam supply system manufacturer. Limitations of the available data are discussed. 25 refs., 30 figs., 5 tabs.

  4. Repowering of the Midland Nuclear Station

    E-Print Network [OSTI]

    Gatlin, C. E. Jr.; Vellender, G. C.; Mooney, J. A.

    natural gas-fired cx:rnbined~cle plant ~~on utilized the original Midland Unit 1 steam turb~ am 12 gas t:w:bine heat recovery trains to prov de 1,165 MW of generatin;J capacity. 'Ihi.s ~ on included a staged approach to stagger availability of the ad... the largest cogeneration facility in the United States. The paper describes the project and the converted facility. 'Ibe Midland Cogeneration Plant started as a 2-unit nuclear-powered electric generating station supplyin;J cogenerated steam to an adjacent...

  5. Nuclear Operations Application to Environmental Restoration at Corrective Action Unit 547, Miscellaneous Contaminated Waste Sites, at the Nevada National Security Site

    SciTech Connect (OSTI)

    Kevin Cabble (NSO), Mark Krauss and Patrick Matthews (N-I)

    2011-03-03T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has responsibility for environmental restoration at the Nevada National Security Site (formerly the Nevada Test Site). This includes remediation at locations where past testing activities have resulted in the release of plutonium to the environment. One of the current remediation efforts involves a site where an underground subcritical nuclear safety test was conducted in 1964. The underground test was vented through a steel pipe to the surface in a closed system where gas samples were obtained. The piping downstream of the gas-sampling apparatus was routed belowground to a location where it was allowed to vent into an existing radioactively contaminated borehole. The length of the pipe above the ground surface is approximately 200 meters. This pipe remained in place until remediation efforts began in 2007, at which time internal plutonium contamination was discovered. Following this discovery, an assessment was conducted to determine the quantity of plutonium present in the pipe. This site has been identified as Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites. The quantity of plutonium identified at CAU 547 exceeded the Hazard Category 3 threshold but was below the Hazard Category 2 threshold specified in DOE Standard DOE-STD-1027-92. This CAU, therefore, was initially categorized as a Hazard Category 3 environmental restoration site. A contaminated facility or site that is initially categorized as Hazard Category 3, however, may be downgraded to below Hazard Category 3 if it can be demonstrated through further analysis that the form of the material and the energy available for release support reducing the hazard category. This is an important consideration when performing hazard categorization of environmental restoration sites because energy sources available for release of material are generally fewer at an environmental restoration site than at an operating facility and environmental restoration activities may result in the complete removal of source material.

  6. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    DENSITIES AROUND CALIFORNIA NUCLEAR POWER PLANT. le Iil _. .AROUND CALIFORNIA NUCLEAR POWER PLANTS Miles San OnofreIN CALIFORNIA The California Nuclear Power Plant Emergency

  7. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    from the Rancho Seco nuclear plant was simulated, A total ofdistributions around the nuclear plant sites based on thegrowth surrounding nuclear plants after the issuance of the

  8. CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, jA.V.

    2010-01-01T23:59:59.000Z

    surrounding a nuclear plant, and they are stronglylocation for a nuclear plant, but it is the measures thatand consequences of nuclear plant accidents and would match

  9. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    S. Commercial Nuclear Power Plants. WASH-1400. October 1975.Content of for Nuclear Power Plants. Regulatory Guide 1.101.PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESS

  10. Activation cross sections of $?$-particle induced nuclear reactions on hafnium and deuteron induced nuclear reaction on tantalum: production of $^{178}$W/$^{178m}$Ta generator

    E-Print Network [OSTI]

    F. TŠrk'anyi; S. Tak'acs; F. Ditrůi; A. Hermanne; A. V. Ignatyuk; M. S. Uddin

    2014-12-01T23:59:59.000Z

    In the frame of a systematic study of charged particle production routes of medically relevant radionuclei, the excitation function for indirect production of $^{178m}$Ta through $^{nat}$Hf($\\alpha$,xn)$^{178}$W-$^{178m}$Ta nuclear reaction was measured for the first time up to 40 MeV. In parallel, the side reactions $^{nat}$Hf($\\alpha$,x)$^{179,177,176,175}$W, $^{183,182,178g,177,176,175}$Ta, $^{179m,177m,175}$Hf were also assessed. Stacked foil irradiation technique and $\\gamma$-ray spectrometry were used. New experimental cross section data for the $^{nat}$Ta(d,xn)$^{178}$W reaction are also reported up to 40 MeV. The measured excitation functions are compared with the results of the ALICE-IPPE, and EMPIRE nuclear reaction model codes and with the TALYS 1.4 based data in the TENDL-2013 library. The thick target yields were deduced and compared with yields of other charged particle ((p,4n), (d,5n) and ($^3$He,x)) production routes for $^{178}$W.

  11. Supporting Our Nation's Nuclear Industry

    ScienceCinema (OSTI)

    Lyons, Peter

    2013-05-29T23:59:59.000Z

    On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

  12. Resergence of U.S. Nuclear Power

    SciTech Connect (OSTI)

    none

    2006-02-15T23:59:59.000Z

    Over the past quarter century, things have not gone well for the nuclear industry. First came the Three Mile Island accident in America in 1979, then the disaster at the Chernobyl plant in Ukraine in 1986. In Japan, Tokyo Electric Power, the world's largest private electricity company, shut its 17 nuclear reactors after it was caught falsifying safety records to hide cracks at some of its plants in 2002. In addition, the attacks on September 11, 2001 were a sharp reminder that the risks of nuclear power generation were not only those inherent in the technology. But lately, prospects have brightened for the nuclear industry. Nuclear power is an important source of electricity in many countries. In 2003, 19 countries depended on nuclear power for at least 20 percent of their electricity generation. As of March 2005, there were 441 nuclear power reactors in operation around the world, and another 25 were under construction. Five new nuclear power plants began operation in 2004 - one each in China, Japan, and Russia and two in Ukraine. In addition, Canada?s Bruce 3 reactor was reconnected to the grid. Five nuclear power plants were permanently shut down in 2004 - one in Lithuania and four in the United Kingdom. Nuclear power is expected to see a revival in the next decade given the availability of uranium and the prospect of emission-free power generation, Also, with conventional energy sources such as oil and gas likely to see severe depletion over the next 30 years, the price of conventional power generation is set to rise significantly, which would put nuclear power generation in focus again. The report provides an overview of the opportunities for nuclear power in the U.S. electric industry and gives a concise look at the challenges faced by nuclear power, the ability of advanced nuclear reactors to address these challenges, and the current state of nuclear power generation. Topics covered in the report include: an overview of U.S. Nuclear Power including its history, the current market environment, and the future of nuclear power in the U.S.; an analysis of the key business factors that are driving renewed interest in nuclear power; an analysis of the barriers that are hindering the implementation of new nuclear power plants; a description of nuclear power technology including existing reactors, as well as 3rd and 4th generation reactor designs; a review of the economics of new nuclear power projects and comparison to other generation alternatives; a discussion of the key government initiatives supporting nuclear power development; profiles of the key reactor manufacturers participating in the U.S. nuclear power market; and, profiles of the leading U.S. utilities participating in the U.S. nuclear power market.

  13. LETTER REPORT. INDEPENDENT CONFIRMATORY SURVEY RESULTS OF SOILS ASSOCIATED WITH THE ARGYLE STREET SEWER LINE AT THE UNITED NUCLEAR CORPORATION NAVAL PRODUCTS SITE, NEW HAVEN, CONNECTICUT

    SciTech Connect (OSTI)

    Adams, Wade C.

    2012-01-24T23:59:59.000Z

    Oak Ridge Institute for Science and Education (ORISE) personnel visited the United Nuclear Corporation (UNC) Naval Products site on three separate occasions during the months of October and November 2011. The purpose of these visits was to conduct confirmatory surveys of soils associated with the Argyle Street sewer line that was being removed. Soil samples were collected from six different, judgmentally determined locations in the Argyle Street sewer trench. In addition to the six soil samples collected by ORISE, four replicate soil samples were collected by Cabrera Services, Inc. (CSI) for analysis by the ORISE laboratory. Replicate samples S0010 and S0011 were final status survey (FSS) bias samples; S0012 was an FSS systematic sample; and S0015 was a waste characterization sample. Six soil samples were also collected for background determination. Uranium-235 and uranium-238 concentrations were determined via gamma spectroscopy; the spectra were also reviewed for other identifiable photopeaks. Radionuclide concentrations for these soil samples are provided. In addition to the replicate samples and the samples collected by ORISE, CSI submitted three soil samples for inter-laboratory comparison analyses. One sample was from the background reference area, one was from waste characterization efforts (material inside the sewer line), and one was a FSS sample. The inter-laboratory comparison analyses results between ORISE and CSI were in agreement, except for one sample collected in the reference area. Smear results For Argyle Street sewer pipes are tabulated.

  14. Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect (OSTI)

    Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

    1993-06-01T23:59:59.000Z

    Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen.

  15. North Carolina Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  16. New Jersey Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  17. New York Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

  18. Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory

    SciTech Connect (OSTI)

    S.G. Johnson; K.L. Lively; C.C. Dwight

    2014-07-01T23:59:59.000Z

    Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administrationís Mars Science Laboratory, which launched in November of 2011.

  19. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1

    SciTech Connect (OSTI)

    BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

    2003-12-01T23:59:59.000Z

    OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

  20. Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report

    SciTech Connect (OSTI)

    NONE

    1993-12-31T23:59:59.000Z

    The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

  1. Inventory of power plants in the United States, 1993

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), U.S. Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

  2. Inventory of power plants in the United States 1994

    SciTech Connect (OSTI)

    NONE

    1995-10-18T23:59:59.000Z

    The Inventory of Power Plants in the US provides year-end statistics on generating units operated by electric utilities in the US (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of December 31, 1994. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress, Federal, and State agencies; the electric utility industry; and the general public. This is a report of electric utility data; in cases where summary data of nonutility capacity are presented, it is specifically noted as such.

  3. Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems

    SciTech Connect (OSTI)

    Nagy, Peter

    2013-09-30T23:59:59.000Z

    The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV materials. Through the results obtained from this integrated materials behavior and NDE study, new insight will be gained into the best nondestructive creep and microstructure monitoring methods for the particular mechanisms identified in these materials. The proposed project includes collaboration with a national laboratory partner and the results will also serve as a foundation to guide the efforts of scientists in the DOE laboratory, university, and industrial communities concerned with the technological challenges of monitoring creep and microstructural evolution in materials planned to be used in Generation IV Nuclear Energy Systems.

  4. Inventory of power plants in the United States as of January 1, 1996

    SciTech Connect (OSTI)

    NONE

    1996-12-01T23:59:59.000Z

    The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1996. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 as amended.

  5. Inventory of power plants in the United States as of January 1, 1997

    SciTech Connect (OSTI)

    NONE

    1997-12-01T23:59:59.000Z

    The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1997. The publication also provides a 10-yr outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

  6. Energy Praises the Nuclear Regulatory Commission Approval of...

    Energy Savers [EERE]

    Energy Praises the Nuclear Regulatory Commission Approval of the First United States Nuclear Plant Site in Over 30 Years Energy Praises the Nuclear Regulatory Commission Approval...

  7. Department of Energy Awards $15 Million for Nuclear Fuel Cycle...

    Energy Savers [EERE]

    nuclear fuel cycle technology development, meet the need for advanced nuclear energy production and help to close the nuclear fuel cycle in the United States. "Today's awards...

  8. Verification of voltage/frequency requirement for emergency diesel generator in nuclear power plant using dynamic modeling

    SciTech Connect (OSTI)

    Hur, Jin-Suk; Roh, Myung- Sub [KEPCO International Nuclear Graduate School, 1456-1 Shinam-ri, Seosaeng-myeon, Ulju-gun, Ulsan, 689-882 (Korea, Republic of)

    2014-02-12T23:59:59.000Z

    One major cause of the plant shutdown is the loss of electrical power. The study is to comprehend the coping action against station blackout including emergency diesel generator, sequential loading of safety system and to ensure that the emergency diesel generator should meet requirements, especially voltage and frequency criteria using modeling tool. This paper also considered the change of the sequencing time and load capacity only for finding electrical design margin. However, the revision of load list must be verified with safety analysis. From this study, it is discovered that new load calculation is a key factor in EDG localization and in-house capability increase.

  9. UNITED STATES NUCLEAR REGULATORY COMMISSION

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7 AugustAFRICAN3uj: ;;IDEC. i' ,' ,'

  10. Closing the circle on the splitting of the atom: The environmental legacy of nuclear weapons production in the United States and what the Department of Energy is doing about it

    SciTech Connect (OSTI)

    NONE

    1996-01-01T23:59:59.000Z

    In the grand scheme of things we are a little more than halfway through the cycle of splitting the atom for weapons purposes. If we visualize this historic cycle as the full sweep of a clockface, at zero hour we would find the first nuclear chain reaction by Enrico Fermi, followed immediately by the Manhattan Project and the explosion of the first atomic bombs. From two o`clock until five, the United States built and ran a massive industrial complex that produced tens of thousands of nuclear weapons. At half past, the Cold War ended, and the United States shut down most of its nuclear weapons factories. The second half of this cycle involves dealing with the waste and contamination from nuclear weapons production - a task that had, for the most part, been postponed into the indefinite future. That future is now upon us. Dealing with the environmental legacy of the Cold War is in many ways as big a challenge for us today as the building of the atomic bomb was for the Manhattan Project pioneers in the 1940s. Our challenges are political and social as well as technical, and we are meeting those challenges. We are reducing risks, treating wastes, developing new technologies, and building democratic institutions for a constructive debate on our future course.

  11. The harmony between nuclear reactions and nuclear reactor structures and systems

    SciTech Connect (OSTI)

    Popa-Simil, L. [LAVM LLC, Los Alamos, NM (United States)

    2012-07-01T23:59:59.000Z

    Advanced nuclear energy is one extremely viable approach for achieving the required goals. With its extraordinarily high energy density (both, per unit mass and per unit volume), it produces over seven orders of magnitude less waste than fossil fuels per unit of energy generated. Applying nano-technologies to nuclear reactors could potentially produce the extraordinary performance required. The actual nuclear reactors lack of performances, the complexity and hazard of the fuel cycle are in part due to the lack of understanding of the nature's laws related to energy distribution applied to fission products, and in part to the current technologic capabilities that make the economical optimum. In order to produce the desired increase of performances a novel multi-scale multi-physics and engineering approach have been developed, starting from the nuclear reactions involved, analyzing in detail the key features and requirements of the 'key players' in the process (neutrons, compound nucleus, fission products, transmutation products, decay radiation), the consequences of their interaction with matter. That complex interaction generates new reactions and new key-players (knock-on electrons, photons, phonons) that further interact with the matter represented by the nuclear fuel, cladding, cooling agents, structural materials and control systems. The understanding of this complexity of problems from fm-ps scale up to macro-system and mitigating all the requirements drives to that desired harmony that provides a safe energy delivery. (authors)

  12. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750Ė800įC Reactor Outlet Temperature

    SciTech Connect (OSTI)

    John Collins

    2009-08-01T23:59:59.000Z

    This document presents the NGNP Critical PASSCs and defines their technical maturation path through Technology Development Roadmaps (TDRMs) and their associated Technology Readiness Levels (TRLs). As the critical PASSCs advance through increasing levels of technical maturity, project risk is reduced and the likelihood of within-budget and on-schedule completion is enhanced. The current supplier-generated TRLs and TDRMs for a 750Ė800įC reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

  13. Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

    SciTech Connect (OSTI)

    Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Peddicord, K.L. [Texas A and M Univ., College Station, TX (United States); Witmer, F.E.; Krumpe, P.F. [USDOE, Washington, DC (United States); Lazarev, L.; Moshkov, M. [Radievyj Inst., Leningrad (Russian Federation)

    1997-04-09T23:59:59.000Z

    The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment.

  14. GET TO KNOW National Nuclear Science Week

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    from 104 operating reactors across the United States. Nearly half of South Carolina's electricity and one-fourth of Georgia's electric power come from nuclear energy. Nuclear...

  15. CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, jA.V.

    2010-01-01T23:59:59.000Z

    Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

  16. CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, jA.V.

    2010-01-01T23:59:59.000Z

    Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

  17. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro`s Bruce nuclear generating station {open_quotes}A{close_quotes}

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L. [ADTECHS Corporation, Herndon, VA (United States)

    1994-12-31T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station {open_quotes}A{close_quotes} has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  18. Some policy implications of nuclear winter

    SciTech Connect (OSTI)

    Gertler, J.J.

    1985-01-01T23:59:59.000Z

    The theory of nuclear winter has had as checkered a history as any new idea since Darwin published The Origin of Species. There have been questions of its scientific validity, reviews both laudatory and damning, pleas for arms reductions, hosannahs for a newfound hope that nuclear war has at least been rendered completely unthinkable, and frustration that two generations of human toil in weapons laboratories and think tanks have been rendered by a natural doomsday machine. Some have even suggested that nuclear winter might be used as an offensive weapon. Disturbingly, a substantial number of commentators have concluded that nuclear winter carries no immediate implications for policy, because to their way of thinking, nuclear winter is a (a) just one more of the many undesirable effects of nuclear war; (b) the ulimate deterrent to nuclear use, and therefore should be welcomed rather than compensated for; or (c) an unproven theory, meaning that consideration of policy questions is premature. Those who overlook the policy questions are following a dangerous path. The nuclear winter theory contains serious short- and long-term implications for United States foreign and strategic policy. Although the theory may never be confirmed or refuted, discussion of these policy questions should begin now because many of the potential effects of nuclear winter - particularly in foreign policy - will come about regardless of whether or not the phenomenon can actually exist.

  19. REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198

    SciTech Connect (OSTI)

    Lowry, N.

    2010-11-05T23:59:59.000Z

    Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste. Allowable options must be evaluated carefully in order to reduce compliance risks, protect personnel, limit potential negative impacts on facility operations, and minimize the generation of wastes subject to TSCA. This paper will identify critical factors in selecting the appropriate TSCA regulatory path in order to minimize the generation of radioactive PCB waste and reduce negative impacts to facilities. The importance of communicating pertinent technical issues with facility staff, regulatory personnel, and subsequently, the public, will be discussed. Key points will be illustrated by examples from five former production reactors at the DOE Savannah River Site. In these reactors a polyurethane sealant was used to seal piping penetrations in the biological shield walls. During the intense neutron bombardment that occurred during reactor operation, the sealant broke down into a thick, viscous material that seeped out of the piping penetrations over adjacent equipment and walls. Some of the walls were painted with a PCB product. PCBs from the paint migrated into the degraded sealant, creating PCB 'spill areas' in some of these facilities. The regulatory cleanup approach selected for each facility was based on its operational status, e.g., active, inactive or undergoing decommissioning. The selected strategies served to greatly minimize the generation of radioactive liquid PCB waste. It is expected that this information would be useful to other DOE sites, DOD facilities, and commercial nuclear facilities constructed prior to the 1979 TSCA ban on most manufacturing and uses of PCBs.

  20. Effect on the condition of the metal in A K-300-3.5 turbine owing to multicycle fatigue from participation of a power generating unit in grid frequency and power regulation

    SciTech Connect (OSTI)

    Lebedeva, A. I.; Zorchenko, N. V.; Prudnikov, A. A.

    2011-09-15T23:59:59.000Z

    The effect on the condition of the rotor material owing to multicycle fatigue caused by variable stresses during participation of a power generating unit in grid frequency and power regulation is evaluated using the K-300-23.5 steam turbine as an example. It is shown that during normalized primary frequency regulation the safety factor is at least 50, while during automatic secondary regulation of frequency and power there is essentially no damage to the metal.

  1. Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems - Final Report , Project 99-0280

    SciTech Connect (OSTI)

    Bruemmer, Stephen M.; Simonen, Edward P.; Gan, Jian; Garner, Francis A.; Gelles, David S.; Edwards, Danny J.; Andresen, Peter L.; Young, Lisa M.; Was, Gary S.; Fournier, L.; Sencer, Bulent H.

    2002-12-27T23:59:59.000Z

    The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

  2. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model

    SciTech Connect (OSTI)

    Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

    2013-02-01T23:59:59.000Z

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system , and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity.

  3. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413

    SciTech Connect (OSTI)

    Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

    2013-07-01T23:59:59.000Z

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

  4. Louisiana Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant NameTotal Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

  5. Innovations in Nuclear Infrastructure and Education

    SciTech Connect (OSTI)

    John Bernard

    2010-12-13T23:59:59.000Z

    The decision to implement the Innovation in Nuclear Infrastructure and Engineering Program (INIE) was an important first step towards ensuring that the United States preserves its worldwide leadership role in the field of nuclear science and engineering. Prior to INIE, university nuclear science and engineering programs were waning, undergraduate student enrollment was down, university research reactors were being shut down, while others faced the real possibility of closure. For too long, cutting edge research in the areas of nuclear medicine, neutron scattering, radiochemistry, and advanced materials was undervalued and therefore underfunded. The INIE program corrected this lapse in focus and direction and started the process of drawing a new blueprint with positive goals and objectives that supports existing as well the next generation of educators, students and researchers.

  6. California Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    California nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

  7. Pennsylvania Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Pennsylvania nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

  8. Connecticut Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

  9. NUCLEAR PLANT OPERATIONS AND

    E-Print Network [OSTI]

    DemaziŤre, Christophe

    NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed absorption cross-section behavior. Consequently, if NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;DemaziŤre

  10. NUCLEAR PLANT OPERATIONS AND

    E-Print Network [OSTI]

    PŠzsit, Imre

    NUCLEAR PLANT OPERATIONS AND CONTROL KEYWORDS: moderator temper- ature coefficient, reactivity co reactor Unit 4 of the Ringhals Nuclear Power Plant (Sweden) during fuel cycle 16 is analyzed. Consequently, if*E-mail: demaz@nephy.chalmers.se NUCLEAR TECHNOLOGY VOL. 140 NOV. 2002 147 #12;high-burnup fuel

  11. Joint electric power alternatives study. Appendix G. Joint parallel nuclear alternatives study for Russia. Final report

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Joint Parallel Nuclear Alternatives Study for Russia (JPNAS) is a parallel study to the Joint Electric Power Alternatives Study (JEPAS). The JPNAS assessed the costs of enhancing the safety level of Russian nuclear power plants (NPPs), decommissioning of RBMK-1000 and first generation VVER-440 units, completion of NPP construction, NPP repowering into fossil fuel plants, and construction of new generation NPPs. In the framework of the JEPAS, the JPNAS provides data on the nuclear sector which is needed to formulate an integrated resources plan and schedule for investments for the development of Russia`s power sector.

  12. GENERATION OF ELECTRIC Hesham E. Shaalan

    E-Print Network [OSTI]

    Powell, Warren B.

    exhaust gases are delivered to a heat-recovery steam generator to produce steam that is used to drive.1 Optimum Electric-Power Generating Unit . . . . . . . . . . . . . . . . . . . . . . 8.7 Annual Capacity.21 Hydropower Generating Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.23 Largest Units

  13. United States Atomic Energy Commission formed

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    weapons problem, the United States worked to establish its own formal organization. The transition from military civilian control of nuclear energy was defined in the Atomic...

  14. Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

    SciTech Connect (OSTI)

    Starodubtsev, G.S.; Prishchepov, A.I.; Zatorsky, Y.M.; James, L.T. [and others

    1997-11-01T23:59:59.000Z

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

  15. Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

    SciTech Connect (OSTI)

    Prishchepov, A.I.; Starodubtsev, G.S.; Zatorsky, Y.M. [Mayak Production Association, Ozersk City (Russian Federation); James, L.T. [Sandia National Labs., Albuquerque, NM (United States); Ehinger, M.H. [Oak Ridge National Lab., TN (United States); Manatt, D.R. [Lawrence Livermore National Lab., CA (United States); Voss, S.S. [Los Alamos National Lab., NM (United States); Lundgren, R.A. [Pacific Northwest National Lab., Richland, WA (United States); Suda, S.C. [Brookhaven National Lab., Upton, NY (United States)

    1998-08-01T23:59:59.000Z

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC and A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC and A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC and A systems at two plants that are operated by Mayak and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

  16. Cooperation Between the Russia Federation and the United States to Enhance the Existing Nuclear-Material Protection, Control, and Accounting Systems at Mayak Production Association

    SciTech Connect (OSTI)

    Cahalane, P.T.; Ehinger, M.H.; James, L.T.; Jarrett, J.H.; Lundgren, R.A.; Manatt, D.R.; Niederauer, G.F.; Olivos, J.D.; Prishchepov, A.I.; Starodubtsev, G.S.; Suda, S.C.; Tittemore, G.W.; Zatorsky, Y.M.

    1999-07-19T23:59:59.000Z

    The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by lylINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at two of the plants operated by Mayak that work with proliferation-sensitive nuclear materials.

  17. An Overview of the Cooperative Effort between the United States Department of Energy and the China Atomic Energy Authority to Enhance MPC&A Inspections for Civil Nuclear Facilities in China

    SciTech Connect (OSTI)

    Ahern, Keith [U.S. Enrichment Corporation Paducah Gaseous Diffusion Plant; Daming, Liu [China Institute of Atomic Energy (CIAE); Hanley, Tim [U.S. Department of Energy, NNSA; Livingston, Linwood [Pacific Northwest National Laboratory (PNNL); McAninch, Connie [U.S. Department of Energy, NNSA; McGinnis, Brent R [ORNL; Ning, Shen [China Institute of Atomic Energy (CIAE); Qun, Yang [China Institute of Atomic Energy (CIAE); Roback, Jason William [ORNL; Tuttle, Glenn [U.S. Nuclear Regulatory Commission; Xuemei, Gao [China Institute of Atomic Energy (CIAE); Galer, Regina [U.S. National Nuclear Security Administration; Peterson, Nancy [U.S. National Nuclear Security Administration; Jia, Jinlie [China Atomic Energy Authority (CAEA)

    2011-01-01T23:59:59.000Z

    The United States Department of Energy, National Nuclear Security Administration (DOE/NNSA) and the China Atomic Energy Authority (CAEA) are cooperating to enhance the domestic regulatory inspections capacity for special nuclear material protection, control and accounting (MPC&A) requirements for civil nuclear facilities in China. This cooperation is conducted under the auspices of the Agreement between the Department of Energy of the United States of America and the State Development and Planning Commission of the People s Republic of China on Cooperation Concerning Peaceful Uses of Nuclear Technology. This initial successful effort was conducted in three phases. Phase I focused on introducing CAEA personnel to DOE and U. S. Nuclear Regulatory Commission inspection methods for U. S. facilities. This phase was completed in January 2008 during meetings in Beijing. Phase II focused on developing physical protection and material control and accounting inspection exercises that enforced U. S. inspection methods identified during Phase 1. Hands on inspection activities were conducted in the United States over a two week period in July 2009. Simulated deficiencies were integrated into the inspection exercises. The U. S. and Chinese participants actively identified and discussed deficiencies noted during the two week training course. The material control and accounting inspection exercises were conducted at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, KY. The physical protection inspection exercises were conducted at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN. Phase III leveraged information provided under Phase I and experience gained under Phase II to develop a formal inspection guide that incorporates a systematic approach to training for Chinese MPC&A field inspectors. Additional hands on exercises that are applicable to Chinese regulations were incorporated into the Phase III training material. Phase III was completed in May 2010 at the China Institute of Atomic Energy (CIAE) in Beijing. This paper provides details of the successful cooperation between DOE/NNSA and CAEA for all phases of the cooperative effort to enhance civil domestic MPC&A inspections in China.

  18. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    Vol. 16, No.1, January- Power-Plant Sites. 1i February 1975,~ ties Surrounding Nuclear Power Plants. LBlr5921, LawrenceS. Commercial Nuclear Power Plants. WASH-1400. October 1975.

  19. United States of Agriculture

    E-Print Network [OSTI]

    United States Department of Agriculture Forest Service Intermountain Research Station General. in the aircraft nuclear propulsion department at the National Reactor Testing Station in Idaho. In 1961 Rothermel.S. Department of Agriculture, Fire Laboratory at Missoula was conceived in the aftermath of the Mann Gulch fire

  20. Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors

    E-Print Network [OSTI]

    Galvez, Cristhian

    2011-01-01T23:59:59.000Z

    Advisory Committee and Generation IV International Forum.Nuclear Energy Agency The Generation IV International Forum.Technology Roadmap for Generation IV Nuclear Energy Systems.

  1. United States

    Office of Legacy Management (LM)

    - I United States Department of Energy D lSCk Al M E R "This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the United...

  2. Nebraska Nuclear Profile - Cooper

    U.S. Energy Information Administration (EIA) Indexed Site

    Cooper" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  3. Missouri Nuclear Profile - Callaway

    U.S. Energy Information Administration (EIA) Indexed Site

    Callaway" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  4. Michigan Nuclear Profile - Fermi

    U.S. Energy Information Administration (EIA) Indexed Site

    Fermi" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  5. Tennessee Nuclear Profile - Sequoyah

    U.S. Energy Information Administration (EIA) Indexed Site

    Sequoyah" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License Expiration Date"...

  6. Pennsylvania Nuclear Profile - Limerick

    U.S. Energy Information Administration (EIA) Indexed Site

    Limerick" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  7. Virginia Nuclear Profile - Surry

    U.S. Energy Information Administration (EIA) Indexed Site

    Surry" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  8. Wisconsin Nuclear Profile - Kewaunee

    U.S. Energy Information Administration (EIA) Indexed Site

    Kewaunee" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License expiration date"...

  9. Ohio Nuclear Profile - Perry

    U.S. Energy Information Administration (EIA) Indexed Site

    Perry" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  10. Michigan Nuclear Profile - Palisades

    U.S. Energy Information Administration (EIA) Indexed Site

    Palisades" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  11. A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles

    E-Print Network [OSTI]

    Djokic, Denia

    2013-01-01T23:59:59.000Z

    m source, special nuclear, and waste † byproduct directly †United † States † Nuclear † Waste † Technical † Review †12, †2009. † NWPA †1982 † Nuclear †Waste †Policy †Act †of †

  12. The Politically Correct Nuclear Energy Plant

    E-Print Network [OSTI]

    Transportation ? ∑ Fuel Cells ? ∑ Electric Cars ? ∑ Solar Electric Cars ∑ Natural Gas ? ∑ Combo-Cars ∑ Hydrogen Nuclear Plants Operating Very Well ∑ But, Generating Companies not Interested in New Nuclear Plants

  13. Next Generation Nuclear Plant Phenomena

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for the production of electricity. Some reactors also sell steam for industrial users and district heat. VHTRs produce high-temperature heat that can be used as process heat for...

  14. Registration of Electric Generators (Connecticut)

    Broader source: Energy.gov [DOE]

    All electric generating facilities operating in the state, with the exception of hydroelectric and nuclear facilities, must obtain a certificate of registration from the Department of Public...

  15. NOx emissions retrofit at Reliant Energy, W.A. Parish Generating Station, Unit 7: Achieving 0.15 lb/MBtu

    SciTech Connect (OSTI)

    Gessner, T.M.; Hoh, R.H.; Ray, B.; Dorazio, T.; Jennings, P.; Sikorski, K.

    1999-07-01T23:59:59.000Z

    The current Clean Air Act (CAA), Title 1 regulations require States to develop implementation plans (SIPs) which address NO{sub x} emissions as part of the ozone non-attainment requirements. The EPA has recommended NO{sub x} limits of 0.15 lb/MBtu for utility boilers. In this paper, Reliant Energy and ABB C-E Services, Inc. will discuss a project where 0.15 lb NO{sub x}/MBtu can be achieved with the TFS 2000{trademark} R firing system and highly reactive Powder River Basin (PRB) fuels. Reliant Energy will retrofit their W.A. Parish Unit 7 with this system in the first quarter of 1999. This is part of Reliant Energy's drive to lower NO{sub x} emissions and meet future air quality requirements at the W.Q. Parish station.

  16. UPDATE: nuclear power program information and data, July-September 1981

    SciTech Connect (OSTI)

    DOE /NBM--6011986

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATA is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  17. Update: nuclear power program information and data, March-April 1981

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  18. Update: nuclear power program information and data, October-December 1981

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  19. Commercial nuclear power 1990

    SciTech Connect (OSTI)

    Not Available

    1990-09-28T23:59:59.000Z

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

  20. Boronline, a new generation of boron meter

    SciTech Connect (OSTI)

    Pirat, P. [Rolls-Royce Company, Meylan (France)

    2011-07-01T23:59:59.000Z

    Rolls-Royce is a global business providing integrated power systems for use on land, at sea and in the air. The Group has a balanced business portfolio with leading market positions - civil aerospace, defence aerospace, marine and energy Rolls-Royce understands the challenges of design, procurement, manufacture, operation and in-service support of nuclear reactor plants, with over 50 years of experience through the Royal Navy submarine programme. Rolls-Royce can therefore offer full product life-cycle management for new civil nuclear installations, as well as support to existing installations, including plant lifetime extensions. Rolls-Royce produced for 40 years, Instrumentation and Control (I and C) systems of and associated services for nuclear reactors in Europe, including 58 French reactors and others situated in the United States and in others countries, such as China. Rolls-Royce equipped in this domain 200 nuclear reactors in 20 countries. Among all of its nuclear systems, Rolls Royce is presenting to the conference its new generation of on-line boron measurement system, so called Boronline. (authors)

  1. Multi-unit operations considerations.

    SciTech Connect (OSTI)

    Gilmore, Walter E. (Los Alamos National Laboratory, Los Alamos, NM); Bennett, Thomas C. (Lawrence Livermore National Laboratory, Albuquerque, NM); Brannon, Nathan Gregory

    2005-09-01T23:59:59.000Z

    Several nuclear weapons programs have or are pursuing the implementation of multi-unit operations for tasks such as disassembly and inspection, and rebuild. A multi-unit operation is interpreted to mean the execution of nuclear explosive operating procedures in a single facility by two separate teams of technicians. The institution of a multi-unit operations program requires careful consideration of the tools, resources, and environment provided to the technicians carrying out the work. Therefore, a systematic approach is necessary to produce safe, secure, and reliable processes. In order to facilitate development of a more comprehensive multi-unit operations program, the current work details categorized issues that should be addressed prior to the implementation of multi-unit operations in a given weapons program. The issues have been organized into the following categories: local organizational conditions, work process flow/material handling/workplace configuration, ambient environmental conditions, documented safety analysis, and training.

  2. UNIT NUMBER:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    193 UNIT NUMBER: 197 UNIT NAME: CONCRETE RUBBLE PILE (30) REGULATORY STATUS: AOC LOCATION: Outside plant security fence, north of the plant on Big Bayou Creek on private property....

  3. Distributed Generation Dispatch Optimization under Various Electricity Tariffs

    E-Print Network [OSTI]

    Firestone, Ryan; Marnay, Chris

    2007-01-01T23:59:59.000Z

    time of use United States Postal Service v Distributed Generation Dispatch Optimization Under Various Electricity Tariffs

  4. Final Report: Particulate Emissions Testing, Unit 1, Potomac...

    Broader source: Energy.gov (indexed) [DOE]

    were completed while Unit 1 was operating at 90% of full load (84MW) or greater. Final Report: Particulate Emissions Testing, Unit 1, Potomac River Generating Station, Alexandria,...

  5. Nuclear Decommissioning Financing Act (Maine)

    Broader source: Energy.gov [DOE]

    The Nuclear Decommissioning Financing Act calls for the establishment of a tax-exempt, tax-deductible decommissioning fund by the licensee of any nuclear power generating facility to pay for the...

  6. EFFICIENT PARALLELIZATION OF STOCHASTIC SIMULATION ALGORITHM FOR CHEMICALLY REACTING SYSTEMS ON THE GRAPHICS PROCESSING UNIT

    E-Print Network [OSTI]

    Li, Hong; Petzold, Linda

    2009-01-01T23:59:59.000Z

    REACTING SYSTEMS ON THE GRAPHICS PROCESSING UNIT H. Li ? L.The current generation of graphics processing units (GPU) issystems on the low cost graphics processing unit (GPU)

  7. South Carolina Nuclear Profile - Power Plants

    U.S. Energy Information Administration (EIA) Indexed Site

    South Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

  8. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01T23:59:59.000Z

    ABBREVIATIONS AAB Accident Analysis Branch (NRC) ApplicationF, Nischan, US NRC. Accident Analysis Branch, U. S. Nuclear2. L 2 is placed in the Accident Analysis Branch (AAB); with

  9. Impact of Public Policy and Societal Risk Perception on U.S. Civilian Nuclear Power Plant Construction

    E-Print Network [OSTI]

    Ford, David N.

    a new generation of NPP construction across the northeastern and southeastern United States. The Nuclear, com- plex projects. However, NPP construction has the potential to also be exposed to risks driven Construction Timothy R. B. Taylor1 ; David N. Ford2 ; and Kenneth F. Reinschmidt3 Abstract: Due

  10. 2009 UK/US Nuclear Engineering Workshop Report

    SciTech Connect (OSTI)

    Richard Rankin

    2009-04-01T23:59:59.000Z

    This report summarizes the 2009 UK/US Nuclear Engineering Workshop held April 20-21, 2010, in Washington, D.C. to discuss opportunities for nuclear engineering collaboration between researchers in the United States and the United Kingdom.

  11. A Strategy for Nuclear Energy Research and Development

    SciTech Connect (OSTI)

    Ralph G. Bennett

    2008-12-01T23:59:59.000Z

    The United States is facing unprecedented challenges in climate change and energy security. President-elect Obama has called for a reduction of CO2 emissions to 1990 levels by 2020, with a further 80% reduction by 2050. Meeting these aggressive goals while gradually increasing the overall energy supply requires that all non-emitting technologies must be advanced. The development and deployment of nuclear energy can, in fact, help the United States meet several key challenges: 1) Increase the electricity generated by non-emitting sources to mitigate climate change, 2) Foster the safe and proliferation-resistant use of nuclear energy throughout the world, 3) Reduce the transportation sectorís dependence on imported fossil fuels, and 4) Reduce the demand on natural gas for process heat and hydrogen production. However, because of the scale, cost, and time horizons involved, increasing nuclear energyís share will require a coordinated research effortócombining the efforts of industry and government, supported by innovation from the research community. This report outlines the significant nuclear energy research and development (R&D) necessary to create options that will allow government and industrial decision-makers to set policies and create nuclear energy initiatives that are decisive and sustainable. The nuclear energy R&D strategy described in this report adopts the following vision: Safe and economical nuclear energy in the United States will expand to address future electric and non-electric needs, significantly reduce greenhouse gas emissions and provide energy diversity, while providing leadership for safe, secure and responsible expansion of nuclear energy internationally.

  12. Nuclear Power - System Simulations and Operation†

    E-Print Network [OSTI]

    2011-01-01T23:59:59.000Z

    A&M University United States of America 1 Simulation and Simulators for Nuclear Power Generation J a n o s Sebe s ty e n Janos y MTA KFKI Atomic Energy Research Institute Hungary 1. Introduction T h i s chapte r deals with simula... t i o n , a very po werfu l tool in designi n g , constru c t i n g and operat i n g nuclea r power genera t i n g facili ti es . There are very differ e n t types of power plants , and the exampl e s mentio n e d in this chapte r or igin a t e from...

  13. Investigation of the Potential for Biofuel Blends in Residual Oil-Fired Power Generation Units as an Emissions Reduction Strategy for New York State

    SciTech Connect (OSTI)

    Krishna, C.R.; McDonald, R.

    2009-05-01T23:59:59.000Z

    There is a significant amount of oil, about 12.6 million barrels per year, used for power generation in New York State. The majority of it is residual oil. The primary reason for using residual oil probably is economic, as these fuels are cheaper than distillates. However, the stack emissions from the use of such fuels, especially in densely populated urban areas, can be a cause for concern. The emissions of concern include sulfur and nitrogen oxides and particulates, particularly PM 2.5. Blending with distillate (ASTM No.2) fuels may not reduce some or all of these emissions. Hence, a case can be made for blending with biofuels, such as biodiesel, as they tend to have very little fuel bound sulfur and nitrogen and have been shown in prior work at Brookhaven National Laboratory (BNL) to reduce NOx emissions as well in small boilers. Some of the research carried out at CANMET in Canada has shown potential reductions in PM with blending of biodiesel in distillate oil. There is also the benefit obtaining from the renewable nature of biofuels in reducing the net carbon dioxide emitted thus contributing to the reduction of green house gases that would otherwise be emitted to the atmosphere. The present project was conceived to examine the potential for such benefits of blending biofuels with residual oil. A collaboration was developed with personnel at the New York City Poletti Power Plant of the New York Power Authority. Their interest arose from an 800 MW power plant that was using residual oil and which was mandated to be shut down in 2010 because of environmental concerns. A blend of 20% biodiesel in residual oil had also been tested for a short period of about two days in that boiler a couple of years back. In this project, emission measurements including particulate measurements of PM2.5 were made in the commercial boiler test facility at BNL described below. Baseline tests were done using biodiesel as the blending biofuel. Biodiesel is currently and probably in the foreseeable future more expensive than residual fuel. So, another task was to explore potential alternative biofuels that might confer emission benefits similar to those of biodiesel, while being potentially significantly cheaper. Of course, for power plant use, availability in the required quantities is also a significant criterion. A subsidiary study to determine the effect of the temperature of the filter used to collect and measure the PM 2.5 emissions was conducted. This was done for reasons of accuracy in a residential boiler using distillate fuel blends. The present report details the results obtained in these tests with the baseline ASTM No. 6 fuel and blends of biodiesel with it as well as the results of the filter temperature study. The search for the alternative 'cheaper' biofuel identified a potential candidate, but difficulties encountered with the equipment during the testing prevented testing of the alternative biofuel.

  14. Nuclear space power safety and facility guidelines study

    SciTech Connect (OSTI)

    Mehlman, W.F.

    1995-09-11T23:59:59.000Z

    This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an {open_quotes}Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missions{close_quotes}. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system.

  15. Energy Department Invests $60 Million to Train Next Generation...

    Office of Environmental Management (EM)

    generation of leaders in America's nuclear industry as well as support new and advanced nuclear technologies from reactor materials to innovative sensors and instruments to more...

  16. Nuclear Energy | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    systems, nonproliferation and national security, and environmental management. Nuclear energy is the largest generator of carbon-free electricity in use today, and it will play...

  17. The elements of nuclear power

    SciTech Connect (OSTI)

    Bennet, D.J.; Thomson, J.R.

    1989-01-01T23:59:59.000Z

    An introduction to the principles of nuclear fission power generation. Describes the physical processes which occur in a nuclear reactor and discusses the theory behind the calculations. Also covers heat transfer in reactors, thermodynamic power cycles, reactor operators, and radiation shielding. Material covered includes topics on the effects of nuclear radiation on humans, the safety of nuclear reactors and of those parts of the nuclear fuel cycle which deal with fuel element manufacture and the reprocessing of irradiated fuel.

  18. Future Prospects for Nuclear Power after Fukushima

    E-Print Network [OSTI]

    Goldberg, Bennett

    at the FukushimaDaiichi nuclear power plant in Japan has changed the perception of nuclear as a safe energy sourceFuture Prospects for Nuclear Power after Fukushima Nuclear is a highintensity energy source as the next generation of Light Water Reactors. We will also discuss the future prospects of nuclear power

  19. Waste Generated from LMR-AMTEC Reactor Concept

    SciTech Connect (OSTI)

    Hasan, Ahmed; Mohamed, Yasser, T.; Mohammaden, Tarek, F.

    2003-02-25T23:59:59.000Z

    The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from the packing materials (e.g. activated carbon in cold trap and purification units). The regulations and management of these wastes are summarized in this paper.

  20. Generating Unit Retirements in the United States by State, 2003

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-15

  1. Generating Unit Retirements in the United States by State, 2004

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154" "Note:

  2. Generating Unit Retirements in the United States by State, 2005

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154" "Note:5"

  3. Generating Unit Retirements in the United States by State, 2006

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154"

  4. Generating Unit Retirements in the United States by State, 2007

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154"7" "Note:

  5. Generating Unit Retirements in the United States by State, 2008

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154"7"

  6. Generating Unit Retirements in the United States by State, 2009

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15 Mar-154"7"9"

  7. Generating Unit Retirements in the United States by State, 2010

    U.S. Energy Information Administration (EIA) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14 Dec-14 Jan-15 Feb-15

  8. UNIT NUMBER

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    4 UNIT NAME C-611 Underaround Diesel Tank REGULATORY STATUS: AOC LOCATION: Immediately southeast of C-611 APPROXIMATE DIMENSIONS: 1000 gallon FUNCTION: Diesel storage OPERATIONAL...

  9. A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    Charges Relating to Nuclear Reactor Safety," 1976, availableissues impor tant to nuclear reactor safety. This report wasstudies of overall nuclear reactor safety have been

  10. A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    for sabotage of nuclear plants or the potential forAccidents in Large Nuclear Plants" (AEC Report, WASH-/40),YEAR FROM POTENTIAL NUCLEAR PLANT ACCIDENTS(a) Consequence

  11. POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    Removal Equipment (nuclear plant) Turbine Building ClosedCooling Water System (nuclear plant) SteamReheater (nuclear plant) Inspection Water Induction

  12. A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01T23:59:59.000Z

    Charges Relating to Nuclear Reactor Safety," 1976, availablestudies of light-water nuclear reactor safety, emphasizingstudies of overall nuclear reactor safety have been

  13. World nuclear outlook 1995

    SciTech Connect (OSTI)

    NONE

    1995-09-29T23:59:59.000Z

    As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

  14. World nuclear outlook 1994

    SciTech Connect (OSTI)

    NONE

    1994-12-01T23:59:59.000Z

    As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

  15. United Power- Business Energy Efficiency Rebate Program

    Broader source: Energy.gov [DOE]

    United Power, in conjunction with wholesale power supplier Tri-State Generation and Transmission (TSGT), offers rebates for the installation of a variety of commercial energy efficient equipment...

  16. Sustainability Features of Nuclear Fuel Cycle Options

    E-Print Network [OSTI]

    Passerini, Stefano

    The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an ...

  17. United States and France Sign Joint Statement on Civil Liability...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and France Sign Joint Statement on Civil Liability for Nuclear Damage United States and France Sign Joint Statement on Civil Liability for Nuclear Damage Joint Statement Signed.pdf...

  18. State Nuclear Profiles 2010

    U.S. Energy Information Administration (EIA) Indexed Site

    60 Vermont Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347...

  19. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

    2012-05-15T23:59:59.000Z

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  20. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

    2010-07-13T23:59:59.000Z

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.