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1

Light Water Reactor Sustainability Program: Integrated Program...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Light Water Reactor Sustainability Program: Integrated Program Plan Light Water Reactor Sustainability Program: Integrated Program Plan Nuclear power has safely, reliably, and...

2

Light Water Reactor Sustainability Program - Integrated Program Plan |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Light Water Reactor Sustainability Program - Integrated Program Light Water Reactor Sustainability Program - Integrated Program Plan Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U. S. Department of Energy (DOE), performed in close collaboration and cooperation with related industry R&D programs. The LWRS Program provides technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants, utilizing the unique capabilities of the national laboratory system. Sustainability is defined as the ability to maintain safe and economic operation of the existing fleet of nuclear power plants for a longer than-initially-licensed lifetime. It has two facets

3

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement (decreased toughness) , as shown in Fig. 1.1, and extending operation from

4

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations, which govern the operation of commercial nuclear power plants, require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including

5

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Light Water Reactor Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program The Light Water Reactor Sustainability (LWRS) Program is developing the scientific basis to extend existing nuclear power plant operating life beyond the current 60-year licensing period and ensure long-term reliability, productivity, safety, and security. The program is conducted in collaboration with national laboratories, universities, industry, and international partners. Idaho National Laboratory serves as the Technical Integration Office and coordinates the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems

6

Light Water Reactor Sustainability Program - Non-Destructive...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Remaining Useful Life of Aging Cables in Nuclear Power Plants Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful...

7

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Assessment of High Value Surveillance Materials Assessment of High Value Surveillance Materials Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations that govern the operation of commercial nuclear power plants require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including pressurized thermal shock (PTS) in pressurized water reactors (PWR). In the irradiated condition, however, the fracture toughness of the RPV may be severely

8

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Initial Assessment of Thermal Annealing Needs and Challenges Initial Assessment of Thermal Annealing Needs and Challenges Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement (decreased toughness) , as shown in Fig. 1.1, and extending operation from 40y to 80y implies a doubling of the neutron exposure for the RPV. Thus,

9

Light Water Reactor Sustainability Program: Integrated Program Plan |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Integrated Program Plan Integrated Program Plan Light Water Reactor Sustainability Program: Integrated Program Plan Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas- emitting electric power generation in the United States. Domestic demand for electrical energy is expected to grow by more than 30% from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license, for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power

10

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

2013-04-01T23:59:59.000Z

11

Light Water Reactor Sustainability Program Integrated Program Plan  

Science Conference Proceedings (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

2012-01-01T23:59:59.000Z

12

Light Water Reactor Sustainability Program: Materials Aging and Degradation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Materials Aging and Materials Aging and Degradation Technical Program Plan Light Water Reactor Sustainability Program: Materials Aging and Degradation Technical Program Plan Components serving in a nuclear reactor plant must withstand a very harsh environment including extended time at temperature, neutron irradiation, stress, and/or corrosive media. The many modes of degradation are complex and vary depending on location and material. However, understanding and managing materials degradation is a key for the continued safe and reliable operation of nuclear power plants. Extending reactor service to beyond 60 years will increase the demands on materials and components. Therefore, an early evaluation of the possible effects of extended lifetime is critical. The recent NUREG/CR-6923 gives a

13

Light Water Reactor Sustainability Program - Non-Destructive Evaluation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program - Non-Destructive Program - Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter experts to develop the NDE R&D Roadmap for Cables. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters.

14

Materials Inventory Database for the Light Water Reactor Sustainability Program  

Science Conference Proceedings (OSTI)

Scientific research involves the purchasing, processing, characterization, and fabrication of many sample materials. The history of such materials can become complicated over their lifetime – materials might be cut into pieces or moved to various storage locations, for example. A database with built-in functions to track these kinds of processes facilitates well-organized research. The Material Inventory Database Accounting System (MIDAS) is an easy-to-use tracking and reference system for such items. The Light Water Reactor Sustainability Program (LWRS), which seeks to advance the long-term reliability and productivity of existing nuclear reactors in the United States through multiple research pathways, proposed MIDAS as an efficient way to organize and track all items used in its research. The database software ensures traceability of all items used in research using built-in functions which can emulate actions on tracked items – fabrication, processing, splitting, and more – by performing operations on the data. MIDAS can recover and display the complete history of any item as a simple report. To ensure the database functions suitably for the organization of research, it was developed alongside a specific experiment to test accident tolerant nuclear fuel cladding under the LWRS Advanced Light Water Reactor Nuclear Fuels Pathway. MIDAS kept track of materials used in this experiment from receipt at the laboratory through all processes, test conduct and, ultimately, post-test analysis. By the end of this process, the database proved to be right tool for this program. The database software will help LWRS more efficiently conduct research experiments, from simple characterization tests to in-reactor experiments. Furthermore, MIDAS is a universal tool that any other research team could use to organize their material inventory.

Kazi Ahmed; Shannon M. Bragg-Sitton

2013-08-01T23:59:59.000Z

15

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light water reactor sustainability (LWRS) nondestructive evaluation (NDE) Workshops were held at Oak Ridge National Laboratory (ORNL) during July 30th to August 2nd, 2012. This activity was conducted to help develop the content of the NDE R&D roadmap for the materials aging and degradation (MAaD) pathway of the LWRS program. The workshops focused on identifying NDE R&D needs in four areas: cables, concrete, reactor pressure vessel, and piping. A selected group of subject matter experts (SMEs) from DOE national

16

DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-NE Light Water Reactor Sustainability Program and EPRI DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's

17

DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-NE Light Water Reactor Sustainability Program and EPRI DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program - Joint Research and Development Plan Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's

18

Reactor Pressure Vessel Task of Light Water Reactor Sustainability...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure...

19

Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

(LWRS) Program - R&D Roadmap (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping Light water reactor sustainability (LWRS) nondestructive evaluation (NDE) Workshops were held at Oak Ridge National Laboratory (ORNL) during July 30th to August 2nd, 2012. This activity was conducted to help develop the content of the NDE R&D roadmap for the materials aging and degradation (MAaD) pathway of the LWRS program. The workshops focused on identifying NDE R&D needs in four areas: cables, concrete, reactor pressure vessel, and piping. A selected group of subject matter experts (SMEs) from DOE national laboratories, academia, vendors, EPRI, and NRC were invited to each

20

Overview of the US Department of Energy Light Water Reactor Sustainability Program  

Science Conference Proceedings (OSTI)

The US Department of Energy Light Water Reactor Sustainability Program is focused on the long-term operation of US commercial power plants. It encompasses two facets of long-term operation: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the nuclear industry that support implementation of performance improvement technologies. An important aspect of the Light Water Reactor Sustainability Program is partnering with industry and the Nuclear Regulatory Commission to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The Department of Energy research, development, and demonstration role focuses on aging phenomena and issues that require long-term research and/or unique Department of Energy laboratory expertise and facilities and are applicable to all operating reactors. This paper gives an overview of the Department of Energy Light Water Reactor Sustainability Program, including vision, goals, and major deliverables.

K. A. McCarthy; D. L. Williams; R. Reister

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program  

SciTech Connect

The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

2012-09-01T23:59:59.000Z

22

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–2013  

SciTech Connect

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

23

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–201/span>3  

Science Conference Proceedings (OSTI)

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

24

Light Water Reactor Sustainability Technical Documents | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Technologies » Light Water Reactor Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents April 30, 2013 LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water Reactor Sustainability (LWRS) Program and EPRI's Long-Term Operations (LTO) Program. April 30, 2013 Light Water Reactor Sustainability Program - Integrated Program Plan The Light Water Reactor Sustainability (LWRS) Program is a research and

25

Light Water Reactor Sustainability Program Grizzly Year-End Progress Report  

SciTech Connect

The Grizzly software application is being developed under the Light Water Reactor Sustainability (LWRS) program to address aging and material degradation issues that could potentially become an obstacle to life extension of nuclear power plants beyond 60 years of operation. Grizzly is based on INL’s MOOSE multiphysics simulation environment, and can simultaneously solve a variety of tightly coupled physics equations, and is thus a very powerful and flexible tool with a wide range of potential applications. Grizzly, the development of which was begun during fiscal year (FY) 2012, is intended to address degradation in a variety of critical structures. The reactor pressure vessel (RPV) was chosen for an initial application of this software. Because it fulfills the critical roles of housing the reactor core and providing a barrier to the release of coolant, the RPV is clearly one of the most safety-critical components of a nuclear power plant. In addition, because of its cost, size and location in the plant, replacement of this component would be prohibitively expensive, so failure of the RPV to meet acceptance criteria would likely result in the shutting down of a nuclear power plant. The current practice used to perform engineering evaluations of the susceptibility of RPVs to fracture is to use the ASME Master Fracture Toughness Curve (ASME Code Case N-631 Section III). This is used in conjunction with empirically based models that describe the evolution of this curve due to embrittlement in terms of a transition temperature shift. These models are based on an extensive database of surveillance coupons that have been irradiated in operating nuclear power plants, but this data is limited to the lifetime of the current reactor fleet. This is an important limitation when considering life extension beyond 60 years. The currently available data cannot be extrapolated with confidence further out in time because there is a potential for additional damage mechanisms (i.e. late blooming phases) to become active later in life beyond the current operational experience. To develop a tool that can eventually serve a role in decision-making, it is clear that research and development must be perfomed at multiple scales. At the engineering scale, a multiphysics analysis code that can capture the thermomechanical response of the RPV under accident conditions, including detailed fracture mechanics evaluations of flaws with arbitrary geometry and orientation, is needed to assess whether the fracture toughness, as defined by the master curve, including the effects of embrittlement, is exceeded. At the atomistic scale, the fundamental mechanisms of degradation need to be understood, including the effects of that degradation on the relevant material properties. In addition, there is a need to better understand the mechanisms leading to the transition from ductile to brittle fracture through improved continuum mechanics modeling at the fracture coupon scale. Work is currently being conducted at all of these levels with the goal of creating a usable engineering tool informed by lower length-scale modeling. This report summarizes progress made in these efforts during FY 2013.

Benjamin Spencer; Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner; Marie Backman; Brian Wirth; Stephen Novascone; Jason Hales

2013-09-01T23:59:59.000Z

26

Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study  

SciTech Connect

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

2012-08-01T23:59:59.000Z

27

Sustainable Agriculture Loan Program  

Energy.gov (U.S. Department of Energy (DOE))

The Minnesota Sustainable Agriculture Loan program will provide loans to Minnesota residents actively engaged in farming for capital expenditures which enhance the environmental and economic...

28

Light Water Reactor Sustainability Technical Documents | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Initiatives » Nuclear Reactor Technologies » Light Water Reactor Initiatives » Nuclear Reactor Technologies » Light Water Reactor Sustainability Program » Light Water Reactor Sustainability Technical Documents Light Water Reactor Sustainability Technical Documents September 30, 2011 Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement

29

Light Water Reactor Sustainability Program FY13 Status Update for EPRI - RISMC Collaboration  

Science Conference Proceedings (OSTI)

The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced "RISMC toolkit" that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory (INL) is collaborating with the Electric Power Research Institute (EPRI) in order to focus on applications of interest to the U.S. nuclear power industry. This report documents the collaboration activities performed between INL and EPRI during FY2013.

Curtis Smith

2013-09-01T23:59:59.000Z

30

Light Water Reactor Sustainability Nondestructive Evaluation for Concrete  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nondestructive Evaluation for Nondestructive Evaluation for Concrete Research and Development Roadmap Light Water Reactor Sustainability Nondestructive Evaluation for Concrete Research and Development Roadmap Materials issues are a key concern for the existing nuclear reactor fleet as material degradation can lead to increased maintenance, increased downtown, and increased risk. Extending reactor life to 60 years and beyond will likely increase susceptibility and severity of known forms of degradation. Additionally, new mechanisms of materials degradation are also possible. The purpose of the US Department of Energy Office of Nuclear Energy's Light Water Reactor Sustainability (LWRS) Program is to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend

31

Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan  

SciTech Connect

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01T23:59:59.000Z

32

Reactor Sharing Program  

Science Conference Proceedings (OSTI)

Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy's University Reactor Sharing Program is reported for the period of 1991--1992.

Vernetson, W.G.

1993-01-01T23:59:59.000Z

33

ANL/NE-12/43 Light Water Reactor Sustainability (LWRS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ANLNE-1243 Light Water Reactor Sustainability (LWRS) Program - R&D Roadmap for Non-Destructive Evaluation (NDE) of Fatigue Damage in Piping ...

34

Federal Energy Management Program: Sustainable Federal Fleets  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Sustainable Federal Fleets to someone by E-mail Share Federal Energy Management Program: Sustainable Federal Fleets on Facebook Tweet about Federal Energy Management Program: Sustainable Federal Fleets on Twitter Bookmark Federal Energy Management Program: Sustainable Federal Fleets on Google Bookmark Federal Energy Management Program: Sustainable Federal Fleets on Delicious Rank Federal Energy Management Program: Sustainable Federal Fleets on Digg Find More places to share Federal Energy Management Program: Sustainable Federal Fleets on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance Greenhouse Gases Water Efficiency Data Center Energy Efficiency Industrial Facilities Sustainable Federal Fleets Laboratories for the 21st Century Institutional Change

35

Federal Energy Management Program: Sustainable Building Basics  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Building Basics to someone by E-mail Share Federal Energy Management Program: Sustainable Building Basics on Facebook Tweet about Federal Energy Management Program:...

36

Federal Energy Management Program: Sustainable Building Contacts  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Building Contacts to someone by E-mail Share Federal Energy Management Program: Sustainable Building Contacts on Facebook Tweet about Federal Energy Management Program:...

37

Sustainable Manufacturing Program  

Science Conference Proceedings (OSTI)

... Program is to develop and deploy advances in measurement science to enable improvements in resource (energy, material) efficiency and waste ...

2013-01-08T23:59:59.000Z

38

Weatherization and Intergovernmental Program: Sustainable Energy Resources  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Energy Resources for Consumers (SERC) Grants to someone by E-mail Share Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on Facebook Tweet about Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on Twitter Bookmark Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on Google Bookmark Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on Delicious Rank Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on Digg Find More places to share Weatherization and Intergovernmental Program: Sustainable Energy Resources for Consumers (SERC) Grants on

39

Sustainability Outreach Program Brochure  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Health, Safety and Security (HSS) is Health, Safety and Security (HSS) is the Department of Energy's (DOE) central organization responsible for health, safety, environment, and security; providing corporate-level leadership and strategic vision to coordinate and integrate these vital programs. HSS is responsible for policy development and technical assistance; safety analysis; corporate safety and security programs; education and training; complex-wide independent oversight; and enforcement. The Chief Health, Safety and Security Officer advises the Secretary and the Deputy Secretary on all matters related to health, safety and security across the complex. Our Stakeholders Labor Unions/Workers Local Communities/General Public Contractors Universities/Academic Institutions Professional Associations

40

Federal Energy Management Program: Sustainable Buildings and...  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Buildings and Campuses to someone by E-mail Share Federal Energy Management Program: Sustainable Buildings and Campuses on Facebook Tweet about Federal Energy...

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Update Sustainable Transportation Program  

NLE Websites -- All DOE Office Websites (Extended Search)

4, No.1 * May 2013 4, No.1 * May 2013 VSI Lab opening to accelerate pace of powertrain R&D provide data that industry partners could use to adjust their vehicle designs accordingly to meet federal regulations on fuel efficiency and emissions control," said David Smith, manager of the Advanced Vehicle Systems Research Program. The lab comprises a powertrain test cell with twin AVL 500 kW AC transient dynamometers and a component test cell - both share energy storage system emulation and dSPACE hardware-in-the-loop (HIL) real-time platform capabilities. The VSI Lab also features "X"-in-the-loop hardware evaluation of powertrain components and/or subsystems in virtual vehicle environments, where "X" represents any experimental component or subsystem.

42

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT  

SciTech Connect

Progress on reactor programs and in general engineering research and development programs is summarized. Research and development are reported on water-cooled reactors including EBWR and Borax-V, sodium-cooled reactors including ZPR-III, IV, and IX, Juggernaut, and EBR-I and II. Other work included a review of fast reactor technology, and studies on nuclear superheat, thermal and fast reactor safety, and reactor physics. Effort was also devoted to reactor materials and fuels development, heat engineering, separation processes and advanced reactor concepts. (J.R.D.)

1961-04-01T23:59:59.000Z

43

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

Science Conference Proceedings (OSTI)

Summary report for Fiscal Year 2011 activities associated with the Constellation Pilot Project. The project is a joint effor between Constellation Nuclear Energy Group (CENG), EPRI, and the DOE Light Water Reactor Sustainability Program. The project utilizes two CENG reactor stations: R.E. Ginna and Nine Point Unit 1. Included in the report are activities associate with reactor internals and concrete containments.

R. Johansen

2011-09-01T23:59:59.000Z

44

Sustainable Development Fund Financing Program (PECO Territory) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Development Fund Financing Program (PECO Territory) Sustainable Development Fund Financing Program (PECO Territory) Sustainable Development Fund Financing Program (PECO Territory) < Back Eligibility Commercial Industrial Nonprofit Schools Savings Category Heating & Cooling Commercial Heating & Cooling Heating Cooling Home Weatherization Construction Commercial Weatherization Design & Remodeling Other Heat Pumps Appliances & Electronics Commercial Lighting Lighting Bioenergy Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Water Solar Water Heating Wind Program Info State Pennsylvania Program Type Local Loan Program Rebate Amount Varies by project Provider TRF Sustainable Development Fund The Pennsylvania Public Utility Commission created the Sustainable Development Fund (SDF) in its final order of the PECO Energy electric

45

Federal Energy Management Program: Sustainable Building Contacts  

NLE Websites -- All DOE Office Websites (Extended Search)

Contacts For more information about sustainable buildings and campuses, contact: Sarah Jensen Federal Energy Management Program 202-287-6033 DOE laboratory support is also provided...

46

Sustainable Energy Utility - Residential Energy Efficiency Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Energy Utility - Residential Energy Efficiency Program Sustainable Energy Utility - Residential Energy Efficiency Program (District of Columbia) Sustainable Energy Utility - Residential Energy Efficiency Program (District of Columbia) < Back Eligibility Residential Savings Category Appliances & Electronics Commercial Lighting Lighting Program Info Start Date 01/01/2013 Expiration Date 09/30/2013 State District of Columbia Program Type Utility Rebate Program Rebate Amount Refrigerators: $50 Clothes Washers: $50 CFL Lighting: varies by in-store discounts LED Lighting: $5-$10 The District of Columbia Sustainable Energy Utility currently offers the Residential Energy Efficiency Program. The program provides incentives to residents who complete qualifying home energy upgrades. Qualifying items include refrigerators, clothes washers, LED lighting and CFL lighting

47

2012 Annual Report Research Reactor Infrastructure Program  

SciTech Connect

The content of this report is the 2012 Annual Report for the Research Reactor Infrastructure Program.

Douglas Morrell

2012-11-01T23:59:59.000Z

48

Mexico-National Program for Sustainable Use of Energy | Open...  

Open Energy Info (EERE)

Program for Sustainable Use of Energy Jump to: navigation, search Name Mexico-National Program for Sustainable Use of Energy AgencyCompany Organization Government of Mexico...

49

New Production Reactors Program Plan  

SciTech Connect

Part I of this New Production Reactors (NPR) Program Plan: describes the policy basis of the NPR Program; describes the mission and objectives of the NPR Program; identifies the requirements that must be met in order to achieve the mission and objectives; and describes and assesses the technology and siting options that were considered, the Program's preferred strategy, and its rationale. The implementation strategy for the New Production Reactors Program has three functions: Linking the design, construction, operation, and maintenance of facilities to policies requirements, and the process for selecting options. The development of an implementation strategy ensures that activities and procedures are consistent with the rationale and analysis underlying the Program. Organization of the Program. The strategy establishes plans, organizational structure, procedures, a budget, and a schedule for carrying out the Program. By doing so, the strategy ensures the clear assignment of responsibility and accountability. Management and monitoring of the Program. Finally, the strategy provides a basis for monitoring the Program so that technological, cost, and scheduling issues can be addressed when they arise as the Program proceeds. Like the rest of the Program Plan, the Implementation Strategy is a living document and will be periodically revised to reflect both progress made in the Program and adjustments in plans and policies as they are made. 21 figs., 5 tabs.

1990-12-01T23:59:59.000Z

50

Caribbean Sustainable Energy Program | Open Energy Information  

Open Energy Info (EERE)

Caribbean Sustainable Energy Program Caribbean Sustainable Energy Program Agency/Company /Organization Organization of American States (OAS) Sector Energy Focus Area Energy Efficiency, Renewable Energy Topics Market analysis, Policies/deployment programs Country St. Lucia, Dominica, Grenada, St. Kitts & Nevis, St. Vincent and the Grenadines, Antigua and Barbuda, Bahamas, Barbados UN Region Latin America and the Caribbean References OAS Project Database[1] The objective of this program is to "Facilitate the adoption of energy policies and legislation in the seven Project Countries pertaining to address the market conditions for the development and use of renewable energy and energy efficiency systems by mitigating the barriers to their use." References ↑ "OAS Project Database"

51

Sustainable Design | Building Energy Codes Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Design Sustainable Design Session 5 of a seven-part webcast series presented by the Department of Energy's Federal Energy Management Program to help federal agencies comply with the requirements of ASHRAE Standard 90.1-2004. The Sustainable Design webcast provides an overview of sustainable design federal requirements and strategies. Sustainable design principles and practices are well established and can be applied at some level to any project to reduce the environmental impact and operational cost of a building, while increasing occupant satisfaction. The requirements within Executive Order 13423, the Energy Policy Act of 2005, and the Energy Independence and Security Act of 2007 are driving the federal sector to be leaders in sustainable design. Estimated Length:

52

Federal Energy Management Program: Institutional Change for Sustainability  

NLE Websites -- All DOE Office Websites (Extended Search)

Institutional Institutional Change for Sustainability to someone by E-mail Share Federal Energy Management Program: Institutional Change for Sustainability on Facebook Tweet about Federal Energy Management Program: Institutional Change for Sustainability on Twitter Bookmark Federal Energy Management Program: Institutional Change for Sustainability on Google Bookmark Federal Energy Management Program: Institutional Change for Sustainability on Delicious Rank Federal Energy Management Program: Institutional Change for Sustainability on Digg Find More places to share Federal Energy Management Program: Institutional Change for Sustainability on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance Greenhouse Gases Water Efficiency Data Center Energy Efficiency

53

Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable  

NLE Websites -- All DOE Office Websites (Extended Search)

Life Cycle Cost Life Cycle Cost Analysis for Sustainable Buildings to someone by E-mail Share Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on Facebook Tweet about Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on Twitter Bookmark Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on Google Bookmark Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on Delicious Rank Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on Digg Find More places to share Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable Buildings on AddThis.com... Sustainable Buildings & Campuses Basics

54

Federal Energy Management Program: Federal Requirements for Sustainable  

NLE Websites -- All DOE Office Websites (Extended Search)

Federal Federal Requirements for Sustainable Buildings to someone by E-mail Share Federal Energy Management Program: Federal Requirements for Sustainable Buildings on Facebook Tweet about Federal Energy Management Program: Federal Requirements for Sustainable Buildings on Twitter Bookmark Federal Energy Management Program: Federal Requirements for Sustainable Buildings on Google Bookmark Federal Energy Management Program: Federal Requirements for Sustainable Buildings on Delicious Rank Federal Energy Management Program: Federal Requirements for Sustainable Buildings on Digg Find More places to share Federal Energy Management Program: Federal Requirements for Sustainable Buildings on AddThis.com... Sustainable Buildings & Campuses Basics Federal Requirements By Regulation

55

Federal Energy Management Program: Resources on Sustainable Buildings and  

NLE Websites -- All DOE Office Websites (Extended Search)

Resources on Resources on Sustainable Buildings and Campuses to someone by E-mail Share Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on Facebook Tweet about Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on Twitter Bookmark Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on Google Bookmark Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on Delicious Rank Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on Digg Find More places to share Federal Energy Management Program: Resources on Sustainable Buildings and Campuses on AddThis.com... Sustainable Buildings & Campuses Basics Federal Requirements

56

Federal Energy Management Program: Interagency Sustainability Working Group  

NLE Websites -- All DOE Office Websites (Extended Search)

Interagency Interagency Sustainability Working Group to someone by E-mail Share Federal Energy Management Program: Interagency Sustainability Working Group on Facebook Tweet about Federal Energy Management Program: Interagency Sustainability Working Group on Twitter Bookmark Federal Energy Management Program: Interagency Sustainability Working Group on Google Bookmark Federal Energy Management Program: Interagency Sustainability Working Group on Delicious Rank Federal Energy Management Program: Interagency Sustainability Working Group on Digg Find More places to share Federal Energy Management Program: Interagency Sustainability Working Group on AddThis.com... Sustainable Buildings & Campuses Basics Federal Requirements Existing Buildings New Construction & Major Renovations

57

Federal Energy Management Program: Business Case for Sustainable Design in  

NLE Websites -- All DOE Office Websites (Extended Search)

Business Case for Business Case for Sustainable Design in Federal Facilities to someone by E-mail Share Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on Facebook Tweet about Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on Twitter Bookmark Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on Google Bookmark Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on Delicious Rank Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on Digg Find More places to share Federal Energy Management Program: Business Case for Sustainable Design in Federal Facilities on

58

SitesSustainability Outreach Program Brochure | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Brochure Our Goal: Engage in a dialogue and exchange of ideas related to sustainability management practices at DOE. What is Sustainability? A recognized business...

59

Federal Energy Management Program: Benefits of Sustainable Building...  

NLE Websites -- All DOE Office Websites (Extended Search)

Benefits of Sustainable Building Design to someone by E-mail Share Federal Energy Management Program: Benefits of Sustainable Building Design on Facebook Tweet about Federal Energy...

60

Program Sustainability Peer Exchange Call: Transitioning to a...  

NLE Websites -- All DOE Office Websites (Extended Search)

January 17, 2013 Program Sustainability Peer Exchange Call: Transitioning to a Utility Funded Program Environment: What Do I Need To Know? Utility Funded Programming: What Do You...

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

HANFORD SITE SUSTAINABILITY PROGRAM RICHLAND WASHINGTON - 12464  

SciTech Connect

In support of implementation of Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance, the Hanford Site Sustainability Plan was developed to implement strategies and activities required to achieve the prescribed goals in the EO as well as demonstrate measurable progress in environmental stewardship at the Hanford Site. The Hanford Site Sustainability Program was developed to demonstrate progress towards sustainability goals as defined and established in Executive Order (EO) 13514, Federal Leadership in Environmental, Energy and Economic Performance; EO 13423, Strengthening Federal Environmental, Energy and Transportation Management, and several applicable Energy Acts. Multiple initiatives were undertaken in Fiscal Year (FY) 2011 to implement the Program and poise the Hanford Site as a leader in environmental stewardship. In order to implement the Hanford Site Sustainability Program, a Sustainability Plan was developed in conjunction with prime contractors, two U.S. Department of Energy (DOE) Offices, and key stakeholders to serve as the framework for measuring progress towards sustainability goals. Based on the review of these metrics and future plans, several activities were initiated to proactively improve performance or provide alternatives for future consideration contingent on available funding. A review of the key metric associated with energy consumption for the Hanford Site in FY 2010 and 2011 indicated an increase over the target reduction of 3 percent annually from a baseline established in FY 2003 as illustrated in Figure 1. This slight increase was attributed primarily from the increased energy demand from the cleanup projects funded by the American Recovery and Reinvestment Act (ARRA) in FY 2010 and 2011. Although it is forecasted that the energy demand will decrease commensurate with the completion of ARRA projects, several major initiatives were launched to improve energy efficiency.

FRITZ LL

2012-01-12T23:59:59.000Z

62

Federal Energy Management Program: Sustainable Federal Fleets  

NLE Websites -- All DOE Office Websites (Extended Search)

Federal Fleets Federal Fleets The Federal Fleet Program Overview outlines FEMP services and assistance available to Federal fleet managers to increase the use of alternative fuels and advanced vehicles. FEMP's Sustainable Federal Fleets website provides guidance and assistance to help implement Federal legislative and regulatory requirements mandating reduced petroleum consumption and increased alternative fuel use. FEMP's efforts include assisting agencies with implementing and managing energy-efficient and alternative fuel vehicles and facilitating a coordinated effort to reduce petroleum consumption and increase alternative fuel use annually. Content on Sustainable Federal Fleets spans Federal requirements and reporting compliance, alternative fuels and advanced vehicles, fleet performance data, analysis services, information resources, and FEMP contacts.

63

Self-sustaining nuclear pumped laser-fusion reactor experiment  

DOE Green Energy (OSTI)

The features of a neutron feedback nuclear pumped (NFNP) laser-fusion reactor equipment were studied with the intention of establishing the feasibility of the concept. The NFNP laser-fusion concept is compared schematically to electrically pumped laser fusion. The study showed that, once a method of energy storage has been demonstrated, a self-sustaining fusion-fission hybrid reactor with a ''blanket multiplication'' of two would be feasible using nuclear pumped Xe F* excimer lasers having efficiencies of 1 to 2 percent and D-D-T pellets with gains of 50 to 100. (MHR)

Boody, F.P.; Choi, C.K.; Miley, G.H.

1977-01-01T23:59:59.000Z

64

September 18, 2008, Visiting Speakers Program - Sustainability...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waves of Change Sustainability Challenges and the Corporate Response September, 2008 Jeff Erikson, SustainAbility Inc Washington, DC * UK, Europe, US, India * Consulting, research,...

65

ARS Energy Water and Sustainability Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ARS Energy Water and ARS Energy Water and Sustainability Program Sandy Morgan - Facilities Energy Manager * Research Arm of USDA * 3,200 buildings in 106 locations * Annual utility cost $45 million * Labs, greenhouses, animal facilities, agricultural buildings * 13.5 Million SF * $1 billion Agency * 50,000 large animals, 400,000 acres About ARS * Management support * Policies * Taking stock * Outreach * Reporting * Funding - Use UESCs then ESPCs * Network - Facility Energy Managers Our Approach Surveys * Meters - Fuels, account numbers, utilities * Water use * Sustainable buildings - Based on LEED EB V2.0 * Location energy and water consumption * Next surveys - Ag irrigation, land use, animals, refrigerants Lots of Data * Contact utilities - 30 energy audits, 10 UESCs, found a few errors * Contact DLA Energy and GSA

66

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, FEBRUARY 1961  

SciTech Connect

Design, development, and testing efforts were continued on BORAX-V, EBR- I, EBR-II, EBWR, JUGGERNAUT ZPRIII, ZPR-VI, and ZPR-W. An evaluation program is outlined for Pebble Bed Reactor designs. Fast and thermal reactor safety studies were conducted. Experimental and theoretical studies in applied nuclear and reactor physics are dsscribed. Developments made in reactor components, fuels, and materials are discussed. Heat engineering studies were conducted on steam separation, and velocity and void distributions in two-phase systems. Fluidization and fluoride volatility separation, and chemical-metallurgical separation processes were studied. Advanced reactor concepts that were discusssd includsed. Basic Radiation Effects Beactor, Biogeonuclear Reactor, Fast Reactor Test Facility, compact high-power density fast reactors, AHFR hydraulic test loop, Packed Bed Reactor, and direct conversion. (For preceding period see ANL- 6328.) (B.O.G.)

1961-03-15T23:59:59.000Z

67

Robustness of RISMC Insights under Alternative Aleatory/Epistemic Uncertainty Classifications: Draft Report under the Risk-Informed Safety Margin Characterization (RISMC) Pathway of the DOE Light Water Reactor Sustainability Program  

SciTech Connect

The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, would be founded on probabilistic characterizations of uncertainty in SSC performance. In the context of probabilistic risk assessment (PRA) technology, there has arisen a general consensus about the distinctive roles of two types of uncertainty: aleatory and epistemic, where the former represents irreducible, random variability inherent in a system, whereas the latter represents a state of knowledge uncertainty on the part of the analyst about the system which is, in principle, reducible through further research. While there is often some ambiguity about how any one contributing uncertainty in an analysis should be classified, there has nevertheless emerged a broad consensus on the meanings of these uncertainty types in the PRA setting. However, while RISMC methodology shares some features with conventional PRA, it will nevertheless be a distinctive methodology set. Therefore, the paradigms for classification of uncertainty in the PRA setting may not fully port to the RISMC environment. Yet the notion of risk-informed margin is based on the characterization of uncertainty, and it is therefore critical to establish a common understanding of uncertainty in the RISMC setting.

Unwin, Stephen D.; Eslinger, Paul W.; Johnson, Kenneth I.

2012-09-20T23:59:59.000Z

68

Comparison of two different rating programs for sustainable homes  

E-Print Network (OSTI)

This thesis compares two different rating programs for sustainable homes; The Code for Sustainable Homes in the United Kingdom, and LEED for Homes in the United States. The comparison is both in general and with respect ...

Bjarnadottir, Margret Halla

2009-01-01T23:59:59.000Z

69

Light Water Reactor Sustainability (LWRS) Program | Department...  

NLE Websites -- All DOE Office Websites (Extended Search)

the research and development (R&D) projects in the following pathways: Materials Aging and Degradation Assessment, Advanced Instrumentation, Information, and Control Systems...

70

Ensuring the Performance of Nuclear Reactor Pressure Vessels for ...  

Science Conference Proceedings (OSTI)

The Light Water Reactor Sustainability Program is a collaborative program ... and in situ Mechanical Test Methods in the US Fusion Reactor Materials Program.

71

Austria-Program on Technologies for Sustainable Development | Open Energy  

Open Energy Info (EERE)

Austria-Program on Technologies for Sustainable Development Austria-Program on Technologies for Sustainable Development Jump to: navigation, search Name Austria-Program on Technologies for Sustainable Development Agency/Company /Organization Nachhaltig Wirtschaften Sector Energy Focus Area Renewable Energy Topics Background analysis, Technology characterizations Website http://www.nachhaltigwirtschaf Country Austria UN Region Western Europe References Program on Technologies for Sustainable Development[1] Background "This initiative has been developed by the Austrian Federal Ministry of Transport, Innovation and Technology (BMVIT). It initiates and supports trendsetting research and development projects and the implementation of exemplary pilot projects." Objectives "*New opportunities for the economy

72

Chelan County PUD- Sustainable Natural Alternative Power Producers Program  

Energy.gov (U.S. Department of Energy (DOE))

The Sustainable Natural Alternative Power (SNAP) program encourages customers to install alternative power generators such as solar panels and wind turbines and connect them to the District's...

73

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY12.

R. Johansen

2012-09-01T23:59:59.000Z

74

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY13.

R. Johansen

2013-09-01T23:59:59.000Z

75

Sustainable Energy Fund (SEF) Loan Program (PPL Territory) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Energy Fund (SEF) Loan Program (PPL Territory) Sustainable Energy Fund (SEF) Loan Program (PPL Territory) Sustainable Energy Fund (SEF) Loan Program (PPL Territory) < Back Eligibility Agricultural Commercial Industrial Local Government Nonprofit Schools State Government Savings Category Bioenergy Commercial Heating & Cooling Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Water Energy Sources Solar Heating & Cooling Heating Water Heating Wind Maximum Rebate $1 million Program Info State Pennsylvania Program Type Local Loan Program Rebate Amount Varies by project; may provide up to 100% of financing needs Minimum $35,000 direct or $10,000 through an Energy Services Provider (ESP) Provider Sustainable Energy Fund Financing Programs The Sustainable Energy Fund (SEF) promotes and invests in energy efficiency

76

City of San Diego - Sustainable Building Expedited Permit Program |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

San Diego - Sustainable Building Expedited Permit Program San Diego - Sustainable Building Expedited Permit Program City of San Diego - Sustainable Building Expedited Permit Program < Back Eligibility Commercial Industrial Residential Savings Category Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Solar Buying & Making Electricity Program Info Start Date 05/20/2003 State California Program Type Green Building Incentive Provider City of San Diego In 2002, the City of San Diego passed a Resolution R-298001, which amended the [http://dsireusa.org/incentives/incentive.cfm?Incentive_Code=CA42R&re=1&ee=1 Sustainable Building Policy] to allow for expedited permitting for sustainable buildings. Sustainable buildings are defined in Policy Number

77

Federal Energy Management Program: High-Performance Sustainable Building  

NLE Websites -- All DOE Office Websites (Extended Search)

High-Performance High-Performance Sustainable Building Design for New Construction and Major Renovations to someone by E-mail Share Federal Energy Management Program: High-Performance Sustainable Building Design for New Construction and Major Renovations on Facebook Tweet about Federal Energy Management Program: High-Performance Sustainable Building Design for New Construction and Major Renovations on Twitter Bookmark Federal Energy Management Program: High-Performance Sustainable Building Design for New Construction and Major Renovations on Google Bookmark Federal Energy Management Program: High-Performance Sustainable Building Design for New Construction and Major Renovations on Delicious Rank Federal Energy Management Program: High-Performance Sustainable Building Design for New Construction and Major Renovations on Digg

78

Program summary for the Civilian Reactor Development Program  

SciTech Connect

This Civilian Reactor Development Program document has the prime purpose of summarizing the technical programs supported by the FY 1983 budget request. This section provides a statement of the overall program objectives and a general program overview. Section II presents the technical programs in a format intended to show logical technical interrelationships, and does not necessarily follow the structure of the formal budget presentation. Section III presents the technical organization and management structure of the program.

1982-07-01T23:59:59.000Z

79

Federal Energy Management Program: Sustainable Building Basics  

NLE Websites -- All DOE Office Websites (Extended Search)

Basics Basics Image of the side of a sustainable building Sustainable building design results in energy savings and environment stewardship. Sustainable building design and operation strategies demonstrate a commitment to energy efficiency, and environmental stewardship. These approaches result in an optimal balance of energy, cost, environmental, and societal benefits, while still meeting the mission of a Federal agency and the function of the facility or infrastructure. For buildings and facilities, responsible resource management and the assessment of operational impacts encompass the principles of sustainability. Sustainable development aims to meet the needs of the present without compromising future needs. Learn more about the: Benefits of sustainable building design

80

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, SEPTEMBER 1961  

SciTech Connect

BS>Data from examination of blade-type control rods which were used in BORAX are discussed. Operation and maintenance of EBWR is outlined. In work on Borax V, modifications for easier installation of reactor and components is outlined followed by discussion of superheat fuel element development, and fabrication of various reactor components. Borax reactor design is also reported along with information on development and testing. In research on sodiumcooled reactors, activities are summarized in the LPR III and LPR IV programs along with developmental work on EBR I and II. Studies on reactor safety are reported and activities in a program of nuclear technology and general support are outlined. (J.R.D.)

1961-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Miami-Dade County - Sustainable Buildings Program (Florida) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Miami-Dade County - Sustainable Buildings Program (Florida) Miami-Dade County - Sustainable Buildings Program (Florida) Miami-Dade County - Sustainable Buildings Program (Florida) < Back Eligibility Local Government Savings Category Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Program Info State Florida Program Type Energy Standards for Public Buildings Provider Miami-Dade County In 2005, the Miami-Dade Board of County Commissioners passed a [http://www.miamidade.gov/govaction/matter.asp?matter=052213&file=true&ye... resolution] to incorporate sustainable building measures into county facilities. In 2007, Ordinance 07-65 created the Sustainable Buildings Program in the County Code, and Implementing Order 8-8 established specific

82

UNIDO-Training Program on Sustainable Energy Regulation and Policymaking  

Open Energy Info (EERE)

UNIDO-Training Program on Sustainable Energy Regulation and Policymaking UNIDO-Training Program on Sustainable Energy Regulation and Policymaking for Africa Jump to: navigation, search Tool Summary LAUNCH TOOL Name: UNIDO-Training Program on Sustainable Energy Regulation and Policymaking for Africa Agency/Company /Organization: United Nations Industrial Development Organization (UNIDO) Sector: Energy Topics: Implementation, Market analysis, Policies/deployment programs Resource Type: Publications, Guide/manual, Training materials Website: www.unido.org/index.php?id=1000755 UN Region: Eastern Africa, Middle Africa, Northern Africa, Southern Africa, Western Africa UNIDO-Training Program on Sustainable Energy Regulation and Policymaking for Africa Screenshot References: UNIDO-Training Program on Sustainable Energy Regulation and Policymaking for Africa[1]

83

Local Option - Municipal Sustainable Energy Programs | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Municipal Sustainable Energy Programs Municipal Sustainable Energy Programs Local Option - Municipal Sustainable Energy Programs < Back Eligibility Agricultural Commercial Industrial Institutional Multi-Family Residential Nonprofit Residential Savings Category Heating & Cooling Commercial Heating & Cooling Heating Home Weatherization Commercial Weatherization Sealing Your Home Cooling Construction Design & Remodeling Other Windows, Doors, & Skylights Appliances & Electronics Commercial Lighting Lighting Bioenergy Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Solar Water Heating Wind Program Info State New York Program Type PACE Financing '''''Note: The Federal Housing Financing Agency (FHFA) issued a [http://www.fhfa.gov/webfiles/15884/PACESTMT7610.pdf statement] in July

84

N Reactor Deactivation Program Plan. Revision 4  

SciTech Connect

This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.

Walsh, J.L.

1993-12-01T23:59:59.000Z

85

Developmental Light-Water Reactor Program  

SciTech Connect

This report summarizes the progress of the Developmental Light-Water Reactor (DLWR) Program at Oak Ridge National Laboratory in FY 1989. It also includes (1) a brief description of the program, (2) definition of goals, (3) earlier achievements, and (4) proposed future activities.

Forsberg, C.W.

1989-12-01T23:59:59.000Z

86

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research...

87

Sustainable Energy Utility - Residential Energy Efficiency Program...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Refrigerators: 50 Clothes Washers: 50 CFL Lighting: varies by in-store discounts LED Lighting: 5-10 The District of Columbia Sustainable Energy Utility currently offers...

88

Sustained Recycle in Light Water and Sodium-Cooled Reactors  

Science Conference Proceedings (OSTI)

From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of the MOX was varied among Pu, NpPu, NpPuAm, or all-TRU. (All-TRU means all isotopes through Cf-252.) The Pu case was allowed to go to 10% Pu in fresh fuel, but when the minor actinides were included, the transuranic enrichment was kept below 8% to satisfy the expected void reactivity constraint. The uranium portion of the MOX was enriched uranium. That enrichment was increased (to as much as 6.5%) to keep the fuel critical for a typical LWR irradiation. The second approach uses heterogeneous inert matrix fuel (IMF) assemblies in an LWR - a mix of IMF and traditional UOX pins. The uranium-free IMF fuel pins were Pu, NpPu, NpPuAm, or all-TRU. The UOX pins were limited to 4.95% U-235 enrichment. The number of IMF pins was set so that the amount of TRU in discharged fuel from recycle N (from both IMF and UOX pins) was made into the new IMF pins for recycle N+1. Up to 60 of the 264 pins in a fuel assembly were IMF. The assembly-average TRU content was 1-6%. The third approach uses fast reactor oxide fuel in a sodium-cooled fast reactor with transuranic conversion ratio of 0.50 and 1.00. The transuranic conversion ratio is the production of transuranics divided by destruction of transuranics. The FR at CR=0.50 is similar to the CR for the MOX case. The fast reactor cases had a transuranic content of 33-38%, higher than IMF or MOX.

Steven J. Piet; Samuel E. Bays; Michael A. Pope; Gilles J. Youinou

2010-11-01T23:59:59.000Z

89

Okanogan County PUD - Sustainable Natural Alternative Power Program |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Natural Alternative Power Program Sustainable Natural Alternative Power Program Okanogan County PUD - Sustainable Natural Alternative Power Program < Back Eligibility Agricultural Commercial Industrial Local Government Residential Schools State Government Savings Category Bioenergy Solar Buying & Making Electricity Alternative Fuel Vehicles Wind Maximum Rebate 1.00/kWh Program Info State District of Columbia Program Type Performance-Based Incentive Rebate Amount Varies, 0.037/kWh in July 2011 Provider Okanogan County PUD Conservation Department Created in October 2004, Okanogan County PUD's Sustainable Natural Alternative Power Program (SNAP) encourages members to install renewable energy systems by offering an incentive payment based on the system's production on a dollar per kilowatt-hour ($/kWh) basis. SNAP producers also

90

Chelan County PUD - Sustainable Natural Alternative Power Producers Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Natural Alternative Power Producers Sustainable Natural Alternative Power Producers Program Chelan County PUD - Sustainable Natural Alternative Power Producers Program < Back Eligibility Commercial Industrial Local Government Residential Schools State Government Savings Category Bioenergy Buying & Making Electricity Solar Home Weatherization Water Wind Maximum Rebate $1.50/kWh Program Info State District of Columbia Program Type Performance-Based Incentive Rebate Amount Varies; 2012 payment was $0.16/kWh Provider Chelan County Public Utility District The Sustainable Natural Alternative Power (SNAP) program encourages customers to install alternative power generators such as solar panels and wind turbines and connect them to the District's electrical distribution system by offering an incentive payment based on the system's production.

91

Federal Energy Management Program: Resources on Sustainable Buildings and  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Buildings and Campuses Sustainable Buildings and Campuses Building Technology Office Resources The Building Technology Office offers useful resources to plan and implement energy-efficiency projects. Building Energy Software Tools Directory Buildings Performance Database Energy Modeling Software Better Buildings Alliance Webinars Hospital Energy Alliance Videos Solid-State Lighting Technology Fact Sheets Many helpful resources about sustainable buildings and campuses are available. Also see Case Studies. Federal Requirements and Programs Buildings Technologies Program: A U.S. Department of Energy (DOE) program that leads a vast network of research and industry partners to continually develop innovative, cost-effective, energy-saving solutions for buildings. Crosswalk of Sustainability Goals and Targets: A document that features a table listing sustainability goals/targets under the requirement of Executive Order (E.O.) 13514 and E.O. 13423.

92

Sustainable Transportation Program 2011 Annual Report  

DOE Green Energy (OSTI)

Highlights of selected research and development efforts at Oak Ridge National Laboratory funded by the Vehicle Technologies Program, Biomass Program, and Hydrogen and Fuel Cells Program of the Department of Energy, Office of Energy Efficiency and Renewable Energy; and the Department of Transportation.

Vaughan, Kathi H [ORNL

2012-06-01T23:59:59.000Z

93

Sustainable Energy Utility - Residential Energy Efficiency Program...  

Open Energy Info (EERE)

Utility - Residential Energy Efficiency Program (District of Columbia) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump...

94

Federal Energy Management Program: Sustainable Building Case...  

NLE Websites -- All DOE Office Websites (Extended Search)

U.S. Green Building Council that provides third-party verification of green buildings. Living Building Challenge: A philosophy, advocacy, and certification program from the...

95

Lincoln Electric System (Residential)- Sustainable Energy Program  

Energy.gov (U.S. Department of Energy (DOE))

Lincoln Electric System (LES) offers several rebates to residential customers who are interested in upgrading to energy efficient household equipment. The program includes rebates for insulation...

96

Sustainable Transportation Program | Clean Energy | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

by the DOE Office of Energy Efficiency and Renewable Energy, specifically the Vehicle Technologies, Biomass, and Fuel Cell Technologies Programs. The Department of...

97

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT (FOR) JULY 1961  

SciTech Connect

A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)

1961-08-15T23:59:59.000Z

98

FUEL PROGRAMMING FOR SODIUM GRAPHITE REACTORS  

SciTech Connect

The effect of fuel programming, i.e., the scheme used for changing fuel in a core, on the reactivity and specific power of a sodium graphite reactor is discussed Fuel programs considered Include replacing fuel a core-load at a time or a radial zone at a time, replacing fuel to manutain the same average exposure of fuel elements throughout the core, and replacing and transferring fuel elements to maintain more highly exposed fuel in the center or at the periphery of the core. Flux and criticality calculations show the degree of power flattening and the concurrent decrease in effective multiplication which results from maintaining more exposed fuel toward the core center. Corverse effects are shown for the case of maintaining more exposed fuel near the core periphery. The excess reactivity which must be controlled in the various programs is considered. Illustrative schedules for implementing each of these programs in an SGR are presented. (auth)

Connolly, T.J.

1959-10-15T23:59:59.000Z

99

Management of Naval Reactors' Cyber Security Program, OIG-0884  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Naval Reactors' Naval Reactors' Cyber Security Program DOE/IG-0884 April 2013 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 April 12, 2013 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "Management of Naval Reactors' Cyber Security Program" INTRODUCTION AND OBJECTIVE The Naval Reactors Program (Naval Reactors), an organization within the National Nuclear Security Administration, provides the military with safe and reliable nuclear propulsion plants to power warships and submarines. Naval Reactors maintains responsibility for activities supporting the United States Naval fleet nuclear propulsion systems, including research and

100

Program on Technology Innovation: Power Generation and Water Sustainability  

Science Conference Proceedings (OSTI)

This brochure summarizes the Electric Power Research Institute (EPRI) Report 1015371, Program on Technology Innovation: An Energy/Water Sustainability Program for the Electric Power Industry. It presents a research planbased on business, economic, and technical considerationsthat would create and test new technology and science to overcome present and future constraints on thermoelectric and hydroelectric generation resulting from limited fresh water availability. The 10 year plan has an overall budget o...

2007-09-10T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

NextSTEPS (Sustainable Transportation Energy Pathways) PROGRAM SUMMARY  

E-Print Network (OSTI)

NextSTEPS (Sustainable Transportation Energy Pathways) PROGRAM SUMMARY Institute of Transportation and policies that could support their development are often contentious. The future of these fuels and vehicles associated with the transition to new fuels and vehicles, the UC Davis Institute of Transportation Studies

California at Davis, University of

102

Program for Irradiation of Reactor Structural Materials at the ATR ...  

Science Conference Proceedings (OSTI)

Presentation Title, Program for Irradiation of Reactor Structural Materials at the ATR-National Scientific User Facility. Author(s), Heather J. MacLean Chichester,  ...

103

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, MAY 1962  

SciTech Connect

Research progress is reported on water-cooled reactors, liquid-metal- cooled reactors, general reactor technology, plutonium recycle, advanced systems research and development, and nuclear safety. (M.C.G.)

1962-06-15T23:59:59.000Z

104

N reactor standby program plan: Part 2, Transition to standby  

Science Conference Proceedings (OSTI)

The N Reactor Standby Program is the Westinghouse Hanford Company (WHC) program to prepare the N Reactor for cold standby in a cost effective and quality manner with a primary emphasis on safety. The N Reactor Standby Program is comprised of five parts or subprograms, of which the Transition to Standby Program is part two. Transition to Standby is that part of the overall program that encompasses the on-going operational and maintenance activities required to maintain safe control of the reactor and support facilities until their layup is complete. The Transition to Standby Program Plan has been developed to outline the program plans, baselines, and controls to be employed in the management of the Transition to Standby Program. This plan also defines the roles and responsibilities of the major program participants.

Slinn, S.A.

1988-09-01T23:59:59.000Z

105

Federal Energy Management Program: Institutional Change for Sustainability  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainability Sustainability Graphic showing 5 gears. They progress from Determine Goal to Identify Context-Rules, Roles and Tools to Develop Action Plan to Implement Plan to Measure and Evaluate. Institutional Change Continuous Improvement Cycle The Federal Energy Management Program (FEMP) aims to help Federal agencies make sustainability a natural part of how they operate-while continuing to meet their mission goals. Through its Institutional Change activities, FEMP provides guidance and reference materials to help agencies and the myriad organizations within agencies shift their behavior in an effort to save energy and resources now and in the long-term. Institutional change integrates behavior with technologies and policies, recognizing that all three need to align to create make a significant and lasting difference.

106

DOE reactor-pumped laser program  

SciTech Connect

FALCON is a high-power, steady-state, nuclear reactor-pumped laser (RPL) concept that is being developed by the Department of Energy. The FALCON program has experimentally demonstrated reactor-pumped lasing in various mixtures of xenon, argon, neon, and helium at at wavelengths of 585, 703, 725, 1271, 1733, 1792, 2032, 2630, 2650, and 3370 nm with intrinsic efficiency as high as 2.5%. The major strengths of a reactor-pumped laser are continuous high-power operation, modular construction, self-contained power, compact size, and a variety of wavelengths (from visible to infrared). These characteristics suggest numerous applications not easily accessible to other laser types. A ground-based RPL could beam its power to space for such activities as illuminating geosynchronous communication satellites in the earth`s shadow to extend their lives, beaming power to orbital transfer vehicles, removing space debris, and providing power (from earth) to a lunar base during the long lunar night. The compact size and self-contained power also makes an RPL very suitable for ship basing so that power-beaming activities could be situated around the globe. The continuous high power of an RPL opens many potential manufacturing applications such as deep-penetration welding and cutting of thick structures, wide-area hardening of metal surfaces by heat treatment or cladding application, wide-area vapor deposition of ceramics onto metal surfaces, production of sub-micron sized particles for manufacturing of ceramics, wide-area deposition of diamond-like coatings, and 3-D ceramic lithography.

Felty, J.R. [USDOE, Germantown, MD (United States). Defense Programs; Lipinski, R.J.; McArthur, D.A.; Pickard, P.S. [Sandia National Labs., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

107

Austin's Green Building Program: A Tool for Sustainable Development  

E-Print Network (OSTI)

In a new approach to home rating systems, Austin's Green Building Program was designed in 1991 as a marketing approach to encourage builders, architects, and designers to incorporate sustainable building practices, systems, and materials into residential construction. A secondary goal of the program was to encourage "green" business development in the Austin area. A rating system of accumulated points translates to a "sustainability rating" of one to four stars. Four resource areas relating to the home are considered: water, energy, building materials, and solid waste. Seventeen criteria were used to develop points for more than 130 building options listed under the four categories. The criteria for evaluating the options included consideration of the source, process (i.e. from raw material to finished product), use, postlife (recyclability, disposal), integration (with other systems), and difficulty in offering the option. The options are presented in the Green Building Guide, which includes an overview of the program, a discussion of sustainability and local and regional resources, the rating worksheets, and a comprehensive glossary of terns. The Green Building Guide is supplemented by a Sustainable Building Sourcebook which gives more detailed design and source information for each option listed in the Guide. The Green Building Guide is being revised in a simpler format, and the marketing package is being evaluated based upon our experience of the past two years of program operation. The Green Building Program supports participants through general marketing and technical seminars. Response to the Green Building Program has indicated pent-up demand from the market for more environmentally sensitive building practices. Reaction from the building industry has shown a desire for a mechanism to present building and development in a more positive light to an environmentally aware public. The broad acceptance of this strategy was highlighted at the United Nations Conference for Environment and Development (UNCED), called the "Earth Summit," when the Green Building Program was selected as one of twelve finalists worldwide for the United Nations Local Government Honours Programme. The most recent of several awards was the Award for Innovation presented by the Association of Demand Side Management Professionals in November, 1993. This paper will follow the implementation and operation of the Green Building Program, with discussions on the successes, challenges, and modifications of the program since its introduction to the public in early 1992.

Seiter, D. L.

1994-01-01T23:59:59.000Z

108

Roadmap to a Sustainable Structured Trusted Employee Program  

SciTech Connect

Organizations (facility, regulatory agency, or country) have a compelling interest in ensuring that individuals who occupy sensitive positions affording access to chemical biological, radiological and nuclear (CBRN) materials facilities and programs are functioning at their highest level of reliability. Human reliability and human performance relate not only to security but also focus on safety. Reliability has a logical and direct relationship to trustworthiness for the organization is placing trust in their employees to conduct themselves in a secure, safe, and dependable manner. This document focuses on providing an organization with a roadmap to implementing a successful and sustainable Structured Trusted Employee Program (STEP).

Coates, Cameron W [ORNL; Eisele, Gerhard R [ORNL

2013-08-01T23:59:59.000Z

109

REACTOR DEVELOPMENT PROGRAM, PROGRESS REPORT, MAY 1961  

SciTech Connect

General research and development on water-cooled and sodium-cooled reactors are reported along with specific developments on EBWR, BORAK-V, EBR-I, and EBR-H. Thermal and fast reactor safety studies are summarized in terms of fuel-coolant chemical reactions, kinetics of oxidation and ignition of reactor materials, core meltdown studies, and a sodium vapor pressure furnace. Evaluations were made of improved fast reactors for central station power and of a 50-Mwe Prototype Organic Power Reactor (POPR). Developments in instruments, reactcr fuels and materials, reactor components, heat engineering, separations processes, and advanced reactcrs are discussed. (M.C.G.)

1961-06-15T23:59:59.000Z

110

Sustainability Portal  

Science Conference Proceedings (OSTI)

NIST Home > Sustainability Portal. Sustainability Portal. Programs and Projects. Smart Grid Program ... Precision Timing for Smart Grid Systems ...

2013-04-08T23:59:59.000Z

111

RERTR program reduces use of enriched uranium in research reactors  

NLE Websites -- All DOE Office Websites (Extended Search)

RERTR program reduces use of enriched uranium in research reactors RERTR program reduces use of enriched uranium in research reactors worldwide Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share RERTR program reduces use of enriched uranium in research reactors worldwide The High Flux Reactor in Petten, the Netherlands READY TO CONVERT - The High Flux Reactor in Petten, the Netherlands, has

112

Asia Sustainable and Alternative Energy Program | Open Energy Information  

Open Energy Info (EERE)

Alternative Energy Program Alternative Energy Program Jump to: navigation, search Logo: Asia Sustainable and Alternative Energy Program Name Asia Sustainable and Alternative Energy Program Agency/Company /Organization World Bank Sector Energy Focus Area Energy Efficiency, Renewable Energy Topics Market analysis, Resource assessment, Background analysis Website http://www.worldbank.org/astae UN Region Central Asia, "East Asia" is not in the list of possible values (Eastern Africa, Middle Africa, Northern Africa, Southern Africa, Western Africa, Caribbean, Central America, South America, Northern America, Central Asia, Eastern Asia, Southern Asia, South-Eastern Asia, Western Asia, Eastern Europe, Northern Europe, Southern Europe, Western Europe, Australia and New Zealand, Melanesia, Micronesia, Polynesia, Latin America and the Caribbean) for this property., "SE Asia" is not in the list of possible values (Eastern Africa, Middle Africa, Northern Africa, Southern Africa, Western Africa, Caribbean, Central America, South America, Northern America, Central Asia, Eastern Asia, Southern Asia, South-Eastern Asia, Western Asia, Eastern Europe, Northern Europe, Southern Europe, Western Europe, Australia and New Zealand, Melanesia, Micronesia, Polynesia, Latin America and the Caribbean) for this property.

113

Labs21 sustainable design programming checklist version 1.0  

SciTech Connect

This checklist of sustainable design objectives and strategies can be used in the programming and conceptual design phases of a laboratory project. It includes the following: (1) Brief descriptions of each objective and strategy. (2) Metrics for each objective. This checklist is primarily to be used by owners, architects and engineers during the programming and conceptual design phase of a project. It is especially appropriate for use in design charrettes. The strategies and metrics can be included as requirements in the programming document or can be identified for further analysis or consideration during the design development phase. This checklist is hierarchically organized into design areas, objectives for each design area, and strategies and metrics for each objective. The design areas generally correspond to the design areas of the LEED(TM) rating system from the U.S. Green Building Council.

Mathew, Paul; Greenberg, Steve

2005-01-07T23:59:59.000Z

114

CIVILIAN POWER REACTOR PROGRAM. PART III. BOOK I. STATUS REPORT ON FAST REACTORS AS OF 1959  

SciTech Connect

A description of fast reactor types is given and the objectives of the AEC program on fast reactors are outlined. General research and development programs completed and in process on physics, fuel and materials, heat transfer, fluid flow, coolant chemistry, reactor safety, and components and systems are discussed. Reactors completed, under design and construction, and under study are described. (W.D.M.) A general description of ship and power plant, tabulation of principle characteristics, economics, potential advances, and necessary research and development are discussed in detail. (W.D.M.)

1960-01-01T23:59:59.000Z

115

CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM. HEAVY WATER-MODERATED POWER REACTOR  

SciTech Connect

The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)

Hutton, J.H.; Davis, S.A.; Graves, C.C.; Duffy, J.G. comps.

1960-08-19T23:59:59.000Z

116

Fast Reactor Technology: A Path to Long-Term Energy Sustainability Position Statement  

E-Print Network (OSTI)

The American Nuclear Society believes that the development and deployment of advanced nuclear reactors based on fast-neutron fission technology is important to the sustainability, reliability, and security of the world’s long-term energy supply. Of the known and proven energy technologies, only nuclear fission can provide the large quantities of energy required by industrial societies in a sustainable and environmentally acceptable manner. Natural uranium mined from the earth's crust is composed primarily of two isotopes: 99.3 % is U-238, and 0.7 % is the fissile U-235. Nearly all current power reactors are of the “thermal neutron” design, and their capability to extract the potential energy in the uranium fuel is limited to less than 1 % of that available. The remainder of the potential energy is left unused in the spent fuel and in the uranium, depleted in U-235, that remains from the process of enriching the natural uranium in the isotope U-235 for use in thermal reactors. With known fast reactor technology, this unutilized energy can be harvested, thereby extending by a hundred-fold the amount of energy extracted from the same amount of mined uranium. Fast reactors can convert U-238 into fissile material at rates faster than it is consumed making it economically feasible to utilize ores with very low uranium concentrations and potentially even

unknown authors

2005-01-01T23:59:59.000Z

117

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, FEBRUARY 1962  

SciTech Connect

Progress is reported on EBWR, BORAX-V, and development of liquid metal cooled reactors including EBR-I and -II. Developments in general reactor technology are reported in sections on physics, fuels, components, materials, engineering, and chemical separations. Other research and development is reported in advanced systems and nuclear ssfety. (J.R.D.)

1962-02-01T23:59:59.000Z

118

Establishment of a Hub for the Light Water Reactor Sustainability Online Monitoring Community  

Science Conference Proceedings (OSTI)

Implementation of online monitoring and prognostics in existing U.S. nuclear power plants will involve coordinating the efforts of national laboratories, utilities, universities, and private companies. Internet-based collaborative work environments provide necessary communication tools to facilitate interaction between geographically diverse participants. Available technologies were considered, and a collaborative workspace was established at INL as a hub for the light water reactor sustainability online monitoring community.

Nancy J. Lybeck; Magdy S. Tawfik; Binh T. Pham

2011-08-01T23:59:59.000Z

119

Federal Energy Management Program: Benefits of Sustainable Building...  

NLE Websites -- All DOE Office Websites (Extended Search)

Benefits of Sustainable Building Design The application of sustainable building design not only helps Federal facilities meet laws and regulations, it also provides them with many...

120

Reactor Safety Research Programs Quarterly Report October - December 1980  

SciTech Connect

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from October 1 through December 31, 1980, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining structural graphite strength, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NOE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation and postaccident coolability tests for the ESSOR Test Reactor Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S K

1981-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Reactor Safety Research Programs Quarterly Report July - September 1981  

SciTech Connect

This document summarizes the work performed by Pacific Northwest laboratory (PNL) from July 1 through September 30, 1981, for the Division of Accident Evaluation, U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR} steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-of-coolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, lspra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1982-01-01T23:59:59.000Z

122

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, OCTOBER 1962  

SciTech Connect

Technical progress in specific reactor projects and in general engineering research and development is reported. The information is presented in five main sections for each of which a separate abstract was prepared. (J.R.D.)

1962-11-15T23:59:59.000Z

123

The Ural Electrochemical Integrated Plant Sustainability Program of Nuclear Material Protection, Control and Accounting System Upgrades  

Science Conference Proceedings (OSTI)

UEIP has been working on a comprehensive sustainability program that includes establishing a site sustainability working group, information gathering, planning, organizing, developing schedule and estimated costs, trhough joint UEIP-US DOE/NNSA National Laboratory sustainability contracts. Considerable efforts have been necessary in the sustainability planning, monitoring, and control of the scope of work using tools such as Microsoft Excel, Microsoft Project and SAP R/3. While information interchanges within the sustainability program provides adequate US assurances that US funds are well spent through its quarterly reporting methodology, proper information security and protection measures are taken throughout the process. Decommissioning of outdated equipment has also become part of determining sustainability requirements and processes. The site’s sustainability program has facilitated the development of a transition plan toward eventual full Russian funding of sustaining nuclear security upgrades.

Vakhonin, Alexander; Yuldashev, Rashid; Dabbs, Richard D.; Carroll, Michael F.; Garrett, Albert G.; Patrick, Scott W.; Ku, Eshter M.

2009-09-30T23:59:59.000Z

124

Advanced reactor development: The LMR integral fast reactor program at Argonne  

SciTech Connect

Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs.

Till, C.E.

1990-01-01T23:59:59.000Z

125

N reactor standby program plan: Part 3, Standby and surveillance  

Science Conference Proceedings (OSTI)

The N Reactor Standby Program Summary Plan is a description of the general policy and guidelines to be followed in placing the N Reactor in cold standby status. That Plan defines a number of objectives and activities necessary to achieve this goal. One of these activities is to layup the N Reactor operating systems in a cost-effective manner such that its safe restart may be assured. The Program Summary Plan has defined this activity as Standby and Surveillance and has directed that a Standby and Surveillance Program Plan be prepared to define and plan all of the activities necessary to accomplish this objective. This Plan responds to that commitment and supports the related policies and guidelines contained in the referenced Plan. In a manner similar to the referenced Program Plan, the Standby and Surveillance Program Plan is a description of the policies, guidelines, and methods of implementation to layup the N Reactor systems for cold standby. Accordingly, this Plan: Provides mission and objectives to guide system layup activities; Provides assumptions and criteria for layup; Defines the methodology for formulating the Program; Defines Program Baselines; Defines the method of performance of the Program; Provides for management, administrative control, and reporting requirements. Supporting details to these major elements of the Standby and Surveillance Program Plan are contained in the following sections.

NONE

1988-08-01T23:59:59.000Z

126

Materials Reliability Program: Pressurized Water Reactor Internals Aging Management Program Development Template (MRP-342)  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) has completed and published guidance for managing the effects of aging degradation in pressurized water reactor (PWR) internals. The initial version of this report, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 0), was submitted to the staff of the U. S. Nuclear Regulatory Commission (NRC) ...

2012-10-23T23:59:59.000Z

127

Materials Reliability Program: San Onofre Nuclear Generating Station Reactor Vessel Internals Management Engineering Program (MRP-303)  

Science Conference Proceedings (OSTI)

All operating pressurized water reactors must have a reactor vessel internals aging management document in place by December 2011 according to the mandatory requirement under Nuclear Energy Institute (NEI) 03-08. This program should be developed to meet the guidance provided by Materials Reliability Program (MRP) -227, Rev. 0, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. For non-license renewal plants, the requirements are valid within the current license period, and the Elec...

2011-02-28T23:59:59.000Z

128

Sustainability of irrigated farming systems in a Tunisian region: A recursive stochastic programming analysis  

Science Conference Proceedings (OSTI)

The aim of this study was to evaluate the sustainability of farm irrigation systems in the Cebalat district in northern Tunisia. It addressed the challenging topic of sustainable agriculture through a bio-economic approach linking a biophysical model ... Keywords: Bio-economic modeling, Farmers' decisions, Farming system, Recursive stochastic programming, Sustainable agriculture

H. Belhouchette; M. Blanco; J. Wery; G. Flichman

2012-08-01T23:59:59.000Z

129

Present Status Of Research Reactor Decommissioning Program In Indonesia  

E-Print Network (OSTI)

At present, Indonesia has 3 research reactors: MTR-type multipurpose reactor of 30 MW at Serpong site, TRIGA-type research reactor of 1 MW at Bandung site, and small TRIGA - type reactor of 100 kW at Yogyakarta Research Center. The oldest one is the TRIGA reactor at Bandung site, which went critical at 250 kW in 1964, then was operated at maximum of 1000 kW by 1971. The reactor has operated for a total of 35 years. There is no decision for decommissioning this reactor; however, slowly but surely, it will be an object for a near-future decommissioning program. Anticipation of the situation is necessary. For the Indonesian case, early decommissioning strategy for a research reactor and restricted use of the site for another nuclear installation is favorable under high land pricing, availability of radwaste repository, and cost analysis. Graphite from Triga reactor reflector is recommended for direct disposal after conditioning, without volume reduction treatment. Development of human ...

Mulyanto And Gunandjar

2000-01-01T23:59:59.000Z

130

Foreign Research Reactor Spent Nuclear Fuel Acceptance Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Global Threat Reduction Initiative: Global Threat Reduction Initiative: U.S. Nuclear Remove Program Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance 2007 DOE TEC Meeting Chuck Messick DOE/NNSA/SRS 2 Contents * Program Objective and Policy * Program implementation status * Shipment Information * Operational Logistics * Lessons Learned * Conclusion 3 U.S. Nuclear Remove Program Objective * To play a key role in the Global Threat Reduction Remove Program supporting permanent threat reduction by accepting program eligible material. * Works in conjunction with the Global Threat Reduction Convert Program to accept program eligible material as an incentive to core conversion providing a disposition path for HEU and LEU during the life of the Acceptance Program. 4 Reasons for the Policy

131

THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM  

SciTech Connect

LIUM OXIDE REACTOR. MARITIME GAS-COOLED The Experimental Beryllium Oxide Reactor, EBOR, will be constructed at the National Reactor Testing Station as the AEC portion of the joint Maritime Administration--AEC Maritime Gas Cooled Reactor Program. The ultimate goal of the Program is the development of nuclear power plants employing a helium cooled and beryllium oxide moderated reactor directly coupled to a closed cycle gas turbine. The objective is to obtain compact nuclear engines suitable for use either in a merchant ship propulsion system or an intermediate size central station power plant in the 20 to 100 Mw(e) size range. The EBOR is a l0 Mw(t) test of the basic fuel element and moderator designs. It is capable of being up-graded in power at a later date to a test of the nuclear reactor turbine concept. The objective of the experiment is outlined. The principal reactor components to be tested and the test facility are described. (auth)

Moore, W.C.

1961-07-01T23:59:59.000Z

132

Federal Energy Management Program: Business Case for Sustainable...  

NLE Websites -- All DOE Office Websites (Extended Search)

Facilities full document. Contact For additional information about The Business Case for Sustainable Design in Federal Facilities, contact Sarah Jensen. Contacts | Web Site...

133

EBR-2 (Experimental Breeder Reactor-2) test programs  

SciTech Connect

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs.

Sackett, J.I.; Lehto, W.K.; Lindsay, R.W. (Argonne National Lab., Idaho Falls, ID (USA)); Planchon, H.P.; Lambert, J.D.B.; Hill, D.J. (Argonne National Lab., IL (USA))

1990-01-01T23:59:59.000Z

134

TEN-YEAR SODIUM-REACTOR DEVELOPMENT PROGRAM  

SciTech Connect

>A 10-year program of development and construction of large-scale, sodium-cooled reactors is summarized. The current state of development of the SGR and its associated components is sufficiently advanced to permit construction of economic plants within the 10-year period. Two advanced Sodium Reactor concepts are presented. A construction program involving two reactor experiments and two full-scale plants with a capacity of 550 Mwe, together with associated development, is estimated to cost 6 million. Of this amount approximately 06 million would be borne by the AEC and the remainder by power utility companies. Escalation and construction loan interest charges are included in these figures. The cost of power from the larger power plant would be approximately 6 mills/kw-hr, based on 1959 dollars. (auth)

1959-04-11T23:59:59.000Z

135

Integral Fast Reactor Program. Annual progress report, FY 1993  

Science Conference Proceedings (OSTI)

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1994-10-01T23:59:59.000Z

136

Integral Fast Reactor Program annual progress report, FY 1994  

Science Conference Proceedings (OSTI)

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R&D.

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

1994-12-01T23:59:59.000Z

137

Integral Fast Reactor Program. Annual progress report, FY 1992  

Science Conference Proceedings (OSTI)

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1993-06-01T23:59:59.000Z

138

Federal Energy Management Program: High-Performance Sustainable Building  

NLE Websites -- All DOE Office Websites (Extended Search)

High-Performance Sustainable Building Design for New Construction and Major Renovations High-Performance Sustainable Building Design for New Construction and Major Renovations New construction and major renovations to existing buildings offer Federal agencies opportunities to create sustainable high-performance buildings. High-performance buildings can incorporate energy-efficient designs, sustainable siting and materials, and renewable energy technologies along with other innovative strategies. Also see Guiding Principles for Federal Leadership in High-Performance and Sustainable Buildings. Performance-Based Design Build Typically, architects, engineers, and project managers consider the potential to build a high-performance building to be limited by the initial cost. A different approach-performance-based design build-makes high performance the priority, from start to finish. Contracts are developed that focus on both limiting construction costs and meeting performance targets. The approach is not a source of funding, but rather a strategy to make the most out of limited, appropriated, funds.

139

Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)  

Science Conference Proceedings (OSTI)

The Materials Reliability Program (MRP) developed inspection and evaluation (I&E) guidelines for managing long-term aging reactor vessel internal components of pressurized water reactors (PWRs) reactor internals. Specifically, the guidelines are applicable to reactor vessel internal structural components; they do not address fuel assemblies, reactivity control assemblies, or welded attachments to the reactor vessel.

2011-12-23T23:59:59.000Z

140

EBR-2 (Experimental Breeder Reactor-2), IFR (Integral Fast Reactor) prototype testing programs  

SciTech Connect

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development. (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs.

Lehto, W.K.; Sackett, J.I.; Lindsay, R.W. (Argonne National Lab., Idaho Falls, ID (USA). EBR-II Div. Argonne National Lab., IL (USA)); Planchon, H.P.; Lambert, J.D.B. (Argonne National Lab., IL (USA))

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

The DOE Advanced Gas Reactor Fuel Development and Qualification Program  

Science Conference Proceedings (OSTI)

The high outlet temperatures and high thermal-energy conversion efficiency of modular High Temperature Gas-cooled Reactors (HTGRs) enable an efficient and cost effective integration of the reactor system with non-electricity generation applications, such as process heat and/or hydrogen production, for the many petrochemical and other industrial processes that require temperatures between 300°C and 900°C. The Department of Energy (DOE) has selected the HTGR concept for the Next Generation Nuclear Plant (NGNP) Project as a transformative application of nuclear energy that will demonstrate emissions-free nuclear-assisted electricity, process heat, and hydrogen production, thereby reducing greenhouse-gas emissions and enhancing energy security. The objective of the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification program is to qualify tristructural isotropic (TRISO)-coated particle fuel for use in HTGRs. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission-product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete, fundamental understanding of the relationship between the fuel fabrication process and key fuel properties, the irradiation and accident safety performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. An overview of the program and recent progress is presented.

David Petti

2010-09-01T23:59:59.000Z

142

City of San Diego- Sustainable Building Expedited Permit Program  

Energy.gov (U.S. Department of Energy (DOE))

In 2002, the City of San Diego passed a Resolution R-298001, which amended the [http://dsireusa.org/incentives/incentive.cfm?Incentive_Code=CA42R&re=1&ee=1 Sustainable Building Policy] to...

143

The Westinghouse Electric Corporation Reactor Vessel Radiation Surveillance Program  

Science Conference Proceedings (OSTI)

Westinghouse recognized that the disruption of the atomic lattice of metals by collision from energetic neutrons could alter the properties of the metals to such an extent that the changes could be of engineering significance. Furthermore, it was recognized that a physical-metallurgical phenomenon such as aging, both thermal and mechanical, also could alter the properties of a metal over its service life. Because of the potential changes in properties, reactor vessel radiation surveillance programs to monitor the effect of neutron radiation and other environmental factors on the reactor vessel materials during operational conditions over the life of the plant were initiated for Westinghouse plants with the insertion of reactor vessel material radiation surveillance capsules into the Yankee Atomic Company's Yankee Rowe plant in 1961.

Mayer, T.R.; Anderson, S.L.; Yanichko, S.E.

1983-01-01T23:59:59.000Z

144

Topic: Sustainable Manufacturing  

Science Conference Proceedings (OSTI)

... Project. Sustainable Manufacturing Program. Sustainability Characterization for Product Assembly Processes Project. Testbed ...

2012-09-19T23:59:59.000Z

145

Space reactor system and subsystem investigations: assessment of technology issues for the reactor and shield subsystem. SP-100 Program  

SciTech Connect

As part of Rockwell's effort on the SP-100 Program, preliminary assessment has been completed of current nuclear technology as it relates to candidate reactor/shield subsystems for the SP-100 Program. The scope of the assessment was confined to the nuclear package (to the reactor and shield subsystems). The nine generic reactor subsystems presented in Rockwell's Subsystem Technology Assessment Report, ESG-DOE-13398, were addressed for the assessment.

Atkins, D.F.; Lillie, A.F.

1983-06-30T23:59:59.000Z

146

Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies  

SciTech Connect

The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U.S. Department of Energy (DOE). The program is operated in close collaboration with industry R&D programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of Nuclear Power Plants that are currently in operation. The LWRS Program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy and environmental security. Advanced instruments and control (I&C) technologies are needed to support the safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear assets. It also requires that approaches be developed and proven to achieve sustainability of I&C systems throughout the period of extended operation. The strategic objective of the LWRS Program Advanced Instrumentation, Information, and Control Systems Technology R&D pathway is to establish a technical basis for new technologies needed to achieve safety and reliability of operating nuclear assets and to implement new technologies in nuclear energy systems. This will be achieved by carrying out a program of R&D to develop scientific knowledge in the areas of: • Sensors, diagnostics, and prognostics to support characterization and prediction of the effects of aging and degradation phenomena effects on critical systems, structures, and components (SSCs) • Online monitoring of SSCs and active components, generation of information, and methods to analyze and employ online monitoring information • New methods for visualization, integration, and information use to enhance state awareness and leverage expertise to achieve safer, more readily available electricity generation. As an initial step in accomplishing this effort, the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies was held March 20–21, 2009, in Columbus, Ohio, to enable industry stakeholders and researchers in identification of the nuclear industry’s needs in the areas of future I&C technologies and corresponding technology gaps and research capabilities. Approaches for collaboration to bridge or fill the technology gaps were presented and R&D activities and priorities recommended. This report documents the presentations and discussions of the workshop and is intended to serve as a basis for the plan under development to achieve the goals of the I&C research pathway.

Bruce P. Hallbert; J. J. Persensky; Carol Smidts; Tunc Aldemir; Joseph Naser

2009-08-01T23:59:59.000Z

147

UNIDO-Training Program on Sustainable Energy Regulation and Policymaki...  

Open Energy Info (EERE)

Industrial Development Organization (UNIDO) Sector: Energy Topics: Implementation, Market analysis, Policiesdeployment programs Resource Type: Publications, Guidemanual,...

148

A reactor core on-line monitoring program - COMP  

Science Conference Proceedings (OSTI)

A program named COMP is developed for on-line monitoring PWRs' in-core power distribution in this paper. Harmonics expansion method is used in COMP. The Unit 1 reactor of Daya Bay Nuclear Power Plant (Daya Bay NPP) in China is considered for verification. The numerical results show that the maximum relative error between measurement and reconstruction results from COMP is less than 5%, and the computing time is short, indicating that COMP is capable for online monitoring PWRs. (authors)

Wang, C. [State Nuclear Power Software Development Center, Beijing, 100029 (China); School of Nuclear Science and Technology, Xi'an Jiaotong Univ. (China); Building 1, Compound No.29, North Third Ring Road, Xicheng District, Beijing, 100029 (China); Wu, H.; Cao, L. [School of Nuclear Science and Technology, Xi'an Jiaotong Univ. (China)

2012-07-01T23:59:59.000Z

149

Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials  

Science Conference Proceedings (OSTI)

Since 2002, the Department of Energy's (DOE's) Generation IV Nuclear Energy Systems (Gen IV) Program has addressed the research and development (R&D) necessary to support next-generation nuclear energy systems. The six most promising systems identified for next-generation nuclear energy are described within this roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor-SCWR and the Very High Temperature Reactor-VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor-GFR, the Lead-cooled Fast Reactor-LFR, and the Sodium-cooled Fast Reactor-SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides and may provide an alternative to accelerator-driven systems. At the inception of DOE's Gen IV program, it was decided to significantly pursue five of the six concepts identified in the Gen IV roadmap to determine which of them was most appropriate to meet the needs of future U.S. nuclear power generation. In particular, evaluation of the highly efficient thermal SCWR and VHTR reactors was initiated primarily for energy production, and evaluation of the three fast reactor concepts, SFR, LFR, and GFR, was begun to assess viability for both energy production and their potential contribution to closing the fuel cycle. Within the Gen IV Program itself, only the VHTR class of reactors was selected for continued development. Hence, this document will address the multiple activities under the Gen IV program that contribute to the development of the VHTR. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. The focus of this document will be the overall range of DOE's structural materials research activities being conducted to support VHTR development. By far, the largest portion of material's R&D supporting VHTR development is that being performed directly as part of the Next-Generation Nuclear Plant (NGNP) Project. Supplementary VHTR materials R&D being performed in the DOE program, including university and international research programs and that being performed under direct contracts with the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, will also be described. Specific areas of high-priority materials research that will be needed to deploy the NGNP and provide a basis for subsequent VHTRs are described, including the following: (1) Graphite: (a) Extensive unirradiated materials characterization and assessment of irradiation effects on properties must be performed to qualify new grades of graphite for nuclear service, including thermo-physical and mechanical properties and their changes, statistical variations from billot-to-billot and lot-to-lot, creep, and especially, irradiation creep. (b) Predictive models, as well as codification of the requirements and design methods for graphite core supports, must be developed to provide a basis for licensing. (2) Ceramics: Both fibrous and load-bearing ceramics must be qualified for environmental and radiation service as insulating materials. (3) Ceramic Composites: Carbon-carbon and SiC-SiC composites must be qualified for specialized usage in selected high-temperature components, such as core stabilizers, control rods, and insulating covers and ducting. This will require development of component-specific designs and fabrication processes, materials characterization, assessment of environmental and irradiation effects, and establishment of codes and standards for materials testing and design requirements. (4) Pressure Vessel Steels: (a) Qualification of short-term, high-temperature properties of light water rea

Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Katoh, Yutai [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Wilson, Dane F [ORNL

2008-08-01T23:59:59.000Z

150

Federal Energy Management Program: Energy Security Planning for Sustainable  

NLE Websites -- All DOE Office Websites (Extended Search)

Security Planning for Sustainable Buildings Security Planning for Sustainable Buildings For energy security, Federal facility managers have a responsibility to consider a broad array of potential threats and incident scenarios. An underlying process or methodology is essential to comprehensively and intelligently address all elements of energy security analysis. Given recent blackouts and concerns about vulnerable infrastructure, many public and private organizations are taking steps to ensure reliable power and continuity of operations in the event of future outages. Some government facilities have the capacity to survive short-term power outages, but are now evaluating whether their back-up power capabilities are sufficient to serve their most critical needs during a prolonged outage.

151

CALTECH SUSTAINABILITY CALTECH ENERGY CONSERVATION INVESTMENT PROGRAM (CECIP)  

E-Print Network (OSTI)

absorption Placing LED signage standard throughout campus Increasing diameter of distribution pumping replacement program Replacing existing air handling equipment with high efficiency chillers and motors Click

Tai, Yu-Chong

152

CIVILIAN POWER REACTOR PROGRAM. PART I. SUMMARY OF TECHNICAL AND ECONOMIC STATUS AS OF 1959  

SciTech Connect

The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)

1960-01-01T23:59:59.000Z

153

Federal Energy Management Program: Life Cycle Cost Analysis for Sustainable  

NLE Websites -- All DOE Office Websites (Extended Search)

Life Cycle Cost Analysis for Sustainable Buildings Life Cycle Cost Analysis for Sustainable Buildings To help facility managers make sound decisions, FEMP provides guidance and resources on applying life cycle cost analysis (LCCA) to evaluate the cost-effectiveness of energy and water efficiency investments. Federal Requirements Life cycle cost (LCC) rules are promulgated in 10 CFR 436 A, Life Cycle Cost Methodology and Procedures and conforms to requirements in the National Energy Conservation Policy Act and subsequent energy conservation legislation as well as Executive Order 13423. The LCC guidance and materials provided here assume discount rates and energy price projections (TXT 17 KB) determined annually by FEMP and the Energy Information Administration. Building Life Cycle Cost Software FEMP's Building Life Cycle Cost (BLCC) software can help you calculate life cycle costs, net savings, savings-to-investment ratio, internal rate of return, and payback period for Federal energy and water conservation projects funded by agencies or alternatively financed. BLCC also estimates emissions and emission reductions. An energy escalation rate calculator (EERC) computes an average escalation rate for energy savings performance contracts when payments are based on energy cost savings.

154

Sustainable Manufacturing in the Systems Integration Division  

Science Conference Proceedings (OSTI)

... Sustainability Modeling and Optimization Project. Sustainability of Unit Manufacturing Processes Project. Sustainable Manufacturing Program. ...

2011-12-23T23:59:59.000Z

155

N Reactor Standby Program plan, Part 2: Transition to standby; Revision 1  

Science Conference Proceedings (OSTI)

The N Reactor Standby Program is the Westinghouse Hanford Company (WHC) program to prepare the N Reactor for cold standby in a cost effective and quality manner with a primary emphasis on safety. The N Reactor Standby Program is comprised of five parts or sub-programs, of which the Transition to Standby Program is part two. Transition to Standby is that part of the overall program that encompasses the on-going operational and maintenance activities required to maintain safe control of the reactor and support facilities until their layup is complete. The Transition to Standby Program Plan has been developed to outline the program plans, baselines, and controls to be employed in the management of the Transition to Standby Program. This plan also defines the roles and responsibilities of the major program participants.

NONE

1989-12-01T23:59:59.000Z

156

Procuring Architectural and Engineering Services for Energy Efficiency and Sustainability (Book), Federal Energy Management Program (FEMP)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Procuring Architectural Procuring Architectural and Engineering Services for Energy Efficiency and Sustainability A Resource Guide for Federal Construction Project Managers U.S. Department of Energy Energy Efficiency and Renewable Energy Federal Energy Management Program FEDERAL ENERGY MANAGEMENT PROGRAM Procuring Architectural and Engineering Services for Energy Efficiency and Sustainability: A Resource Guide for Federal Construction Project Managers NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, appa-

157

September 18, 2008, Visiting Speakers Program - SustainAbility - Companion Book  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8, 2008 8, 2008 U.S. Department of Energy Washington, DC Office of Health, Safety and Security ; shareholders and stakeholders. The HSS Focus Group HSS believes an Glenn S. Podonsky Chief Health, Safety and Security Officer The Office of Health, Safety and Security (HSS) is the Department of Energy's (DOE) corporate organization responsible for health, safety, environment, and security providing corporate leadership and strategic vision to coordinate and integrate these vital programs. HSS is responsible for policy development and technical assistance; corporate analysis; corporate safety and security programs; education and training; complex-wide independent oversight; and enforcement. The Chief Health, Safety and Security Officer advises the Secretary and the Deputy Secretary on all matters related to

158

GENERAL REACTOR ANALYSIS COMPUTER PROGRAM FOR THE IBM 704, PROGRAM GEORGE  

SciTech Connect

Program George is an IBM 704 ccde that combines standard ANPD reactor analysis methcds for computing multiplication constant and spatial distribution of flux and power, as well as other nuclear parameters, in aircraft (heterogeneous) reactors. The elapsed time and the chance for human error between initial input and final output are greatly reduced in Program George. A matched set of reflector savings for a reflected, cylindrical core, which was formerly obtained by hand, is now computed by the program. In the C/sub 2/ pcrtion of Program George, the ccde computes the neutron slowingdown density and flux at 19 lethargy levels plus a thermal group in bare, homogeneous compositions with normal mode, ene ngy-dependent bucklings. The diffusion coefficient contains a transport correction as well as a Behrens correction for heterogeneous structure. Flux-depression factors at thermal and two epithermal levels are computed in annular, cylindrical geometry by one-energy, P/sub 3/ transport theory approximation in the I/sub 2/ pontion of the program, or they may be given as input. Flux weighting of various cross sections, transmission factors, and other parameters are computed in a multigroup representation. Two-energy-group constants from the regional compositions are supplied in the F/sub 2/ portion of the program, in which a two-energy group, one-space-dimensional, multiregion diffusion calculation yields multiplication constant, normalized fission density, fast flux, and slow flux in each onedimensional reactor pontrayed. If a reactivity match is requested, the reflector savings of the specified compositions are adjusted until the multiplication constant i n the radial F/sub 2/, longitudinal F/sub 2/, and the reference bare equivalent core of a cylindrical reflected reactor converge to the same value. (auth)

Hoffman, T.A.; Henderson, W.B.

1959-10-01T23:59:59.000Z

159

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program.  

E-Print Network (OSTI)

??This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to… (more)

[No author

2006-01-01T23:59:59.000Z

160

Gas-Cooled Fast Reactor Program. Annual progress report for period ending December 31, 1979  

SciTech Connect

Information on the GCFR reactor is presented concerning the Core Flow Test Loop; shielding and physics; pressure vessel and closure studies; and irradiation program.

Gat, U.; Kasten, P.R.

1980-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World Record For Irradiation Performance Advanced Gas Reactor Fuel Program's TRISO Particle Fuel Sets A New World Record For Irradiation Performance November 16, 2009 - 1:12pm Addthis As part of the Office of Nuclear Energy's Next Generation Nuclear Plant (NGNP) Program, the Advanced Gas Reactor (AGR) Fuel Development Program has achieved a new international record for irradiation testing of next-generation particle fuel for use in high temperature gas reactors (HTGRs). The AGR Fuel Development Program was initiated by the Department of Energy in 2002 to develop the advanced fabrication and characterization technologies, and provide irradiation and safety performance data required to license TRISO particle fuel for the NGNP and future HTGRs. The AGR

162

VARIABLE MODERATOR REACTOR DEVELOPMENT PROGRAM. Quarterly Progress Report No. 1  

SciTech Connect

Development of the boiling water UO/sub 2/ fueled Variable Moderator Reactor (VMR) is conducted under contract for the USAEC. The initiation and progress of work under Phase I of the contract, Physics and Kinetic Analysis and Initial Evaluation,'' and the preparation for Phase II, Critical Experiment and Analysis of Results,'' are reported. A hydrodynamic flow sheet representing the sequence of calculations for the BOCH program was prepared. A preliminary block diagram of the kinetics model of the VMR was prepared. Work is reported on the PUREE code which is designed to give an accurate representation of the physics of the VMR core. A fuel element fabrication speciftcation was prepared and released for quotations. A study was made to select the most appropriate material for void simulation throughout the range of interest in the VMR. (W.D.M.)

1959-08-31T23:59:59.000Z

163

Reactor instrumentation and safety circuit status review and program document  

SciTech Connect

This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.After a plant has been built and operated for a number of years, it becomes apparent to operating and engineering personnel that certain modifications in controls and monitoring systems would provide both tangible and intangible benefits. Systems which were once thought to be the primary points of control shift in importance as others become recognized. As time passes this shifting spreads the main control focus from the central control desk to various other areas in the control room. Production rate increases cause instrument ranges and scales to be changed so that information on the process can still be obtained from existing equipment. Response times, sensitivity, limits, and time constants which were figured for one level must be used or revised for new levels. Further, it is discovered that the process monitoring points could be relocated or increased in number to provide more and better data on plant operation. New monitoring equipment is developed and installed to fill voids in information so production can continue meeting high standards for safety and process control. Equipment is fitted here and there in an already crowded control room, and some is even relocated to less advantageous positions to make available the necessary panel space. This in brief, is the rather complex status of Hanford Production Reactor instrumentation today.

Deichman, J.L.

1963-02-15T23:59:59.000Z

164

US Department of Energy 1992--1993 Reactor Sharing Program. Final report  

SciTech Connect

The University of Florida Training Reactor serves as a host institution to support various educational institutions which are located primarily within the state of Florida. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program. Three tables are included that provide basic information about the 1992--1993 program and utilization of the reactor facilities by user institutions.

Vernetson, W.G.

1994-04-01T23:59:59.000Z

165

Gas-cooled fast breeder reactor steady-state irradiation testing program  

Science Conference Proceedings (OSTI)

The requirements for the gas-cooled fast breeder reactor irradiation program are specified, and an irradiation program plan which satisfies these requirements is presented. The irradiation program plan consists of three parts and includes a schedule and a preliminary cost estimate: (1) a steady-state irradiation program, (2) irradiations in support of the design basis transient test program, and (3) irradiations in support of the GRIST-2 safety test program. Data from the liquid metal fast breeder reactor program are considered, and available irradiation facilities are examined.

Acharya, R.T.; Campana, R.J.; Langer, S.

1980-08-01T23:59:59.000Z

166

Program for alloy development for irradiation performance in fusion reactors  

SciTech Connect

The use of fission reactors as irradiation test facilities for structural materials for a fusion environment is discussed. A comparison is made of displacement damage and helium production in fast fission and fusion reactors for stainless steel. (MOW)

Stiegler, J.O.; Reuther, T.C.

1977-01-01T23:59:59.000Z

167

Education program at the Massachusetts Institute of Technology research reactor for pre-college science teachers  

Science Conference Proceedings (OSTI)

A Pre-College Science Teacher (PCST) Seminar program has been in place at the Massachusetts Institute of Technology (MIT) Nuclear Reactor Laboratory for 4 yr. The purpose of the PCST program is to educate teachers in nuclear technology and to show teachers, and through them the community, the types of activities performed at research reactors. This paper describes the background, content, and results of the MIT PCST program.

Hopkins, G.R.; Fecych, W.; Harling, O.K.

1989-01-01T23:59:59.000Z

168

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program The Department of Energy's (DOE's) Light Water Reactor Sustainability (LWRS) Program is a five year effort that works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operation of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging

169

PRISM; The plant design concept for the U. S. advanced liquid metal reactor program  

SciTech Connect

The US program for development of an advanced liquid metal reactor (ALMR) is proceeding into a new phase of focused design development. This new phase started at the beginning of 1989; its objective is to complete the conceptual design of the US ALMR, with supporting key feature tests, sufficiently to enter a more detailed design phase and subsequent construction of a prototype reactor plant. A project goal is to demonstrate by actual performance of the reactor its passive, inherent safety features and thereby provide the technical basis for certification of the design by the Nuclear Regulatory Commission (NRC). This paper reports on the PRISM (power reactor inherently safe module) reactor concept which in combination with the IFR (integral fast reactor) metal fuel cycle being developed by Argonne National Laboratory, was selected by DOE in 1988 as the reference design for the US ALMR program.

Berglund, R.C.; Tippets, F.E. (GE Nuclear Energy, Advance Nuclear Technology, San Jose, CA (US))

1989-01-01T23:59:59.000Z

170

Materials Reliability Program: Reactor Pressure Vessel Integrity Primer (MRP-278)  

Science Conference Proceedings (OSTI)

This primer is based on two earlier Electric Power Research Institute (EPRI) reports: Reactor Vessel Embrittlement Management Handbook: A Handbook for Managing Reactor Vessel Embrittlement and Vessel Integrity (TR-101975-T2) and Primer: Fracture Mechanics in the Nuclear Power Industry (NP-5792-SR, Rev. 1). The information in those earlier reports has been updated extensively and focuses on todays reactor pressure vessel (RPV) embrittlement, integrity, and plant license renewal issues. This RPV integrity ...

2010-06-09T23:59:59.000Z

171

Final report. U.S. Department of Energy University Reactor Sharing Program  

SciTech Connect

Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

Bernard, John A

2003-01-21T23:59:59.000Z

172

N Reactor standby program plan; Part 5: Safety and environment FY-90 update  

Science Conference Proceedings (OSTI)

N Reactor was shutdown by order of DOE in January 1987 to permit implementation of a series of hardware and software safety enhancements. These upgrades were designed to enhance the safe operation of N Reactor and provide comparability to commercial nuclear industry standards and requirements. The enhancements were identified by a series of external independent reviews and were managed under the N Reactor Safety Enhancement Program. In February 1988, DOE directed that N Reactor would be placed in standby. Additional guidance in FY-88 directed that the reactor would be placed in a dry layup status based on preceding Westinghouse Hanford Studies directed at defining a cost effective layup method which would preserve the ability to subsequently restart and operate N Reactor if required. The FY-88 directives also stipulated that the ability to restart N Reactor in a 2--3 year period from date of notification be preserved. 7 figs., 8 tabs.

NONE

1989-12-01T23:59:59.000Z

173

Materials Reliability Program, Reactor Vessel Head Boric Acid Corrosion Testing (MRP-165)  

Science Conference Proceedings (OSTI)

Pressurized water reactor (PWR) coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential...

2005-12-14T23:59:59.000Z

174

Crosswalk of Sustainability Goals and Targets. Federal Energy Management Program (FEMP) (Fact Sheet).  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

crosswalk was developed by the U.S. Department of crosswalk was developed by the U.S. Department of Energy (DOE) Office of Environmental Policy and Assistance and Federal Energy Management Program (FEMP). FEMP facilitates the Federal Government's implementation of sound, cost-effective energy management and investment practices to enhance the nation's energy security and environmental stewardship. Executive Order (E.O.) 13514 establishes sustainability goals, targets, and requirements for Federal agencies. It builds on, but does not replace, E.O. 13423. This crosswalk aligns goals and targets from E.O. 13514 against E.O. 13423 and other statutes to Federal agencies in identifying current requirements. Crosswalk of Sustainability Goals and Targets Goal / Target E.O. 13514 E.O. 13423 Existing Statute

175

GLOBAL THREAT REDUCTION INITIATIVE REACTOR CONVERSION PROGRAM: STATUS AND CURRENT PLANS  

SciTech Connect

The U.S. Department of Energy’s National Nuclear Security Administration (NNSA) Reactor Conversion Program supports the minimization, and to the extent possible, elimination of the use of high enriched uranium (HEU) in civilian nuclear applications by working to convert research and test reactors and radioisotope production processes to the use of low enriched uranium (LEU). The Reactor Conversion Program is a technical pillar of the NNSA Global Threat Reduction Initiative (GTRI) which is a key organization for implementing U.S. HEU minimization policy and works to reduce and protect vulnerable nuclear and radiological material domestically and abroad.

Staples, Parrish A.; Leach, Wayne; Lacey, Jennifer M.

2009-10-07T23:59:59.000Z

176

Overview of the fast reactors fuels program. [LMFBR  

SciTech Connect

Each nation involved in LMFBR development has its unique energy strategies which consider energy growth projections, uranium resources, capital costs, and plant operational requirements. Common to all of these strategies is a history of fast reactor experience which dates back to the days of the Manhatten Project and includes the CLEMENTINE Reactor, which generated a few watts, LAMPRE, EBR-I, EBR-II, FERMI, SEFOR, FFTF, BR-1, -2, -5, -10, BOR-60, BN-350, BN-600, JOYO, RAPSODIE, Phenix, KNK-II, DFR, and PFR. Fast reactors under design or construction include PEC, CRBR, SuperPhenix, SNR-300, MONJU, and Madras (India). The parallel fuels and materials evolution has fully supported this reactor development. It has involved cermets, molten plutonium alloy, plutonium oxide, uranium metal or alloy, uranium oxide, and mixed uranium-plutonium oxides and carbides.

Evans, E.A.; Cox, C.M.; Hayward, B.R.; Rice, L.H.; Yoshikawa, H.H.

1980-04-01T23:59:59.000Z

177

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES  

SciTech Connect

A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)

Atomic Energy Commission, Washington, D.C.; Jackson and Moreland, Inc., Boston

1959-01-01T23:59:59.000Z

178

Los Alamos National Laboratory and Lawrence Livermore National Laboratory Plutonium Sustainment Monthly Program Report September 2012  

SciTech Connect

In March of 2012 the Plutonium Sustainment program at LANL completed or addressed the following high-level activities: (1) Delivered Revision 2 of the Plutonium Sustainment Manufacturing Study, which incorporated changes needed due to the release of the FY2013 President's Budget and the delay in the Chemistry and Metallurgy Research Replacement Nuclear Facility (CMRRNF). (2) W87 pit type development activities completed a detailed process capability review for the flowsheet in preparation for the Engineering Development Unit Build. (3) Completed revising the Laser Beam Welding schedule to address scope and resource changes. (4) Completed machining and inspecting the first set of high-fidelity cold parts on Precitech 2 for Gemini. (5) The Power Supply Assembly Area started floor cutting with a concrete saw and continued legacy equipment decommissioning. There are currently no major issues associated with achieving MRT L2 Milestones 4195-4198 or the relevant PBIs associated with Plutonium Sustainment. There are no budget issues associated with FY12 final budget guidance. Table 1 identifies all Baseline Change Requests (BCRs) that were initiated, in process, or completed during the month. The earned value metrics overall for LANL are within acceptable thresholds, so no high-level recovery plan is required. Each of the 5 major LANL WBS elements is discussed in detail.

McLaughlin, Anastasia Dawn [Los Alamos National Laboratory; Storey, Bradford G. [Los Alamos National Laboratory; Bowidowicz, Martin [Los Alamos National Laboratory; Robertson, William G. [Los Alamos National Laboratory; Hobson, Beverly F. [Los Alamos National Laboratory

2012-10-22T23:59:59.000Z

179

October 30, 2008, Visiting Speakers Program - Dow Chemicals Presentation - Dows Approach to Sustainability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Catalyst for Change Catalyst for Change Dow's Approach to Sustainability Dr. Susan Butts Sr. Director, External Science & Technology Programs The Dow Chemical Company Office of Health, Safety & Security Visiting Speaker Program US Department of Energy The Power of the Human Element At The Dow Chemical Company, we view chemistry as the work of humanity. We believe the most important element of all is not found on the periodic table, yet is part of every equation for the future. This element is the Human Element. With it, we are more than a chemical company, we are a difference-maker in the world. October 30, 2008 2 3 October 30, 2008 About Dow A science and technology leader with annual sales of $54 billion Founded in 1897 by Herbert H. Supplies plastics and chemical

180

Materials Reliability Program: Pressurized Water Reactor Issue Management Tables—Revision 2 (MRP-205)  

Science Conference Proceedings (OSTI)

Ongoing issues related to the degradation of pressurized water reactor (PWR) nuclear steam supply system (NSSS) components have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues and associated Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) and Steam Generator Management Program (SGMP) requirements.

2010-10-27T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

710 high-temperature gas reactor program summary report. Volume I. Summary  

SciTech Connect

Declassified 6 Sep 1973. A description of the 710 Reactor concept and its significant design features is presented. A summary of the history of the 710 Program and a summary of the major technical achievements of the program are included. (13 references) (auth)

1967-01-01T23:59:59.000Z

182

A computer program to determine the specific power of prismatic-core reactors  

DOE Green Energy (OSTI)

A computer program has been developed to determine the maximum specific power for prismatic-core reactors as a function of maximum allowable fuel temperature, core pressure drop, and coolant velocity. The prismatic-core reactors consist of hexagonally shaped fuel elements grouped together to form a cylindrically shaped core. A gas coolant flows axially through circular channels within the elements, and the fuel is dispersed within the solid element material either as a composite or in the form of coated pellets. Different coolant, fuel, coating, and element materials can be selected to represent different prismatic-core concepts. The computer program allows the user to divide the core into any arbitrary number of axial levels to account for different axial power shapes. An option in the program allows the automatic determination of the core height that results in the maximum specific power. The results of parametric specific power calculations using this program are presented for various reactor concepts.

Dobranich, D.

1987-05-01T23:59:59.000Z

183

Benchmark Evaluation of the Medium-Power Reactor Experiment Program Critical Configurations  

SciTech Connect

A series of small, compact critical assembly (SCCA) experiments were performed in 1962-1965 at the Oak Ridge National Laboratory Critical Experiments Facility (ORCEF) for the Medium-Power Reactor Experiment (MPRE) program. The MPRE was a stainless-steel clad, highly enriched uranium (HEU)-O2 fuelled, BeO reflected reactor design to provide electrical power to space vehicles. Cooling and heat transfer were to be achieved by boiling potassium in the reactor core and passing vapor directly through a turbine. Graphite- and beryllium-reflected assemblies were constructed at ORCEF to verify the critical mass, power distribution, and other reactor physics measurements needed to validate reactor calculations and reactor physics methods. The experimental series was broken into three parts, with the third portion of the experiments representing the beryllium-reflected measurements. The latter experiments are of interest for validating current reactor design efforts for a fission surface power reactor. The entire series has been evaluated as acceptable benchmark experiments and submitted for publication in the International Handbook of Evaluated Criticality Safety Benchmark Experiments and in the International Handbook of Evaluated Reactor Physics Benchmark Experiments.

Margaret A. Marshall; John D. Bess

2013-02-01T23:59:59.000Z

184

Plutonium Consumption Program, CANDU Reactor Project final report  

SciTech Connect

DOE is investigating methods for long term dispositioning of weapons grade plutonium. One such method would be to utilize the plutonium in Mixed OXide (MOX) fuel assemblies in existing CANDU reactors. CANDU (Canadian Deuterium Uranium) reactors are designed, licensed, built, and supported by Atomic Energy of Canada Limited (AECL), and currently use natural uranium oxide as fuel. The MOX spent fuel assemblies removed from the reactor would be similar to the spent fuel currently produced using natural uranium fuel, thus rendering the plutonium as unattractive as that in the stockpiles of commercial spent fuel. This report presents the results of a study sponsored by the DOE for dispositioning the plutonium using CANDU technology. Ontario Hydro`s Bruce A was used as reference. The fuel design study defined the optimum parameters to disposition 50 tons of Pu in 25 years (or 100 tons). Two alternate fuel designs were studied. Safeguards, security, environment, safety, health, economics, etc. were considered. Options for complete destruction of the Pu were also studied briefly; CANDU has a superior ability for this. Alternative deployment options were explored and the potential impact on Pu dispositioning in the former Soviet Union was studied. An integrated system can be ready to begin Pu consumption in 4 years, with no changes required to the reactors other than for safe, secure storage of new fuel.

Not Available

1994-07-31T23:59:59.000Z

185

The SCORE and CitySmart Programs: Sustaining Investment in High Performance Buildings in Schools and Cities  

E-Print Network (OSTI)

The definition of “sustainability” depends on who you ask. We define the sustainability of investing in energy efficiency this way: The practice of selecting higher efficiency alternatives becomes sustainable once the purchaser understands that energy cost savings are invisible to the occupant, that the non-energy benefits (NEB) are more important than pure energy efficiency in creating a constituency that drives decision makers, and puts in place a decision-making process that actively pursues energy cost savings and non-energy benefits. Since 2006, more than 185 educational organizations and municipal governments have participated in the SCORESM and CitySmartSM energy efficiency programs offered by nine investor-owned utility companies in Arkansas and Texas. This paper will describe how the services provided by the programs have led to sustained efforts by participating organizations to save energy and improve occupant comfort through increased energy efficiency.

Kleinman, J.; McMinn, S.

2009-11-01T23:59:59.000Z

186

Using low-enriched uranium in research reactors: The RERTR program  

SciTech Connect

The goal of the RERTR program is to minimize and eventually eliminate use of highway enriched uranium (HEU) in research and test reactors. The program has been very successful, and has developed low-enriched uranium (LEU) fuel materials and designs which can be used effectively in approximately 90 percent of the research and test reactors which used HEU when the program began. This progress would not have been possible without active international cooperation among fuel developers, commercial vendors, and reactor operators. The new tasks which the RERTR program is undertaking at this time include development of new and better fuels that will allow use of LEU fuels in all research and test reactors; cooperation with Russian laboratories, which will make it possible to minimize and eventually eliminate use of HEU in research reactors throughout the world, irrespective of its origin; and development of an LEU-based process for the production of {sup 99}Mo. Continuation and intensification of international cooperation are essential to the achievement of the ultimate goals of the RERTR program.

Travelli, A.

1994-05-01T23:59:59.000Z

187

POWER COST NORMALIZATION STUDIES CIVILIAN POWER REACTOR PROGRAM--Sept. 1, 1959  

SciTech Connect

In connection with the development of a comprehensive plan for a ten- year civilian power reactor program, the AEC has had a series of status reports prepared to present a comprehensive review of the technical and economic status of various nuclear power reactor concepts. In as much as the economic data reported by the various contractors reflected different design philosophies, different estimating policies, and in some cases a technology not verified by the AEC definition of current status, Sargent and Lundy was requested to review the aforementioned status reports and to prepare normalized cost estimates of each of eight reactor concepts. The reactors were studied in three plant sizes: 75, 200, and 300 Mw(e). The reactor concepts considered were pressurized water, boiling water, organic cooled, sodium graphite, liquid metal cooled, fluid fuel (aqueous homogeneous), heavy water moderated, and gas cooled. (W.D.M.)

1960-10-31T23:59:59.000Z

188

Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program  

DOE Green Energy (OSTI)

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

Not Available

1987-05-01T23:59:59.000Z

189

Plan for Demonstration of Online Monitoring for the Light Water Reactor Sustainability Online Monitoring Project  

SciTech Connect

Condition based online monitoring technologies and development of diagnostic and prognostic methodologies have drawn tremendous interest in the nuclear industry. It has become important to identify and resolve problems with structures, systems, and components (SSCs) to ensure plant safety, efficiency, and immunity to accidents in the aging fleet of reactors. The Machine Condition Monitoring (MCM) test bed at INL will be used to demonstrate the effectiveness to advancement in online monitoring, sensors, diagnostic and prognostic technologies on a pilot-scale plant that mimics the hydraulics of a nuclear plant. As part of this research project, INL will research available prognostics architectures and their suitability for deployment in a nuclear power plant. In addition, INL will provide recommendation to improve the existing diagnostic and prognostic architectures based on the experimental analysis performed on the MCM test bed.

Magdy S. Tawfik; Vivek Agarwal; Nancy J. Lybeck

2011-09-01T23:59:59.000Z

190

Program Sustainability Peer Exchange Call: Transitioning to a Utility Funded Program Environment: What Do I Need to Know? (January 17, 2013)  

NLE Websites -- All DOE Office Websites (Extended Search)

January 17, 2013 January 17, 2013 Program Sustainability Peer Exchange Call: Transitioning to a Utility Funded Program Environment: What Do I Need To Know? Utility Funded Programming: What Do You Need to Know? Gavin Hastings Account Executive, Arizona Public Service Better Building Neighborhood Program Peer Exchange Call: Jan. 2013 Roadmap Please! Overview * Critical Areas of Focus - Funding (Regulatory/Rates/Process) - Data, Data, Data - Collaborative Relationships * AZ Case Study * Questions and Discussion Utility Funding 101 * How does a utility fund energy efficiency? * Does your program meet local utility cost effectiveness tests? * What is the timing and steps to get funding approved? Utility Funding Needs * Program Cost Recovery: - System benefits charge

191

U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies.

Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

2004-10-03T23:59:59.000Z

192

Sustainable Electricity | Clean Energy | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Electricity SHARE Sustainable Electricity Outdoor power line accelerated testing. Oak Ridge National Laboratory's Energy Efficiency and Electricity Technologies Program...

193

Designing Biological Systems for Sustainability and Programmed Environmental Interface (2011 JGI User Meeting)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy Joint Genome Institute (JGI) invited scientists interested in the application of genomics to bioenergy and environmental issues, as well as all current and prospective users and collaborators, to attend the annual DOE JGI Genomics of Energy & Environment Meeting held March 22-24, 2011 in Walnut Creek, Calif. The emphasis of this meeting was on the genomics of renewable energy strategies, carbon cycling, environmental gene discovery, and engineering of fuel-producing organisms. The meeting features presentations by leading scientists advancing these topics. Pam Silver of Harvard University gives a presentation on "Designing Biological Systems for Sustainability and Programmed Environmental Interface" at the 6th annual Genomics of Energy & Environment Meeting on March 23, 2011

Silver, Pam [Harvard University

2011-03-23T23:59:59.000Z

194

FFTF and Advanced Reactors Transition Program Resource Loaded Schedule  

SciTech Connect

This Resource Load Schedule (RLS) addresses two missions. The Advanced Reactors Transition (ART) mission, funded by DOE-EM, is to transition assigned, surplus facilities to a safe and compliant, low-cost, stable, deactivated condition (requiring minimal surveillance and maintenance) pending eventual reuse or D&D. Facilities to be transitioned include the 309 Building Plutonium Recycle Test Reactor (PRTR) and Nuclear Energy Legacy facilities. This mission is funded through the Environmental Management (EM) Project Baseline Summary (PBS) RL-TP11, ''Advanced Reactors Transition.'' The second mission, the Fast Flux Test Facility (FFTF) Project, is funded through budget requests submitted to the Office of Nuclear Energy, Science and Technology (DOE-NE). The FFTF Project mission is maintaining the FFTF, the Fuels and Materials Examination Facility (FMEF), and affiliated 400 Area buildings in a safe and compliant standby condition. This mission is to preserve the condition of the plant hardware, software, and personnel in a manner not to preclude a plant restart. This revision of the Resource Loaded Schedule (RLS) is based upon the technical scope in the latest revision of the following project and management plans: Fast Flux Test Facility Standby Plan (Reference 1); Hanford Site Sodium Management Plan (Reference 2); and 309 Building Transition Plan (Reference 4). The technical scope, cost, and schedule baseline is also in agreement with the concurrent revision to the ART Fiscal Year (FY) 2001 Multi-Year Work Plan (MYWP), which is available in an electronic version (only) on the Hanford Local Area Network, within the ''Hanford Data Integrator (HANDI)'' application.

GANTT, D.A.

2000-10-31T23:59:59.000Z

195

Fast reactor safety program. Progress report, January-March 1980  

Science Conference Proceedings (OSTI)

The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development.

Not Available

1980-05-01T23:59:59.000Z

196

EXPERIMENTAL BERYLLIUM OXIDE REACTOR PROGRAM. Quarterly Progress Report for the Period, January 1 through March 31, 1962  

SciTech Connect

Progress made in the development of the Experimental Beryllium Oxide Reactor (EBOR) is reported. The objective of the EBOR program is to develop a gas-cooled, beryllium oxide-moderated reactor which can be used in conjunction with a closed-cycle gas turbine or a steam cycle for a small land-based or a maritime power plant. Progress is reported on reactor development, reactor physics, and materials development. (N.W.R.)

1962-04-25T23:59:59.000Z

197

Materials Reliability Program: Qualification Protocol for Pressurized Water Reactor Upper Head Penetration Ultrasonic Examinations-- -2010 Update (MRP-234)  

Science Conference Proceedings (OSTI)

The Materials Reliability Program (MRP) has directed the Inspection Issues Task Group (ITG) to establish a qualification program for the examination of pressurized water reactor (PWR) reactor pressure vessel upper head penetrations. This new qualification program is being implemented to provide the utilities with a consistent and reliable examination approach for the upper head penetrations. The program will provide assurance that flaws of similar size and location will be detected reliably throughout th...

2010-07-30T23:59:59.000Z

198

Materials Reliability Program: Qualification Protocol for Pressurized Water Reactor Upper Head Penetration Ultrasonic Examinations - - 2012 Update (MRP-311, Revision 1)  

Science Conference Proceedings (OSTI)

The Materials Reliability Program (MRP) has directed the Inspection Technical Advisory Committee to establish a qualification program for the examination of pressurized water reactor (PWR) reactor pressure vessel upper head (RPVUH) penetrations. This qualification program is being implemented to provide the utilities with a consistent and reliable examination approach for upper head penetrations. The program will provide assurance that flaws of similar size and location will be detected reliably ...

2012-11-28T23:59:59.000Z

199

Materials Reliability Program: Qualification Protocol for Pressurized Water Reactor Upper Head Penetration Ultrasonic Examinations 2 011 Update (MRP-311)  

Science Conference Proceedings (OSTI)

The Materials Reliability Program (MRP) has directed the Inspection Technical Advisory Committee (TAC) to establish a qualification program for the examination of pressurized water reactor (PWR) reactor pressure vessel upper head penetrations (RPVUHs). This new qualification program was implemented to provide the utilities with a consistent and reliable examination approach for upper head penetrations. The program will provide assurance that flaws of similar size and location will be detected reliably th...

2011-09-28T23:59:59.000Z

200

Participation in the United States Department of Energy Reactor Sharing Program  

SciTech Connect

The University of Virginia Reactor Facility is an integral part of the Department of Nuclear Engineering and Engineering Physics (to become the Department of Mechanical, Aerospace and Nuclear Engineering on July 1, 1992). As such, it is effectively used to support educational programs in engineering and science at the University of Virginia as well as those at other area colleges and universities. The expansion of support to educational programs in the mid-east region is a major objective. To assist in meeting this objective, the University of Virginia has been supported under the US Department of Energy (DOE) Reactor Sharing Program since 1978. Due to the success of the program, this proposal requests continued DOE support through August 1993.

Mulder, R.U.; Benneche, P.E.; Hosticka, B.

1992-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Light Water Reactor Sustainability (LWRS) Initiative Science-Based R&D to Extend Nuclear Plant Operation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Nuclear Energy Updates Dr. Pete Lyons Acting Assistant Secretary for Nuclear Energy U.S. Department of Energy December 9, 2010 NEAC Meeting Leadership Changes Pete Miller retired Pete Lyons - Acting NE-1 Shane Johnson - Acting NE-2 Dennis Miotla - Acting COO Monica Regalbuto - Acting DAS for Fuel Cycle Technologies John Herczeg- Acting ADAS for Fuel Cycle Technologies John Kelly - DAS for Nuclear Reactor Technologies Bob Boudreau- Acting ADAS International Nuclear Energy Coop Monica Regalbuto John Kelly NE University Programs (NEUP) - Overview and FY 2011 Schedule NEUP FY 2011 Solicitations Schedule RPA/FOA Pre- Applications Proposals Due Awards Announced R&D (PS and Blue Sky) Oct. '10 Dec. '10 Feb. '11 May '11 Integrated Research Projects (IRP) Dec. '10 Late Jan '11

202

Light Water Reactor Sustainability (LWRS) Initiative Science-Based R&D to Extend Nuclear Plant Operation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9, 2010 9, 2010 New Program Proposal for Fiscal Year 2011 - Modified Open Cycle Carter "Buzz" Savage Nuclear Energy Advisory Committee Meeting April 29, 2010 Washington, DC April 29, 2010 Recycle of Used Fuel Option to recycle used fuel has been the subject of much debate and discussion. Nonproliferation issues and economics have limited recycle options. Recycle of used fuel enables increased utilization of uranium resource and potential waste management benefits. - Once through fuel cycle uses less than 1% of energy value of the uranium. Courtesy AREVA 2 April 29, 2010 Summary of Fuel Cycle Options 3 Once-Through Fuel Cycle - One pass through reactor, used fuel directly disposed in a geologic repository. Modified Open Cycle - No or limited separations steps and

203

Materials Reliability Program: Reactor Vessel Head Boric Acid Corrosion Testing (MRP-199)  

Science Conference Proceedings (OSTI)

PWR coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential stages of boric acid corros...

2007-06-27T23:59:59.000Z

204

Materials Reliability Program: Destructive Examination of the North Anna 2 Reactor Pressure Vessel Head (MRP-198)  

Science Conference Proceedings (OSTI)

This document is the final of three reports concerning the nondestructive and destructive examinations of selected control rod drive mechanism (CRDM) penetrations from the decommissioned North Anna Unit 2 reactor vessel head (RVH). The phase-1 report of the EPRI-MRP (Materials Reliability Program) managed program described the selection and removal of penetrations from the decommissioned RVH and the penetration decontamination and laboratory nondestructive evaluation (NDE). The phase-2 report detailed th...

2006-11-13T23:59:59.000Z

205

Materials Reliability Program: Pressurized Water Reactor Issue Management Tables - Revision 3 (MRP-205)  

Science Conference Proceedings (OSTI)

Nuclear utilities continue to face a number of ongoing issues related to degradation of pressurized water reactor (PWR) nuclear steam supply system (NSSS) components. These issues have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues and associated EPRI Materials Reliability Program (MRP) and Steam Generator Management Program (SGMP) requirements.BackgroundA comprehensive, integrated ...

2013-12-03T23:59:59.000Z

206

Light-water breeder reactor (LWBR Development Program)  

DOE Patents (OSTI)

Described is a light-water-moderated and -cooled nuclear breeder reactor of the seed-blanket type characterized by core modules comprising loosely packed blanket zones enriched with fissile fuel and axial zoning in the seed and blanket regions within each core module. Reactivity control over lifetime is achieved by axial displacement of movable seed zones without the use of poison rods in the embodiment illustrated. The seed is further characterized by a hydrogen-to-uranium-233 atom ratio in the range 10 to 200 and a uranium-233-to-thorium-232 atom ratio ranging from 0.012 to 0.200. The seed occupies from 10 to 35 percent of the core volume in the form of one or more individual islands or annuli. (NSA 26: 55130)

Beaudoin, B.R.; Cohen, J.D.; Jones, D.H.; Marier, L.J. Jr.; Raab, H.F.

1972-06-20T23:59:59.000Z

207

Gas reactor international cooperative program. HTR-synfuel application assessment  

SciTech Connect

This study assesses the technical, environmental and economic factors affecting the application of the High Temperature Gas-Cooled Thermal Reactor (HTR) to: synthetic fuel production; and displacement of fossil fuels in other industrial and chemical processes. Synthetic fuel application considered include coal gasification, direct coal liquefaction, oil shale processing, and the upgrading of syncrude to motor fuel. A wide range of other industrial heat applications was also considered, with emphasis on the use of the closed-loop thermochemical energy pipeline to supply heat to dispersed industrial users. In this application syngas (H/sub 2/ +CO/sub 2/) is produced at the central station HTR by steam reforming and the gas is piped to individual methanators where typically 1000/sup 0/F steam is generated at the industrial user sites. The products of methanation (CH/sub 4/ + H/sub 2/O) are piped back to the reformer at the central station HTR.

1979-09-01T23:59:59.000Z

208

Interagency Sustainability Working Group: Update Report; December 2009, Federal Energy Management Program (FEMP) (Brochure)  

SciTech Connect

December 2009 update report offered by the Interagency Sustainability Working Group (ISWG). This report is updated bi-annually.

Not Available

2009-12-01T23:59:59.000Z

209

FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH DEVELOPMENT PROGRAM. First Summary Report for March 1959-July 1960  

SciTech Connect

The Fuel Cycle Development Program is a basic development program for boiling and other water technology. It covers the areas of oxide fuel fabrication. irradiation. and examination; the physics of water-moderated reactore; and boiling-water heat transfer and stability. Schedules for the fuel- cycle program were examined. and it was concluded that portions of the Task A program should be conducted during the period May to Dec. 1959 in order to keep costs of the work as low as possible and to allow initiation of the fuel-cycle program at the earliest possible date after the Vallecitos BWR was returned to service. The basis for the scheduling of the work is discussed. and a chronological summary describing the content of the work is given. Technical progress is outlined and details are summarized. Subsequent reports issued monthly and quarterly will summarize the progress of the prognam. (W.D.M.)

Cook, W.H.

1961-10-31T23:59:59.000Z

210

Towards sustainable well-being in SMEs through the web-based learning program of ergonomics  

Science Conference Proceedings (OSTI)

Promoting well-being at work in the context of sustainable development is a complex and dynamic issue. To enhance sustainable well-being at work, organizational learning (OL) is one requirement. The purpose of this study was to identify and describe ... Keywords: Content analysis, Organizational learning, SMEs, Sustainable development, Web-based learning, Well-being at work

Marja Randelin; Terhi Saaranen; Paula Naumanen; Veikko Louhevaara

2013-03-01T23:59:59.000Z

211

Nuclear Reactors  

NLE Websites -- All DOE Office Websites (Extended Search)

Reactors Nuclear reactors created not only large amounts of plutonium needed for the weapons programs, but a variety of other interesting and useful radioisotopes. They produced...

212

Quarterly technical report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April--June 1975  

SciTech Connect

The current water reactor safety activities of ANC are accomplished in four programs. The Semiscale Program consists of small-scale nonnuclear thermal- hydraulic experiments for the generation of experimental data that can be applied to analytical models describing loss-of-coolant accident (LOCA) phenomena in water-cooled nuclear power plants. Emphasis is placed on acquiring system effects data from integral tests that characterize the most significant thermal- hydraulic phenomena during the depressurization (blowdown) and emergency cooling phase of a LOCA. The LOFT Program provides test data to support: (a) assessment and improvement of the analytical methods utilized for predicting the behavior of pressurized water reactors (PWR) under LOCA conditions; (b) evaluation of the performance of PWR engineered safety features (ESF), particularly the emergency core cooling system (ECCS); and (c) assessment of the quantitative margins of safety inherent in the performance of these safety features. The Thermal Fuels Behavior Program is a program designed to provide information on the behavior of reactor fuels under normal, off-normal, and accident conditions. The experimental portion is concentrated on testing of single fuel rods and fuel rod clusters under power-cooling-mismatch (PCM), loss-of-coolant, and reactivity initiated accident conditions. The Reactor Behavior Program encompasses the analytical aspects of predicting the response of nuclear power reactors under normal, abnormal, and accident conditions. The status of each program is reported. (auth)

1975-11-01T23:59:59.000Z

213

CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM AS OF 1959  

SciTech Connect

The status of technology of nuclear power reactors in 1959 is reviewed. General research and engineering development activities are discussed. The reactors considered include the pressurized water, boiling water, light water moderated superheat, organic cooled, sodium graphite, gas cooled enriched fuel, gas cooled natural uranium, fast breeder, aqueous homogeneous, and heavy water. Power costs are compared with the cost of power from conventional plants. (C.H.)

1960-01-01T23:59:59.000Z

214

University of Florida--US Department of Energy 1994-1995 reactor sharing program  

SciTech Connect

The grant support of $24,250 (1994-95?) was well used by the University of Florida as host institution to support various educational institutions in the use of UFTR Reactor. All users and uses were screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research was not funded by grants for contract funding from outside sources. Over 12 years, the program has been a key catalyst for renewing utilization of UFTR both by external users around the State of Florida and the Southeast and by various faculty members within the University of Florida. Tables provide basic information about the 1994-95 program and utilization of UFTR.

Vernetson, W.G.

1996-06-01T23:59:59.000Z

215

Gas Reactor International Cooperative Program. Interim report. Construction and operating experience of selected European Gas-Cooled Reactors  

SciTech Connect

The construction and operating experience of selected European Gas-Cooled Reactors is summarized along with technical descriptions of the plants. Included in the report are the AVR Experimental Pebble Bed Reactor, the Dragon Reactor, AGR Reactors, and the Thorium High Temperature Reactor (THTR). The study demonstrates that the European experience has been favorable and forms a good foundation for the development of Advanced High Temperature Reactors.

1978-09-01T23:59:59.000Z

216

High-temperature gas-cooled reactor (HTGR): long term program plan  

DOE Green Energy (OSTI)

The FY 1980 effort was to investigate four technology options identified by program participants as potentially viable candidates for near-term demonstration: the Gas Turbine system (HTGR-GT), reflecting its perceived compatibility with the dry-cooling market, two systems addressing the process heat market, the Reforming (HTGR-R) and Steam Cycle (HTGR-SC) systems, and a more developmental reactor system, The Nuclear Heat Source Demonstration Reactor (NHSDR), which was to serve as a basis for both the HTGR-GT and HTGR-R systems as well as the further potential for developing advanced applications such as steam-coal gasification and water splitting.

Not Available

1980-10-09T23:59:59.000Z

217

Sustainable Scientists  

E-Print Network (OSTI)

thanks to extensive green and energy-efficient features, andenergy efficiency improvement programs (xxxviii) and their GreenGreen Grid alliance to address efficiency and sustainability issues (xxxvii). This group is exploring energy

Mills, Evan

2009-01-01T23:59:59.000Z

218

China Energy Group - Sustainable Growth Through Energy Efficiency  

E-Print Network (OSTI)

problems; the China Sustainable Energy Program (funded byFoundation's China Sustainable Energy Program commissionedFoundation (China Sustainable Energy Program) became major

2006-01-01T23:59:59.000Z

219

Light Water Reactor Sustainability Program Power Uprate Research and Development Strategy  

Science Conference Proceedings (OSTI)

The economic incentives for low-cost electricity generation will continue to drive more plant owners to identify safe and reliable methods to increase the electrical power output of the current nuclear power plant fleet. A power uprate enables a nuclear power plant to increase its electrical output with low cost. However, power uprates brought new challenges to plant owners and operators. These include equipment damage or degraded performance, and unanticipated responses to plant conditions, etc. These problems have arisen mainly from using dated design and safety analysis tools and insufficient understanding of the full implications of the proposed power uprate or from insufficient attention to detail during the design and implementation phase. It is essential to demonstrate that all required safety margins have been properly retained and the existing safety level has been maintained or even increased, with consideration of all the conditions and parameters that have an influence on plant safety. The impact of the power uprate on plant life management for long term operation is also an important issue. Significant capital investments are required to extend the lifetime of an aging nuclear power plant. Power uprates can help the plant owner to recover the investment costs. However, plant aging issues may be aggravated by the power uprate due to plant conditions. More rigorous analyses, inspections and monitoring systems are required.

Hongbin Zhang

2011-09-01T23:59:59.000Z

220

DOE-NE Light Water Reactor Sustainability Program and EPRI Long...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

- Joint Research and Development Plan April 2013 U.S. Department of Energy Office of Nuclear Energy DISCLAIMER This information was prepared as an account of work sponsored by an...

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Updated Generation IV Reactors Integrated Materials Technology Program Plan, Revision 2  

SciTech Connect

The Department of Energy's (DOE's) Generation IV Nuclear Energy Systems Program will address the research and development (R&D) necessary to support next-generation nuclear energy systems. Such R&D will be guided by the technology roadmap developed for the Generation IV International Forum (GIF) over two years with the participation of over 100 experts from the GIF countries. The roadmap evaluated over 100 future systems proposed by researchers around the world. The scope of the R&D described in the roadmap covers the six most promising Generation IV systems. The effort ended in December 2002 with the issue of the final Generation IV Technology Roadmap [1.1]. The six most promising systems identified for next generation nuclear energy are described within the roadmap. Two employ a thermal neutron spectrum with coolants and temperatures that enable hydrogen or electricity production with high efficiency (the Supercritical Water Reactor - SCWR and the Very High Temperature Reactor - VHTR). Three employ a fast neutron spectrum to enable more effective management of actinides through recycling of most components in the discharged fuel (the Gas-cooled Fast Reactor - GFR, the Lead-cooled Fast Reactor - LFR, and the Sodium-cooled Fast Reactor - SFR). The Molten Salt Reactor (MSR) employs a circulating liquid fuel mixture that offers considerable flexibility for recycling actinides, and may provide an alternative to accelerator-driven systems. A few major technologies have been recognized by DOE as necessary to enable the deployment of the next generation of advanced nuclear reactors, including the development and qualification of the structural materials needed to ensure their safe and reliable operation. Accordingly, DOE has identified materials as one of the focus areas for Gen IV technology development.

Corwin, William R [ORNL; Burchell, Timothy D [ORNL; Halsey, William [Lawrence Livermore National Laboratory (LLNL); Hayner, George [Idaho National Laboratory (INL); Katoh, Yutai [ORNL; Klett, James William [ORNL; McGreevy, Timothy E [ORNL; Nanstad, Randy K [ORNL; Ren, Weiju [ORNL; Snead, Lance Lewis [ORNL; Stoller, Roger E [ORNL; Wilson, Dane F [ORNL

2005-12-01T23:59:59.000Z

222

Gas-cooled reactor programs annual progress report for period ending December 31, 1972  

SciTech Connect

Information on the gas-cooled reactor development programs is presented concerning HTGR head-end fuel reprocessing development; fuel microsphere preparation development; fuel fabrication process development; HTGR fuel recycle pilot-plant studies; studies and evaluation of commercial HTGR fuel recycle plants; HTGR fuel element development; HTGR fuel irradiations and postirradiation evaluations; HTGR fuel chemistry, fuel integrity, and fission product behavior; reactions of HTGR core materials with steam; fission product behavior in HTGR coolant circuits; HTGR safety program plan and safety analysis; prestressed concrete pressure vessel development; GCFR irradiation experiments; and GCFR steam generator modeling studies. (DCC)

1974-03-01T23:59:59.000Z

223

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980  

Science Conference Proceedings (OSTI)

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

Not Available

1980-06-25T23:59:59.000Z

224

REACTOR AND SHIELD PHYSICS. Comprehensive Technical Report, General Electric Direct-Air-Cycle, Aircraft Nuclear Propulsion Program.  

SciTech Connect

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume describes the experimental and theoretical work accomplished in the areas of reactor and shield physics.

Edwards, W.E.; Simpson, J.D.

1962-01-01T23:59:59.000Z

225

REACTOR  

DOE Patents (OSTI)

A pressurized water reactor in which automatic control is achieved by varying the average density of the liquid moderator-cooiant is patented. Density is controlled by the temperature and power level of the reactor ftself. This control can be effected by the use of either plate, pellet, or tubular fuel elements. The fuel elements are disposed between upper and lower coolant plenum chambers and are designed to permit unrestricted coolant flow. The control chamber has an inlet opening communicating with the lower coolant plenum chamber and a restricted vapor vent communicating with the upper coolant plenum chamber. Thus, a variation in temperature of the fuel elements will cause a variation in the average moderator density in the chamber which directly affects the power level of the reactor.

Roman, W.G.

1961-06-27T23:59:59.000Z

226

DOE/EIS-0218-SA-3: Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (November 2004)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

SUPPLEMENT ANALYSIS FOR THE FOREIGN SUPPLEMENT ANALYSIS FOR THE FOREIGN RESEARCH REACTOR SPENT NUCLEAR FUEL ACCEPTANCE PROGRAM NOVEMBER 2004 DOE/EIS-0218-SA-3 U.S. Department of Energy National Nuclear Security Administration Washington, DC Final Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program Final i TABLE OF CONTENTS Page 1. Introduction.............................................................................................................................................. 1 2. Background .............................................................................................................................................. 1 3. The Proposed Action ...............................................................................................................................

227

RBU: A COMBINED MONTE CARLO REACTOR-BURNUP PROGRAM FOR THE IBM 709  

SciTech Connect

RBU is a digital computer program for the detailed calculation of the neutron, reactivity, and isotopic history of a reactor in which relatively exact models of the geometry and physical processes are included to permit reliable pre dictions of fuel costs and reactor performance. The program uses the Monte Carlo method to obtain the fine structure of the neutron flux in three space dimensions and energy. Using this fine structure, cross sections are averaged over space and energy to obtain the neutronic properties for equivalent homogeneous one- dimensional regions of space and ranges of energy. These are used in diffusion calculations to obtain the macroscopic flux distribution throughout the reactor. The consumption and production of isotopes is computed for a time step by the solution of sets of partial differential equations involving both the macroscopic and microscopic fluxes. With the new concentrations, diffusion calculations are performed again to obtain macroscopic fluxes for the next time step. At variable intervals, Monte Carlo calculations are again performed to determine the changes in microscopic flux distributions. The cycle is repeated until conditions on the reactivity or other properties dictate the end of the calculation. Programmed control rod manipulation may be included in the calculation. The Monte Carlo, diffusion, or burnup portions of the program may be used separately. The unresolved resonance range is treated by random selection of resonance parameters from appropriate distributions using the Doppler broadened single level Breit- Wigner formula. Resolved resonances are treated similarly with the exception that specific values of the resonance parameters are used. The effects of molecular binding and thermal motion of the nuclei on near-thermal scattering are treated by a simple model capable of incorporating the pertinent physical theory and data. (auth)

Leshan, E.J.; Burr, J.R.; Temme, M.; Thompson, G.T.; Triplett, J.R.

1959-09-30T23:59:59.000Z

228

TECHNICAL SCOPE OF GAS-COOLED REACTOR FUEL ELEMENT IRRADIATION PROGRAM  

SciTech Connect

A set of 55 experiments hss been outiined to provide a minimum irradiation program for selection of UO/sub 2/, pellet geometry and fabricntion techniques, and canning technology. These experiments fall into three catagories: prototype: untts in which radial dimension and heat fluxes sre close to proposed design values, but irradiation times are long; reduced-size prototype for accelerated tests in which most variables will be studied; and miniaurized pellet irradiation to obtain high burnup for fission gas release studies. Reactor space has been found generally available and several installations are now examining their capabilities to participate in the program. A tentative schedule has been drawn to illustrate the feasibility of the program. (auth)

1958-08-01T23:59:59.000Z

229

SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM-THEORETICAL ANALYSIS. PART II. BPG COMPUTER PROGRAM REPORT  

DOE Green Energy (OSTI)

The BPG code was written to compute the criticality of reactors using all kinds or moderators, specifically including mixtures of H/sub 2/O and D/sub 2/ O. Since slowing down with hydrogen moderator is susceptible to exact calculation, and since the Fermi age equation accurately treats heavy moderators such as carbon, the important innovations in this code deal with the transition from light to heavy scatter, and particularly with the treatment of moderation by deuterium. Included in the description of the code are derivation of the equations, physical data for the calculations, input and output format, and general operating conditions for use with the Burroughs 205 computer. (M.C.G.)

de Coulon, G.A.G.; Gates, L.D.; Worley, W.R.

1962-01-01T23:59:59.000Z

230

The DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification Program  

SciTech Connect

The Department of Energy has established the Advanced Gas Reactor Fuel Development and Qualification Program to address the following overall goals: Provide a baseline fuel qualification data set in support of the licensing and operation of the Next Generation Nuclear Plant (NGNP). Gas-reactor fuel performance demonstration and qualification comprise the longest duration research and development (R&D) task for the NGNP feasibility. The baseline fuel form is to be demonstrated and qualified for a peak fuel centerline temperature of 1250°C. Support near-term deployment of an NGNP by reducing market entry risks posed by technical uncertainties associated with fuel production and qualification. Utilize international collaboration mechanisms to extend the value of DOE resources. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, postirradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete fundamental understanding of the relationship between the fuel fabrication process, key fuel properties, the irradiation performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. Fuel performance modeling and analysis of the fission product behavior in the primary circuit are important aspects of this work. The performance models are considered essential for several reasons, including guidance for the plant designer in establishing the core design and operating limits, and demonstration to the licensing authority that the applicant has a thorough understanding of the in-service behavior of the fuel system. The fission product behavior task will also provide primary source term data needed for licensing. An overview of the program and recent progress will be presented.

David Petti; Hans Gougar; Gary Bell

2005-05-01T23:59:59.000Z

231

DOE-NE Light Water Reactor Sustainability Program and EPRI Long-Term Operations Program – Joint Research and Development Plan  

SciTech Connect

Nuclear power has contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants (NPPs) some of the most economical power generators available. Further, nuclear power remains the single largest contributor (nearly 70%) of non-greenhouse gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's electrical generation capability.

Don Williams

2012-04-01T23:59:59.000Z

232

CIVILIAN POWER REACTOR PROGRAM. PART III. STATUS REPORT ON GAS-COOLED REACTORS AS OF 1959. Book 8  

SciTech Connect

The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel prototype and for a large natural- uraniumfueled plant. Current technical status is discussed in terms of reactor physics, heat transfer and fluid flow, core materials, components, plant design and conctruction, and hazards. Detailed tables of characteristics for various reactors are given. An extensive bibliography is included. (W.D.M.)

1960-01-01T23:59:59.000Z

233

The BURNUP package of applied programs used for computing the isotopic composition of materials of an operating nuclear reactor  

SciTech Connect

This paper described the procedure of implementation and the possibilities of the BURNUP program. The purpose of the program is to predict the change in the nuclear composition of the materials of which a reactor is made in the course of its run and compute the radiation characteristics of the materials after their irradiation.

Yudkevich, M. S., E-mail: umark@adis.vver.kiae.ru [National Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

234

Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program  

Science Conference Proceedings (OSTI)

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab.

Batte, G.L. (Argonne National Lab., Idaho Falls, ID (USA)); Hoffman, G.L. (Argonne National Lab., IL (USA))

1990-01-01T23:59:59.000Z

235

Efficient System Design and Sustainable Finance for China's Village Electrification Program: Preprint  

DOE Green Energy (OSTI)

This paper describes a joint effort of the Institute for Electrical Engineering of the Chinese Academy of Sciences (IEE), and the U.S. National Renewable Energy Laboratory (NREL) to support China's rural electrification program. This project developed a design tool that provides guidelines both for off-grid renewable energy system designs and for cost-based tariff and finance schemes to support them. This tool was developed to capitalize on lessons learned from the Township Electrification Program that preceded the Village Electrification Program. We describe the methods used to develop the analysis, some indicative results, and the planned use of the tool in the Village Electrification Program.

Ma, S.; Yin, H.; Kline, D. M.

2006-08-01T23:59:59.000Z

236

Efficient System Design and Sustainable Finance for China's Village Electrification Program: Preprint  

SciTech Connect

This paper describes a joint effort of the Institute for Electrical Engineering of the Chinese Academy of Sciences (IEE), and the U.S. National Renewable Energy Laboratory (NREL) to support China's rural electrification program. This project developed a design tool that provides guidelines both for off-grid renewable energy system designs and for cost-based tariff and finance schemes to support them. This tool was developed to capitalize on lessons learned from the Township Electrification Program that preceded the Village Electrification Program. We describe the methods used to develop the analysis, some indicative results, and the planned use of the tool in the Village Electrification Program.

Ma, S.; Yin, H.; Kline, D. M.

2006-08-01T23:59:59.000Z

237

Integrating Enhanced Building Operations into Municipal Sustainability Programming: A Report from NYC  

E-Print Network (OSTI)

With municipalities setting goals for greenhouse gas reductions, there is an emerging need for model program designs based on quantitative analysis. Evidence is cited that commercial-institutional building retrofit programs can be significantly improved by commissioning and enhanced operation activities. Dimensions are defined along which program value is added: capture of high-payback O&M measures, early action, achievement of projections, and persistence. Based on parameters in the NYC Mayor's Office PlaNYC2030, a spreadsheet model is developed to quantify the value of including an EBO component with a Capital Projects program. Given project-cycle considerations, including EBO enables actions and associated energy reduction to begin more quickly under Operating Budget allocations. Although impressive quantified benefits are indicated market difficulties will inhibit the expansion of EBO. Engineering consultants, mechanical-electrical contractors, ESCOs, and facilities staff are at a relatively low level of readiness for undertaking true operational improvement programs. Root cause of this market condition is suggested to lie in the predominant capital-projects business model of the engineering and construction industry. Large municipal programs can be a lever in changing these market conditions. A set of recommendations is developed for program design the will facilitate incorporation of longterm EBO into more traditional energy efficiency programs.

Bobker, M.

2007-01-01T23:59:59.000Z

238

Prospects of Using Reprocessed Uranium in CANDU Reactors, in the U.S. GNEP Program  

Science Conference Proceedings (OSTI)

Current Global Nuclear Energy Partnership (GNEP) plans envision reprocessing spent fuel (SF) with view to minimizing high-level waste (HLW) repository use and recovering actinides (U, Np, Pu, Am, and Cm) for transmutation in reactors as fuel and targets. The reprocessed uranium (RU), however, is to be disposed of. This paper presents a limited-scope analysis of possible reuse of RU in CANDU (Canada Deuterium Uranium) Reactors, within the context of the US GNEP program. Other papers on this topic submitted to this conference discuss the possibility of RU reuse in light-water reactors (LWRs) (with enrichment) and offer an independent economic analysis of RU reuse. A representative RU uranium 'vector', from reprocessed spent LWR fuel, comprises 98.538 wt% 238U, 0.46 wt% {sup 236}U, 0.986 wt% {sup 235}U, and 0.006 wt% {sup 234}U. After multiple recyclings, the concentration of {sup 234}U can approach 0.02 wt%. The presence of {sup 234}U and {sup 236}U in RU reduces the reactivity and fuel lifetime (exit burnup), which is particularly an issue in LWRs. While in PWR analyses, the burnup penalty caused by the concentration of {sup 236}U in RU needs to be offset by additional {sup 235}U enrichment in the amount of {approx}25% to 30% of the weight percentage of the {sup 236}U; however, the effect in CANDU is much smaller. Furthermore, since the {sup 235}U content in RU exceeds that of natural uranium, CANDU offers the advantageous option of uranium recycling without reenrichment. The exit burnup of CANDU RU-derived fuel is considerably larger than that for natural uranium-fueled scenario, despite the presence of {sup 234}U and {sup 236}U.

Ellis, Ronald James [ORNL

2007-01-01T23:59:59.000Z

239

Sustainability Goals  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainability Goals Sustainability Goals We support and encourage energy conservation and environmental sustainability. Energy Conservation Efficient Water Use & Management...

240

Guide for licensing evaluations using CRAC2: A computer program for calculating reactor accident consequences  

Science Conference Proceedings (OSTI)

A version of the CRAC2 computer code applicable for use in analyses of consequences and risks of reactor accidents in case work for environmental statements has been implemented for use on the Nuclear Regulatory Commission Data General MV/8000 computer system. Input preparation is facilitated through the use of an interactive computer program which operates on an IBM personal computer. The resulting CRAC2 input deck is transmitted to the MV/8000 by using an error-free file transfer mechanism. To facilitate the use of CRAC2 at NRC, relevant background material on input requirements and model descriptions has been extracted from four reports - ''Calculations of Reactor Accident Consequences,'' Version 2, NUREG/CR-2326 (SAND81-1994) and ''CRAC2 Model Descriptions,'' NUREG/CR-2552 (SAND82-0342), ''CRAC Calculations for Accident Sections of Environmental Statements, '' NUREG/CR-2901 (SAND82-1693), and ''Sensitivity and Uncertainty Studies of the CRAC2 Computer Code,'' NUREG/CR-4038 (ORNL-6114). When this background information is combined with instructions on the input processor, this report provides a self-contained guide for preparing CRAC2 input data with a specific orientation toward applications on the MV/8000. 8 refs., 11 figs., 10 tabs.

White, J.E.; Roussin, R.W.; Gilpin, H.

1988-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
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241

REPORT OF THE OBJECTIVES AND PLANS FOR THE AEC'S CIVILIAN POWER GAS COOLED REACTOR PROGRAM  

SciTech Connect

Progress in the U. S. civilian power gas-cooled reactor program is discussed. Gas reactors having technical features of high conversion ratio, high temperature, high fuel burnup, and capability of construction in large sizes make them very attractive as potential producers of economic power in the very near term. The operation of Peach Bottom-HTGR and EGCR in late 1964 and 1965, respectively, will contribute to the successful exploitation of thermal gas- cooled reactors. Since the graphite fuel concept promises very low fuel cycle costs along with reactor coolant conditions that can exceed current practice, it was concluded that the concept provides a long term potential that promises some very exciting possibilities. (auth)

Pahler, R.E.

1963-06-01T23:59:59.000Z

242

Participation in the United States Department of Energy Reactor Sharing Program. Annual report, August 31, 1991--August 29, 1992  

SciTech Connect

The University of Virginia Reactor Facility is an integral part of the Department of Nuclear Engineering and Engineering Physics (to become the Department of Mechanical, Aerospace and Nuclear Engineering on July 1, 1992). As such, it is effectively used to support educational programs in engineering and science at the University of Virginia as well as those at other area colleges and universities. The expansion of support to educational programs in the mid-east region is a major objective. To assist in meeting this objective, the University of Virginia has been supported under the US Department of Energy (DOE) Reactor Sharing Program since 1978. Due to the success of the program, this proposal requests continued DOE support through August 1993.

Mulder, R.U.; Benneche, P.E.; Hosticka, B.

1992-05-01T23:59:59.000Z

243

Final report on the University of Florida U.S. Department of Energy 1995--96 Reactor Sharing Program  

SciTech Connect

Grant support has been well used by the University of Florida as host institution to support various educational institutions in the use of the reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over twelve million inhabitants throughout the State of Florida and still others throughout the nation. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program; where research activities were involved, care was taken to assure the research activities were not funded by grants for contract funding from outside sources. In some cases external grant funding is limited or is used up, in which case the Reactor Sharing Grant and frequent cost sharing by the UFTR facility and the University of Florida provide the necessary support to complete a project or to provide more results to make a complete project even better. In some cases this latter usage has aided renewal of external funding. The role of the Reactor Sharing Program, though relatively small in dollars, has been the single most important occurrence in assuring the rebirth and continued high utilization of the UFTR in a time when many better equipped and better placed facilities have ceased operations. Through dedicated and effective advertising efforts, the UFTR has seen nearly every four-year college and university in Florida make substantive use of the facility under the Reactor Sharing Program with many now regular users. Some have even been able to support usage from outside grants where the Reactor Sharing Grant has served as seed money; still others have been assisted when external grants were depleted.

Vernetson, W.G.

1996-11-01T23:59:59.000Z

244

Sustainable Nuclear Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Enabling a Sustainable Nuclear Energy Future Since its inception, Argonne R&D has supported U.S. Department of Energy nuclear programs and initiatives, including today's...

245

Deviation to the Test Program and Procedures for the 710 Critical Experiment Reactor Control Drum Mockup Experiment  

SciTech Connect

This document describes a deviation from the "Test Program and Procedures for the 710 Critical Experiment Reactor Control Drum Mockup Experiment," TM-64-3-706, which was made in accordance with ITS Standard Practice J80-81 on September 14, 1964. The deviation did not involve a significant change in the safety of the operation.

Sims, F.L.

1964-09-14T23:59:59.000Z

246

CIVILIAN POWER REACTOR PROGRAM. PART III. STATUS REPORT ON LARGE (100 AND 300 MWe) HEAVY WATER-MODERATED POWER REACTORS--AS OF 1960  

SciTech Connect

An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce power for 7.3 mills/kwh in a second generation, full scale plant of the same type. A further reduction to 6.4 mills/kwh should be possible as the result of the recommended ten-year development program. The current development program is adequate for providing the data needed to design and construct a prototype reactor. However, there is no natural U-fueled prototype and no prototype of the chosen reference design scheduled in the U.S. Current technology is sufficiently developed to initiate the design and construction of a pressure tube, boiling D/sub 2/Ocooled, natural UO/sub 2/- fueled reactor prototype plant in the immediate future. This plant would demonstrate the main features of a full scale plant and, in addition. would provide design data which could only be obtained by operation of a natural U- fueled reactor. (auth)

Hutton, J.H.; Davis, S.A.; Graves, C.C.; Duffy, J.G. comps.

1960-08-19T23:59:59.000Z

247

Educational Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainability Workshops Highlights of our Programs Named Postdoctoral Fellowship Program Spring Science Undergraduate Laboratory Internship Faculty opportunities Learning Lab...

248

Office of National Infrastructure & Sustainability | National...  

National Nuclear Security Administration (NNSA)

of National Infrastructure & Sustainability Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices > Office of International Material...

249

Bootstrapping a Sustainable North American PEM Fuel Cell Industry: Could a Federal Acquisition Program Make a Difference?  

DOE Green Energy (OSTI)

The North American Proton Exchange Membrane (PEM) fuel cell industry may be at a critical juncture. A large-scale market for automotive fuel cells appears to be several years away and in any case will require a long-term, coordinated commitment by government and industry to insure the co-evolution of hydrogen infrastructure and fuel cell vehicles (Greene et al., 2008). The market for non-automotive PEM fuel cells, on the other hand, may be much closer to commercial viability (Stone, 2006). Cost targets are less demanding and manufacturers appear to be close, perhaps within a factor of two, of meeting them. Hydrogen supply is a significant obstacle to market acceptance but may not be as great a barrier as it is for hydrogen-powered vehicles due to the smaller quantities of hydrogen required. PEM fuel cells appear to be potentially competitive in two markets: (1) Backup power (BuP) supply, and (2) electrically-powered MHE (Mahadevan et al., 2007a, 2007b). There are several Original Equipment Manufacturers (OEMs) of PEM fuel cell systems for these applications but production levels have been quite low (on the order of 100-200 per year) and cumulative production experience is also limited (on the order of 1,000 units to date). As a consequence, costs remain above target levels and PEM fuel cell OEMs are not yet competitive in these markets. If cost targets can be reached and acceptable solutions to hydrogen supply found, a sustainable North American PEM fuel cell industry could be established. If not, the industry and its North American supply chain could disappear within a year or two. The Hydrogen Fuel Cell and Infrastructure Technologies (HFCIT) program of the U.S. Department of Energy (DOE) requested a rapid assessment of the potential for a government acquisition program to bootstrap the market for non-automotive PEM fuel cells by driving down costs via economies of scale and learning-by-doing. The six week study included in-depth interviews of three manufacturers, visits to two production facilities, review of the literature on potential markets in North America and potential federal government procurements, development of a cost model reflecting economies of scale and learning-by-doing, and estimation of the impact of federal PEM fuel cell procurements on fuel cell system costs and the evolution of private market demand. This report presents the findings of that study. Section 2 outlines the status of the industry and describes potential markets based on interviews of manufacturers and the existing literature. Section 3 describes the modeling methodology including key premises and assumptions, and presents estimates of market evolution under four scenarios: (1) Base Case with no federal government procurement program, (2) Scenario 1, an aggressive program beginning with less than 200 units procured in 2008 ramping up to more than 2,000 units in 2012, (3) Scenario 2 which is identical to Scenario 1 except that the private market is assumed to be twice as sensitive to price, and (4) Scenario 3, a delayed, smaller federal procurement program beginning in 2011 increasing to a maximum of just over 1,000 units per year in 2012. The analysis suggests that the aggressive program of Scenario 1 would likely stimulate a sustainable, competitive North American non-automotive PEM fuel cell industry. Given plausible assumptions about learning rates and scale economies, the procurements assumed in Scenario 1 appear to be sufficient to drive down costs to target levels. These findings are conditional on the evolution of acceptable hydrogen supply strategies, which were not explicitly analyzed in this study. Success is less certain under Scenarios 2 and 3, and there appears to be a strong probability that existing OEMs would not survive until 2011. In the Base Case, no program, a viable North American industry does not emerge before 2020.

Greene, David L [ORNL; Duleep, Dr. K. G. [Energy and Environmental Analysis, Inc., an ICF Company

2008-10-01T23:59:59.000Z

250

The Energy Services Provider as Corporate Engineer: A Partnership in Developing a Productive, Sustainable Energy Management Program  

E-Print Network (OSTI)

Industrial facilities can be large consumers of energy and have significant environmental aspects or impacts. Sustainable management of energy use and the environment is a growing concern for most industrial companies. Effective energy management can lower operating costs, improve profits, and contribute to a company’s progress in eco-efficiency and environmental responsibility. It is often difficult for a company to hire or designate the required person or team to focus on developing an effective energy management program. Developing such a program in an industrial environment can require abroad spectrum of experience and expertise. This paper provides an overview of a unique partnership between an industrial firm and an engineering firm that provides energy services. Cook Composites and Polymers Co. (CCP) is a world leader in the production and distribution of gel coat, composite polyester resins, coatings resins, dispersions, and emulsions. CCP operates at 12 locations in the United States. Burns & McDonnell (BMcD) is a large, multi-disciplined engineering firm with design-build and energy services capabilities. The firms have worked in the past on process design, environmental, and construction projects.

Imel, M.; Gromacki, M.

2007-01-01T23:59:59.000Z

251

U.S. Department Of Energy Advanced Small Modular Reactor R&D Program: Instrumentation, Controls, and Human-Machine Interface (ICHMI) Pathway  

Science Conference Proceedings (OSTI)

Instrumentation, controls, and human-machine interfaces (ICHMI) are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditional analog-based instrumentation, controls, and human-machine interface systems to implementations employing digital technologies. This transition has primarily occurred in an ad hoc fashion through individual system upgrades at existing plants and has been constrained by licenseability concerns. Although the recent progress in constructing new plants has spurred design of more fully digital plant-wide ICHMI systems, the experience base in the nuclear power application domain is limited. Additionally, development of advanced reactor concepts, such as Generation IV designs and small modular reactors, introduces different plant conditions (e.g., higher temperatures, different coolants, etc.) and unique plant configurations (e.g., multiunit plants with shared systems, balance of plant architectures with reconfigurable co-generation options) that increase the need for enhanced ICHMI capabilities to fully achieve industry goals related to economic competitiveness, safety and reliability, sustainability, and proliferation resistance and physical protection. As a result, significant challenges remain to be addressed to enable the nuclear power industry to complete the transition to safe and comprehensive use of modern ICHMI technology. The U.S. Department of Energy (DOE) has recognized that ICHMI research, development, and demonstration (RD&D) is needed to resolve the technical challenges that may compromise the effective and efficient utilization of modern ICHMI technology and consequently inhibit realization of the benefits offered by expanded utilization of nuclear power. Consequently, several DOE programs have substantial ICHMI RD&D elements within their respective research portfolios. This paper describes current ICHMI research in support of advanced small modular reactors. The objectives that can be achieved through execution of the defined RD&D are to provide optimal technical solutions to critical ICHMI issues, resolve technology gaps arising from the unique measurement and control characteristics of advanced reactor concepts, provide demonstration of needed technologies and methodologies in the nuclear power application domain, mature emerging technologies to facilitate commercialization, and establish necessary technical evidence and application experience to enable timely and predictable licensing. 1 Introduction Instrumentation, controls, and human-machine interfaces are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditional analog-based instrumentation, controls, and human-machine interface (ICHMI) systems to implementations employing digital technologies. This transition has primarily occurred in an ad hoc fashion through individual system upgrades at existing plants and has been constrained by licenseability concerns. Although the recent progress in constructing new plants has spurred design of more fully digital plant-wide ICHMI systems, the experience base in the nuclear power application domain is limited. Additionally, development of advanced reactor concepts, such as Generation IV designs and small modular reactors, introduces different plant conditions (e.g., higher temperatures, different coolants, etc.) and unique plant configurations (e.g., multiunit plants with shared systems, balance of plant architectures with reconfigurable co-generation options) that increase the need for enhanced ICHMI capabilities to fully achieve industry goals related to economic competitiveness, safety and reliability, sustainability, and proliferation resistance and physical protection. As a result, significant challenges remain to be addressed to enable the nuclear power industry to complete the transition to safe and comprehensive use of m

Holcomb, David Eugene [ORNL; Wood, Richard Thomas [ORNL

2013-01-01T23:59:59.000Z

252

Rating energy efficiency and sustainability in laboratories: Results and lessons from the Labs21 program  

SciTech Connect

Laboratories are very energy intensive, with significant opportunities for improved efficiency. However, their inherent complexity and variety makes benchmarking of their energy and environmental performance a unique and challenging task. Furthermore, laboratories have a myriad of health and safety requirements that significantly affect energy use, adding complexity to their benchmarking. The Labs21 program, a joint program of the US EPA and US DOE, has developed two resources specifically for assessing laboratory energy and environmental performance: (1) An energy benchmarking tool which allows users to compare laboratories using a standard set of building and system level energy use metrics. (2) The Environmental Performance Criteria (EPC) a point-based rating system that builds on the LEED(TM) green building rating system, designed to score overall environmental performance. In this paper, for each of these tools we present the underlying methodology and results from their use. For the benchmarking tool, we contrast our approach, which includes a simulation model-based component, with those used for other building types. We also present selected results from data collection and analysis of about 40 private and public sector laboratory facilities. In the case of the EPC, we describe variations from the LEED standard, focusing on the energy credits. Finally, using laboratories as a case in point, we discuss lessons learned that can be applied to the development of similar tools for other building types that have complex requirements impacting energy and environmental performance.

Mathew, Paul; Sartor, Dale; van Geet, Otto; Reilly, Sue

2004-05-26T23:59:59.000Z

253

China's Approaches to Financing Sustainable Development: Policies, Practices, and Issues  

E-Print Network (OSTI)

Finance and China’s Sustainable Energy Transition. http://was supported by the China Sustainable Energy Program of theexample is the Sustainable Energy Utility model pioneered in

Shen, Bo

2013-01-01T23:59:59.000Z

254

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

1995-06-30T23:59:59.000Z

255

FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Eleventh Quarterly Progress Report, January-March 1963  

SciTech Connect

Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the flow channel. Natural circulation tests in the hydraulic stability loop were conducted over a range of conditions from stable, to oscillatory with exponential decay, to self-sustaining oscillation of constant amplitude, to unstable oscillations with divergent amplitude. The response to impulses in power input shows the effect of the time delay for transporting steam voids up through the riser. The data permit calculation of oscillation frequency, damping coefficient, time lags, and show the magnitude and character of pressure and velocity changes. The data, which have an experimental scatter of plus or minus 10% maximum, show that burnout heat fiux: decreases with increasing flow up to 2 x 10/sup 8/ lb/hr-ft/sup 2/; has a maximum for hydraulic diameter between 0.25 and 0.5 inch; and decreases for pressure increases between 600 to 1400 psi. A correlating equation for the data is given. The data are compared to results of others. Tests of special geometries show that the burnout heat flux: decreases 22 to 50% when the heated rod is within 0.033 inch of the channel wall; is unchanged upstream of a plate-type spacer; decreases 35 to 50% when the rod surface is roughened by sandblasting; is increased 20 to 40% by use of a rough liner. The four-rod test section is operating satisfactorily and 17 critical heat fiux data points are obtained at 1000 psia and flows of 0.5, 1.0, and 1.5 x 10/sup 6/ lb/hr-ft/sup 2/. In each case the critical heat flux occurred at the exit end and on the side of the rod facing the corner of the channel. The evaluation of film trippers (rough liner) on the unheated channel walls indicates considerable promise for increasing the burnout heat flux limit. The theory of operation is that the liquid film on the unheated wail is sheared off and dispersed, thus adding to the liquid film on the heated rod. Measurements with a heater rod bowed so that it is in contact with the channel wall show that the critical heat flux is decreased by a factor of two or more from values with normal clearance. Temperature measurements on the rod, when operating past the critical heat flux, were in the order of magnitude of 1000 deg F for heat fluxes of about 500,000--600,000 Btu/hr-ft/sup 2/. Chemical analyses for radial variations in isotopic composition within a fuel pellet are nearly completed and are compiled for interpretation. (N.W.R.)

Howard, C.L. comp.

1963-04-01T23:59:59.000Z

256

Materials Reliability Program: Reactor Pressure Vessel Integrity Training Module (MRP-286)  

Science Conference Proceedings (OSTI)

For many reactor pressure vessels, embrittlement is the primary concern in ensuring continued safe operation. The shutdown of the Yankee Rowe plant, which occurred because of uncertainties related to embrittlement of the vessel, demonstrated the importance of adequately addressing embrittlement issues. Managing embrittlement involves the integration, management, and implementation of diverse technical, regulatory, planning, and economic activities. Reactor vessel embrittlement management is an essential ...

2010-11-22T23:59:59.000Z

257

The Ongoing Impact of the U.S. Fast Reactor Integral Experiments Program  

SciTech Connect

The creation of a large database of integral fast reactor physics experiments advanced nuclear science and technology in ways that were unachievable by less capital intensive and operationally challenging approaches. They enabled the compilation of integral physics benchmark data, validated (or not) analytical methods, and provided assurance of future rector designs The integral experiments performed at Argonne National Laboratory (ANL) represent decades of research performed to support fast reactor design and our understanding of neutronics behavior and reactor physics measurements. Experiments began in 1955 with the Zero Power Reactor No. 3 (ZPR-3) and terminated with the Zero Power Physics Reactor (ZPPR, originally the Zero Power Plutonium Reactor) in 1990 at the former ANL-West site in Idaho, which is now part of the Idaho National Laboratory (INL). Two additional critical assemblies, ZPR-6 and ZPR-9, operated at the ANL-East site in Illinois. A total of 128 fast reactor assemblies were constructed with these facilities [1]. The infrastructure and measurement capabilities are too expensive to be replicated in the modern era, making the integral database invaluable as the world pushes ahead with development of liquid metal cooled reactors.

John D. Bess; Michael A. Pope; Harold F. McFarlane

2012-11-01T23:59:59.000Z

258

GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961  

SciTech Connect

Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced power plants, experimental investigations of heat transfer and fluid flow, development of equipment anmd test facilities. and fabrication studies. (M.C.G.)

1962-02-01T23:59:59.000Z

259

Update Sustainable Transportation Program  

NLE Websites -- All DOE Office Websites (Extended Search)

4 * November 2012 4 * November 2012 Titan's computational capability- almost unimaginable-is on par with each of the world's 7 billion people being able to carry out 3 million calculations per second. Accelerating the automotive engine through high performance computing Today's automotive manufacturers are in pursuit of a more perfect internal combustion engine, one designed to meet both consumer and regulatory demands for clean and efficient operation. In a recent online article, Digital Manufacturing Report journalist John Kirkley sheds light on two ORNL-

260

Update Sustainable Transportation Program  

NLE Websites -- All DOE Office Websites (Extended Search)

2 * April 2012 2 * April 2012 HTML expertise and "can do" attitudes solve manufacturing crisis Pumpkin pie is a small sacrifice when it comes to assisting a user. Last November during the Thanksgiving holidays, High Temperature Materials Laboratory staff members worked around the clock to assist global automotive parts manufacturer Cosma International in resolving a component materials issue that briefly interrupted its Clinton, TN operations as well as those at

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Update Sustainable Transportation Program  

NLE Websites -- All DOE Office Websites (Extended Search)

3 * July 2012 3 * July 2012 Boosting the battery industry Future automotive batteries could cost less and pack more power because of ORNL's new Battery Manufacturing Facility. Co-located with the National Transportation Research Center and Manufacturing Demonstration Facility off Hardin Valley Road, the $3 million DOE facility allows for collaboration with industry and other national labs while protecting

262

Update Sustainable Transportation Program  

NLE Websites -- All DOE Office Websites (Extended Search)

with cost-savings and performance benefits Successful multi-year collaborations with industry, universities, and other national labs have enabled the development and industry...

263

Reactor Materials Program electrochemical potential measurements by ORNL with unirradiated and irradiated stainless steel specimens  

Science Conference Proceedings (OSTI)

Effect of irradiation of stainless steel on electrochemical potential (ECP) was investigated by measurements in dilute HNO{sub 3} and H{sub 2}O{sub 2} solutions, conditions simulating reactor moderator. The electrodes were made from unirradiated/irradiated, unsensitized/sensitized specimens from R-reactor piping. Results were inconclusive because of budgetary restrictions. The dose rate may have been too small to produce a significant radiolytic effect. Neither the earlier CERT corrosion susceptibility tests nor the present ECP measurements showed a pronounced effect of irradiation on susceptibility of the stainless steel to IGSCC; this is confirmed by the absence in the stainless steel of the SRS reactor tanks (except for the C Reactor tank knuckle area).

Baumann, E.W.; Caskey, G.R. Jr.

1993-07-01T23:59:59.000Z

264

Materials Reliability Program: Pressurized Water Reactor Issue Management Tables (MRP-205)  

Science Conference Proceedings (OSTI)

This report provides PWR Issue Management Tables (IMTs) that identify, prioritize, and describe R&D gaps related to degradation issues in PWR Reactor Pressure Vessels (RPVs), Reactor Internals, ASME Class 1 Piping Components, Pressurizers, and Steam Generators. An R&D "Gap" is identified whenever there are needs in the areas of degradation mechanism understanding, mitigation techniques, repair/replacement techniques, or inspection & evaluation technologies to provide reasonable assurance that a component...

2006-11-29T23:59:59.000Z

265

US LMFBR (Liquid Metal Fast Breeder Reactor): flow induced vibration program (1977-1986): A summary and overview  

SciTech Connect

This paper summarizes the activities and accomplishments under the US LMFBR Flow Induced Vibration Program for the period 1977-1986. Since 1977 represents the date of the last IAEA IWGFR Specialists Meeting on LMFBR Flow Induced Vibration, this paper thus provides an update to the results presented at that meeting. This period also represents a period of substantial change for the US LMFBR program. A major reactor project, the FFTF, was completed and a second major project, the CRBR plant, was terminated. This change adversely impacted the US flow induced vibration program. Nevertheless, base technology activities have continued. In this paper, research in the following areas is summarized: Vibration characteristics and scaling, Turbulent buffeting and vortex shedding, Fluidelastic instabilities of tube bundles in crossflow, and Instabilities induced by leakage flows.

Wambsganss, M.W.; Chen, S.S.; Mulcahy, T.M.; Jendrzejczyk, J.A.

1986-09-01T23:59:59.000Z

266

Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management  

SciTech Connect

The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

Curtis Smith; James Knudsen; Bentley Harwood

2013-08-01T23:59:59.000Z

267

Advanced Reactor Development and Technology - Nuclear Engineering...  

NLE Websites -- All DOE Office Websites (Extended Search)

Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor...

268

Sustainable Buildings and Campuses | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Campuses and Campuses Sustainable Buildings and Campuses October 4, 2013 - 4:18pm Addthis Sustainable Buildings and Campuses The Federal Energy Management Program (FEMP) provides strategies, best practices, and resources to help Federal agencies implement sustainable design practices within Federal buildings and facilities. Learn about: Sustainable building design basics Federal requirements Sustainability for existing buildings Sustainable design for new construction and major renovations Life cycle cost analysis for sustainability Energy security planning Case studies Interagency Sustainability Working Group. Also see Sustainable Building Contacts. Addthis Related Articles Energy Department Training Breaks New Ground Sustainable Building Contacts Commissioning Training Available

269

Sustainability watch  

Science Conference Proceedings (OSTI)

With the December 2010 issue, inform begins a new column, featuring some of the latest news and research on sustainability. Sustainability watch Inform Magazine Inform Archives Sustainability watch With this issue, infor

270

GAS-COOLED REACTOR PROGRAM SEMIANNUAL PROGRESS REPORT FOR PERIOD ENDING MARCH 31, 1963  

SciTech Connect

Progress is reported on the development of gas-cooled reactors. The report contains eleven sections which are abstracted separately in NSA. These sections are contained in two parts: investigations in support of the Experimental Gas-Cooled Reactor and advanced reactor design and development. The four sections abstracted under Part I are: performance analyses, component development and testing, materials development, and irradiation testing of components and materials. The remaining sections are under Part II and they are: development of fueled-graphite bodies, investigations of fueled-graphite systems, clad fuel development, investigations of moderator materials, studies of advanced systems, experimental investigations of heat transfer and fluid flow, and facilities and equipment. (N.W.R.)

1963-07-23T23:59:59.000Z

271

R and D program for core instrumentation improvements devoted for French sodium fast reactors  

Science Conference Proceedings (OSTI)

Under the framework of French R and D studies for Generation IV reactors and more specifically for sodium-cooled fast reactors (SFR); the CEA, EDF and AREVA have launched a joint coordinated research programme. This paper deals with the R and D sets out to achieve better inspection, maintenance, availability and decommissioning. In particular the instrumentation requirements for core monitoring and detection in the case of accidental events. Requirements mainly involve diversifying the means of protection and improving instrumentation performance in terms of responsiveness and sensitivity. Operation feedback from the Phenix and Superphenix prototype reactors and studies, carried out within the scope of the EFR projects, has been used to define the needs for instrumentation enhancement. (authors)

Jeannot, J. P.; Rodriguez, G.; Jammes, C.; Bernardin, B.; Portier, J. L.; Jadot, F. [Commissariat a l'Energie Atomique, Saint-Paul-lez-Durance, 13108 (France); Maire, S.; Verrier, D. [Advanced Projects and Decommissioning Div. Plant Sector AREVA NP - NEPL-FT, Lyon, 69000 (France); Loisy, F. [EDF - EDF R and D STEP Dept., 6 Quai Watier, Chatou, 78401 (France); Prele, G. [EDF, Generation/Nuclear Engineering, Basic Design Dept., Villeurbanne, 69628 (France)

2011-07-01T23:59:59.000Z

272

Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, April 1, 1983-September 30, 1983  

SciTech Connect

An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity on the Market Definition Task (WBS 03). Within the Plant Technology (WBS 13) task, there were activities to develop analytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. The activities in support of the HTGR-SC/C Lead Plant (WBS 30 and 31) were the participation in the Lead Plant System Engineering (LPSE) effort and the plant simulation task. The efforts on the Advanced HTGR systems was performed under the Modular Reactor Systems (MRS) (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors.

Not Available

1983-12-01T23:59:59.000Z

273

Sustainability Support  

Energy.gov (U.S. Department of Energy (DOE))

Sustainability Support serves as a corporate technical assistance, coordination, and integration resource to support line organizations in the resolution of sustainability issues and management concerns.

274

Sustainable Transport  

E-Print Network (OSTI)

THOUGHT PIECE Sustainable Transport by Melvin M. Webberwant to sustain any mode of transport only if we judge it todraconian in rejecting transport modes that have failed in

Webber, Melvin

2006-01-01T23:59:59.000Z

275

Sustainable Federal Fleets: Fleet Reporting  

NLE Websites -- All DOE Office Websites (Extended Search)

Home | Programs & Offices | Consumer Information U.S. Department of Energy Energy Efficiency and Renewable Energy Sustainable Federal Fleets Welcome, Guest Login | Register...

276

City of Jacksonville- Sustainable Public Buildings  

Energy.gov (U.S. Department of Energy (DOE))

In 2009, the Jacksonville City Office of Sustainability Initiatives announced the creation of the Sustainable Building Program. As part of the program, all new city-owned buildings must meet...

277

Program on Technology Innovation: Evaluation of Wear Characteristics of a Nanofluid in a Pressurized Water Reactor  

Science Conference Proceedings (OSTI)

A nanofluid is a fluid suspension of nanosized particles. It is a relatively new heat transfer fluid that is characterized by enhanced heat transfer properties over those of the base fluid. The enhanced heat transfer properties are desirable for potential use as the coolant in a nuclear reactor.

2008-01-31T23:59:59.000Z

278

Proposed Program: Reliability-Centered Maintenance (RCM) for the High Flux Isotope Reactor  

E-Print Network (OSTI)

There is a desire to implement a reliability-centered maintenance at the High Flux Isotope Reactor (HFIR) at the Oak-Centered Maintenance (RCM) structure is proposed for implementation at the HFIR. This proposed RCM structure is based on widely used and accepted industry practices. The HFIR primary cleanup system is used to provide specific

279

MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING MARCH 31, 1959  

SciTech Connect

Turbomachinery considerations indicated that it would be desirable to reduce the cycle pressure from 1,000 to 800 psia. The problem of determining the temperature distribution and the resulting thermal stress pattern within the graphite was considered. Preliminary designs for a heterogeneous fuel element and a semihomogeneous fuel element were developed. Utilization of the Hanford in- pile gas loop for fuel element testing is discussed. Two-group PDQ calculations were run to estimate control rod worth for the preliminary design core under cold, clean conditions. Curves of rod worth versus position were developed for the hot, clean and the cold, clean preliminary design core. A detailed lifetime calculation was made for the preliminary design heterogeneous core. Fuel cycle costs were estimated on the basis of the effect of B in the fuel elements. The schedule and facilities for the critical experiments are discussed in some detail. The speed of the main turbine shaft was tentatively set at about 12,200 rpm. The design and fabrication of a test stand to evaluate shaft seals and seal systems were completed and trial runs were made. The effects of minor heat transfer due to heat leakage, fluid flow, and thermodynamic phenomena on MGCR full-load cycle performance were studied. Operating characteristics of the heat exchanger test facility are described. A critical review was conducted on the desirability of using concentric ducts and valves. Block diagrams outlining reactor power level, outlet temperature, and plant inventory control are presented. Equations which permit the dynamic analysis of a closed-cycle gas-turbine plant were programed for a digital computer. Descriptions were prepared for fluid-mechanical systems. Several methods of purifying He in both storage bank and main loop were investigated. Investigations into the maximum operating temperatures of the various electrical equipment indicate that temperatures up to 140 deg F can be tolerated. Preliminary design work was carried out on an emergency cooldown system which uses a stored inert coolant. Work on the irradiation stability of fuel materials indicated that conversion from the monocarbide to the dicarbide can take place at 2,350 deg F in graphite bodies containing UC. Densities as high as 96.6% theoretical were obtalned in alumina pellets sintered in H. Xenon released from irradiated UO/sub 2/ granules was measured. Progress was made in the development of high-temperature x-ray-diffraction techniques. Tests were conducted to investigate the effects of coolant and impurities in the coolant on plant materials and the effects of gettering on inhibiting reactions. Economic studies were continued with the objective of determining the optimum size and power ranges for both nuclear and conventionally powered ships. (For preceding period see GA-744.) (W.D.M.)

1960-10-31T23:59:59.000Z

280

MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960  

SciTech Connect

The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit use of gases other than helium. It was further directed that the reactor should be designated BORE for Beryllium- Oxide Reactor Experiment. Reactor development work was mainly in connection with the BORE preliminary design. It was established that the most important information which could be provided by a 10 Mw(t) reactor experiment would be on performance of fuel elements and moderator bodies. This required that the experirment duplicate the power density in the fuel and moderator that would exist in the full size reactor and made it advisable to use full length fuel elements. This resulted in an unconventionally shaped core which is roughly cylindrical with the length more than twice its mean diameter. Studies continued on performance of fuel elements, and methods were developed for calculation of thermal stress in BeO-moderated modules. These studies are equally applicable to the MGCR prototype and BORE. A thermal analysis of the MGCR pressure vessel and thermal shields was performed and means of externally cooling the vessel were studied. Some of the components of the experimental control rod drive mechanism were received. Endurance tests of a ball-nut lead screw in hot helium continued. Heat exchanger tests were resumed after an interruption due to leaks in the tube to tubesheet joints in the test unit. Plant control studies were continued with analyses of the system dynamics with a turbomachinery configuration in which the high pressure turbine provides the output power. This arrangement was found to be more sensitive than the low-pressure drive system. Turbomachinery component tests are providing stage performance data. The seal and bearing test rig was completed and tests were begun. Physics calculations were made for the BORE design. Basic physics information on Fermi age and neutron thermalization in BeO was provided during the quarter by experlments in the linear accelerator. Materials work continued with further investigations of the effect of additives on properties of UC/sub 2/--BeO diluted fuel bodies. Hot cell examination of the MTR-31-3 fuel capsule indicated no significant dimensional changes after burnups from 30,000 to 45,000 Mwd/T. An experiment to determine irradiation effects on BeO was inserted in GETR during September. Work was started on development of high density BeO bodies. Structural materials research continued with completion of a second series of self-welding tests of different metal pairs in high temperature helium. A series of galling tests and a series of creep rupture tests of weld specimens in SA302-B steel were completed. Work on site development included establishing requirements of the BORE for buildings, auxiliary facilities, and utilities. (auth)

1960-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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281

Fiscal year 1999 multi-year work plan, advanced reactors transition program  

SciTech Connect

The Advanced Reactors Transition (ART) has two missions. One, funded by DOE-EM is to transition assigned, surplus facilities to a safe and compliant, low-cost stable, deactivated condition (requiring minimal surveillance and maintenance) pending eventual reuse or D and D. Facilities to be transitioned include the 309 Building/Plutonium Recycle Test Reactor (PRTR) and Nuclear Energy (NE) Legacy Facilities. The second mission, funded by DOE-NE, is to maintain the Fast Flux Test Facility (FFTF) and affiliated 400 Area buildings in a safe and compliant standby condition. The condition of the plant hardware, software and personnel is to be preserved in a manner not to preclude a plant restart.

Gantt, D.A.

1998-09-17T23:59:59.000Z

282

Materials Reliability Program: Third International Conference on Fatigue of Reactor Components (MRP-151)  

Science Conference Proceedings (OSTI)

These proceedings contain information presented at the Third International Conference on Fatigue of Reactor Components held October 3-6, 2004, in Seville, Spain. This third conference was again sponsored by EPRI, the Organisation for Economic Co-Operation and Development (OECD) Nuclear Energy Agency/Committee on the Safety of Nuclear Installations (NEA/CSNI), and the U. S. Nuclear Regulatory Commission (NRC) and hosted by Consejo de Segurida Nuclear (CNS) of Spain.

2005-09-12T23:59:59.000Z

283

Materials Reliability Program: Codes Comparison for Reactor Internals Neutronics, Thermal, and Mechanical Calculations (MRP-354)  

Science Conference Proceedings (OSTI)

During the last few years, the Electric Power Research Institute (EPRI) has led an effort to conduct functionality analyses, which have been performed by AREVA and Westinghouse, to evaluate the potential degradation of reactor internals during life extension to 60 years. The methodologies employed in these functionality analyses make use of different thermal-hydraulic, neutronics, and structural models and computer codes and involve different geometries and loading histories. A comparative ...

2013-09-18T23:59:59.000Z

284

Materials Reliability Program: Utility Preparation for Nondestructive Evaluation of Reactor Vessel Upper Head Penetrations (MRP-360)  

Science Conference Proceedings (OSTI)

The purpose of this report is to provide nuclear power plant owners with recommendations for planning and executing reactor vessel upper head (RVUH) penetration examinations in a manner that will minimize the occurrence of human errors while maximizing the probability of success. RVUH penetrations include control rod drive mechanism, control element drive mechanism, in-core instrumentation, and vent line penetrations. These encompass the standard nomenclatures for domestic utilities but might not ...

2013-12-19T23:59:59.000Z

285

Program on Technology Innovation: Cooling Water Review of the Advanced Light Water Reactor Utility Requirements Document  

Science Conference Proceedings (OSTI)

The EPRI Utility Requirements Document (URD) was developed and last revised in 1999 to provide a list of requirements for the design and construction of new nuclear power plants. The objective of this project was to review URD Vol. III. This volume covers passive advanced light water reactors (ALWRs) for plant design requirements with respect to operations and maintenance (O&M) practices of the plant's cooling water systems (not including the circulating water system used for condenser cooling). The revi...

2007-07-26T23:59:59.000Z

286

Reactor thermal-hydraulic FY 1986 status report for the multimegawatt Space Nuclear Power Program  

SciTech Connect

PNL's 1986 activities can be divided into three basic areas: code assessment, correlation assessment and experimental activities. The ultimate goal of all these activities is developing computer codes and verifying their use to perform the thermal-hydraulic analysis and design of the reactor core and plenum of the various proposed concepts. To perform this task as assessment is made of existing computer codes, models, correlations, and microgravity experimental data.

Krotiuk, W.J.; Antoniak, Z.I.

1986-10-01T23:59:59.000Z

287

Sustainable Building Design Training | Open Energy Information  

Open Energy Info (EERE)

Sustainable Building Design Training Sustainable Building Design Training Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Sustainable Building Design Training Agency/Company /Organization: United States Department of Energy Focus Area: Buildings Resource Type: Training materials Website: www1.eere.energy.gov/femp/program/sustainable_training.html References: Sustainable Building Design Training[1] Logo: Sustainable Building Design Training This training, sponsored by FEMP and other organizations, provides Federal agencies the essential information and skills needed to plan, implement, and manage sustainable buildings and sites. Overview "Sustainable Design Training Opportunities to learn more about sustainable design are available throughout the year. This training, sponsored by FEMP

288

Final environmental statement, Liquid Metal Fast Breeder Reactor Program. Volume 1  

SciTech Connect

Information is presented under the following section headings: LMFBR program options and their compatibility with the major issues affecting commercial development, Proposed Final Environmental Statement for the LMFBR program, December 1974, WASH-1535, supplemental material, and material relating to Proposed Final Environmental Statement review. (DG)

1975-12-01T23:59:59.000Z

289

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description  

SciTech Connect

The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

Not Available

1980-06-01T23:59:59.000Z

290

Program on Technology Innovation: Review of EPRI Advanced Light Water Reactor Utility Requirement Document to Include Small Modular Light Water Reactors  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) conducted a limited scope assessment to better understand what areas of the current EPRI advanced light water reactor (ALWR) Utility Requirement Document (URD) should be modified to ensure that the document is applicable to light water small modular reactors (LWSMRs). The LWSMRs differ from current light water reactors in that LWSMRs are significantly smaller than existing plants and utilize revolutionary design and construction strategies.

2011-04-25T23:59:59.000Z

291

Advanced light water reactor plants system 80+{trademark} design certification program. Annual progress report, October 1, 1993--September 30, 1994  

SciTech Connect

The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80{sup +}{trademark} during the U.S. government`s 1994 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW (1350 MWe) Pressurized Water Reactor (PWR). The design covers an essentially complete plant. It is based on EPRI ALWR Utility Requirements Document (URD) improvements to the Standardized System 80 Nuclear Steam Supply System (NSSS) in operation at Palo Verde Units 1, 2 and 3. The NSSS is a traditional two-loop arrangement with two steam generators, two hot legs and four cold legs, each with a reactor coolant pump. The System 80+ standard design houses the NSSS in a spherical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual barrier to radioactivity release. Other major features include an all-digital, human-factors-engineered control room, an alternate electrical AC power source, an In-Containment Refueling Water Storage Tank (IRWST), and plant arrangements providing complete separation of redundant trains in safety systems. Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of Korea. These units and the System 80+ design form the basis of the Korean standardization program. The Nuclear Island portion of the System 80+ standard design has also been offered to the Republic of China, in response to their bid specification for an ALWR. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was docketed by the Nuclear Regulatory Commission (NRC) in May 1991 and a Draft Safety Evaluation Report (DSER) was issued in October 1992.

Not Available

1995-01-01T23:59:59.000Z

292

Advanced Light Water Reactor Plants System 80+{trademark} Design Certification Program. Annual progress report, October 1, 1992--September 30, 1993  

SciTech Connect

The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80+{trademark} during the US government`s 1993 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW{sub t} (1350 MWe) Pressurized Water Reactor (PWR). The design consists of an essentially complete plant. It is based on evolutionary improvements to the Standardized System 80 nuclear steam supply system in operation at Palo Verde Units 1, 2, and 3, and the Duke Power Company P-81 balance-of-plant (BOP) that was designed and partially constructed at the Cherokee plant site. The System 80/P-81 original design has been substantially enhanced to increase conformance with the EPRI ALWR Utility Requirements Document (URD). Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of Korea. These units form the basis of the Korean standardization program. The full System 80+ standard design has been offered to the Republic of China, in response to their recent bid specification. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was submitted to the NRC and a Draft Safety Evaluation Report was issued by the NRC in October 1992. CESSAR-DC contains the technical basis for compliance with the EPRI URD for simplified emergency planning. The Nuclear Steam Supply System (NSSS) is the standard ABB-Combustion Engineering two-loop arrangement with two steam generators, two hot legs and four cold legs each with a reactor coolant pump. The System 80+ standard plant includes a sperical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual containment.

Not Available

1993-12-31T23:59:59.000Z

293

Steam Generator Management Program: Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 7  

Science Conference Proceedings (OSTI)

This report provides requirements for examination plans and processes that are necessary to meet the performance criteria set forth in the Nuclear Energy Institute (NEI) 97-06, Steam Generator Program.

2007-10-10T23:59:59.000Z

294

Technology Development Program for an Advanced Potassium Rankine Power Conversion System Compatible with Several Space Reactor Designs  

SciTech Connect

This report documents the work performed during the first phase of the National Aeronautics and Space Administration (NASA), National Research Announcement (NRA) Technology Development Program for an Advanced Potassium Rankine Power Conversion System Compatible with Several Space Reactor Designs. The document includes an optimization of both 100-kW{sub e} and 250-kW{sub e} (at the propulsion unit) Rankine cycle power conversion systems. In order to perform the mass optimization of these systems, several parametric evaluations of different design options were investigated. These options included feed and reheat, vapor superheat levels entering the turbine, three different material types, and multiple heat rejection system designs. The overall masses of these Nb-1%Zr systems are approximately 3100 kg and 6300 kg for the 100- kW{sub e} and 250-kW{sub e} systems, respectively, each with two totally redundant power conversion units, including the mass of the single reactor and shield. Initial conceptual designs for each of the components were developed in order to estimate component masses. In addition, an overall system concept was presented that was designed to fit within the launch envelope of a heavy lift vehicle. A technology development plan is presented in the report that describes the major efforts that are required to reach a technology readiness level of 6. A 10-year development plan was proposed.

Yoder, G.L.

2005-10-03T23:59:59.000Z

295

Reactor safety research programs. Quarterly report, July 1-September 30, 1979  

SciTech Connect

The programs include: ultimate heat sink performance measurement; experimental verification of steady state codes: Task A - irradiation results and Task C - code development; graphite nondestructive testing; acoustic emission-flaw relationship for in-service monitoring of nuclear pressure vessels; fuel subassembly procurement and irradiation test program; report of resident engineer at Cadarache, France; core thermal model development; integration of nondestructive examination reliability and fracture mechanics; and steam generator tube integrity.

Hooper, J.L. (comp.)

1980-03-01T23:59:59.000Z

296

Results and Analyses of Irradiation/Anneal Experiments Conducted on Yankee Rowe Reactor Pressure Vessel Surrogate Materials: Yankee Atomic Electric Company Test Reactor Program  

Science Conference Proceedings (OSTI)

Many variables influence the response of reactor vessel steels to neutron irradiation. This study looks at the influence of irradiation temperature, steel heat treatment and microstructure, and nickel and phosphorus content on the irradiation response of high-copper reactor vessel steel. Also addressed are several studies evaluating the potential of thermal annealing to restore the mechanical properties of the steels tested.

1996-03-22T23:59:59.000Z

297

Seismic Safety Margins Research Programs. Assessment of potential increases in risk due to degradation of steam generator and reactor coolant pump supports. [PWR  

Science Conference Proceedings (OSTI)

During the NRC licensing review for the North Anna Units 1 and 2 pressurized-water reactors (PWRs), questions were raised regarding the potential for low-fracture toughness of steam-generator and reactor-coolant-pump supports. Because other PWRs may face similar problems, this issue was incorporated into the NRC Program for Resolution of Generic Issues. The work described in this report was performed to provide the NRC with a quantitative evaluation of the value/impact implications of the various options of resolving the fracture-toughness question. This report presents an assessment of the probabilistic risk associated with nil-ductility failures of steam-generator and reactor-coolant-pump structural-support systems during seismic events, performed using the Seismic Safety Margins Research Program codes and data bases.

Bohn, M. P.; Wells, J. E.; Shieh, L. C.; Cover, L. E.; Streit, R. L.

1983-08-01T23:59:59.000Z

298

Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor  

SciTech Connect

Progress in the development and irradiation testing of high-density fuels for use with low-enriched uranium in research and test reactors is reported. Swelling and blister-threshold temperature data obtained from the examination of miniature fuel plates containing UAl/sub x/, U/sub 3/O/sub 8/, U/sub 3/Si/sub 2/, or U/sub 3/Si dispersed in an aluminum matrix are presented. Combined with the results of metallurgical examinations, these data show that these four fuel types will perform adequately to full burnup of the /sup 235/U contained in the low-enriched fuel. The exothermic reaction of the uranium-silicide fuels with aluminum has been found to occur at about the same temperature as the melting of the aluminum matrix and cladding and to be essentially quenched by the melting endotherm. A new series of miniature fuel plate irradiations is also discussed.

Snelgrove, J.L.; Domagala, R.F.; Wiencek, T.C.; Copeland, G.L.

1983-01-01T23:59:59.000Z

299

Deviation of the Test Program and Procedures for the 710 Critical Experiment Reactor Related to Changes in the core Material Volume Fractions  

SciTech Connect

This document describes a deviation from the "Test Program and Procedures for the 710 Critical Experiment Reactor Loading and Rod Calibrations," TM-63-1-702, which was made in accordance with ITS Standard Practice J80-81 on March 13, 1963. The deviation did not involve a significant change in the safety of the operation.

Sims, F.L.

1963-03-13T23:59:59.000Z

300

Fast Spectrum Molten Salt Reactor Options  

DOE Green Energy (OSTI)

During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

2011-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

MARITIME REACTOR PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1961  

SciTech Connect

Progress is reported on general support of the NS Savannah, operation of the pressurized-water in-pile loop, and advanced core development. A shield survey, iodine adsorption studies, a bioassay development program, preparation of replacement control rod drives, irradiation testing of pressure-vessel steel, a thermal insulation investigation, and an analysis of primary system components for gamm-emitting elements were carried out in the NS Savannah program. Water- chemistry studies in the pressurized-water in-pile: loop were made to determine the specific activities and the chemical compositions of filterable and nonfilterable impurities in the loop water. Fuel development and irradiation tests and core I lifetime studies were carried out in the NS Savannah advanced core development. (M.C.G.)

1962-03-01T23:59:59.000Z

302

Modular Pebble-Bed Reactor Project: Laboratory-Directed Research and Development Program FY 2002 Annual Report  

Science Conference Proceedings (OSTI)

This report documents the results of our research in FY-02 on pebble-bed reactor technology under our Laboratory Directed Research and Development (LDRD) project entitled the Modular Pebble-Bed Reactor. The MPBR is an advanced reactor concept that can meet the energy and environmental needs of future generations under DOE’s Generation IV initiative. Our work is focused in three areas: neutronics, core design and fuel cycle; reactor safety and thermal hydraulics; and fuel performance.

Petti, David Andrew; Dolan, Thomas James; Miller, Gregory Kent; Moore, Richard Leroy; Terry, William Knox; Ougouag, Abderrafi Mohammed-El-Ami; Oh, Chang H; Gougar, Hans D

2002-11-01T23:59:59.000Z

303

RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor; low-enriched uranium  

SciTech Connect

The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and schedules project the uranium density of qualified RERTR fuels for plate-type reactors to grow by approximately 1 g U/cm/sup 3/ each year, from the current 1.7 g U/cm/sup 3/ to the 7.0 g U/cm/sup 3/ which will be reached in late 1988. The technical needs of research and test reactors for HEU exports are also forecasted to undergo a gradual but dramatic decline in the coming years.

Travelli, A.

1983-01-01T23:59:59.000Z

304

PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD MAY 5, 1955 TO JUNE 16, 1955  

SciTech Connect

The current PWR plant and core parameters are listed. Resign requirements are briefly summarized for a radiation monitoring system, a fuel handling water system, a coolant purification system, an electrical power distribution system, and component shielding. Results of studies on thermal bowing and stressing of UO/sub 2/ are reported. A graph is presented of reactor power vs. reactor flow for various hot channel conditions. Development of U-- Mo and U-Nb alloys has been stopped because of the recent selection of UO/sub 2/ fuel material for the PWR core and blanket. The fabrication characteristics of UO/sub 2/ powders are being studied. Seamless Zircaloy-2 tubing has been tested to determine elastic limits, bursting pressures, and corrosion resistance. Fabrication techniques and tests for corrosion and defects in Zircaloy-clad U-Mo and UO/sub 2/ fuel rods are described. The preparation of UO/sub 2/ by various methods is being studied to determine which method produces a material most suitable for PWR fuel elements. The stability of UO/sub 2/ compacts in high temperature water and steam is being determined. Surface area and density measurements have been performed on samples of UO/sub 2/ powder prepared by various methods. Revelopment work on U-- Mo and U--Nb alloys has included studies of the effect on corrosion behavior of additions to the test water, additions to the alloys, homogenization of the alloys, annealing times, cladding, and fabrication techniques. Data are presented on relaxation in spring materials after exposure to a corrosive environment. Results are reported from loop and autoclave tests on fission product and crud deposition. Results of irradiation and corrosion testing of clad and unclad U--Mo and U-Nh alloys are described. The UO/sub 2/ irradiation program has included studies of dimensional changes, release of fission gases, and activity in the water surrounding the samples. A review of the methods of calculating reactor physics parameters has been completed, and the established procedures have been applied to determination of PWR reference design parameters. Critical experiments and primary loop shielding analyses are described. (D.E.B.)

1958-10-31T23:59:59.000Z

305

Sustainable Building Basics | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Areas » Sustainable Buildings & Campuses » Sustainable Program Areas » Sustainable Buildings & Campuses » Sustainable Building Basics Sustainable Building Basics October 4, 2013 - 4:21pm Addthis Image of the side of a sustainable building Sustainable building design results in energy savings and environment stewardship. Sustainable building design and operation strategies demonstrate a commitment to energy efficiency and environmental stewardship. These approaches result in an optimal balance of energy, cost, environmental, and societal benefits, while still meeting the mission of a Federal agency and the function of the facility or infrastructure. For buildings and facilities, responsible resource management and the assessment of operational impacts encompass the principles of sustainability. Sustainable development aims to meet the needs of the

306

Preliminary nuclear safety assessment of the NEPST (Topaz II) space reactor program  

SciTech Connect

The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz II space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as; neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz II system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway.

Marshall, A.C.

1993-01-01T23:59:59.000Z

307

PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD SEPTEMBER 9 TO OCTOBER 20, 1955  

SciTech Connect

Progress in the design, development, and construction of PWR power plant systems and components and PWR core and auxiliaries is summarized. The blanket assembly design is described and illustrated. Results of MTR evaluation of fuel element failure instrumentation are reported. Development of fabrication and testing tochaiques for clad fuel elements, fuel rods, plates, and assemblies is described. Investigations of fuel and cladding alloys include crystal structure and thermal stability determinations on U--Mo alloys, studies on the nature of the hydride phase formed during corrosion of gamma -phase alloys in high- temperature water, and specific heat, resistivity, and phase diagram studies of U- -Mo and U--Nb alloys. The equilibrium and kinetics in the system UO/sub 2/--O/ sub 2/ are being studied to gain information on the structure and stability of UO/ sub 2/ under various conditions. Results of irradiation tests on UO/sub 2/ samples and of thermal cycling tests of Zircaloy-2 clad UO/sub 2/ rods are reported. Corrosion test resuIts are summarized for unclad and Zircaloy-2 clad U- - Mo and U--Nb samples. The radiation induced volume change of prototype fuel reds has been investigated. Studies of the fabrication cladding, tensile properties, and corrosion of U-- Si systems are described. Corrosion tests are continuing on Zircaloy-2 clad U-- Zr fuel elements and on various experimental Al alloys for cladding applications. Work was continued on the preparation, corrosion and sinterability of pure UO/sub 2/ and UO/sub 2/ containing additives. Operation and chemical analysis of in-pile loop experiments are described. Results are reported from studies of the erosion of UO/sub 2/ in high-velocity coolant, decontamination of water by ion exchange resins, sorption of radioisotopes on stainless steel, and decontamination of corrosion loops. Work in reactor physics has included PWR control calculations using a 2-dimensional UNIVAC code, calculation of fission product activity in the primary coolant, and criticaiity studies on the Flexibie Critical Experiment and on a lattice of UO/ sub 2/ fuel reds in the TRX. Current PWR plant parameters are recapitulated. (D.E.B.)

1958-10-31T23:59:59.000Z

308

Guiding Tours of the LA River and Promoting Sustainability  

E-Print Network (OSTI)

River and Promoting Sustainability T his spring, I’m pleaseds new M.A. in Urban Sustainability program, and excitedlyCSW research scholars Sustainability,” on the central role

Price, Jenny

2011-01-01T23:59:59.000Z

309

Sustainable Forward Operating Base Nuclear Power Evaluation (Relationship Mapping System) Users’ Manual  

SciTech Connect

The Sustainable Forward Operating Base (FOB) Nuclear Power Evaluation was developed by the Idaho National Laboratory Systems Engineering Department to support the Defense Advanced Research Projects Agency (DARPA) in assessing and demonstrating the viability of deploying small-scale reactors in support of military operations in theatre. This document provides a brief explanation of how to access and use the Sustainable FOB Nuclear Power Evaluation utility to view assessment results as input into developing and integrating the program elements needed to create a successful demonstration.

Not Listed

2012-01-01T23:59:59.000Z

310

Postdoctoral Fellowship Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

directed by Enrico Fermi achieved a sustained chain reaction in the world's first nuclear reactor. Throughout the war, Compton would remain a prominent scientific adviser...

311

Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2  

SciTech Connect

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

NONE

1997-12-01T23:59:59.000Z

312

Sustainability Watch  

Science Conference Proceedings (OSTI)

This month’s Sustainability Watch column was provided by Marguerite Torrey, inform technical projects editor. Following is her summary of the hot topic on sustainable technologies presented on Tuesday, May 3, at the 102nd AOCS Annual Meeting & Expo. Sustai

313

Sustainable Hydrogen Fueling Station, California State University, Los Angeles - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

NLE Websites -- All DOE Office Websites (Extended Search)

8 8 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report David Blekhman California State University Los Angeles Los Angeles, CA 90032 Phone: (323) 343-4569 Email: blekhman@calstatela.edu DOE Managers HQ: Jason Marcinkoski Phone: (202) 586-7466 Email: Jason.Marcinkoski@ee.doe.gov GO: Gregory Kleen Phone: (720) 356-1672 Email: Gregory.Kleen@go.doe.gov Contract Number: DE-EE0000443 Subcontractors: * General Physics Corporation, Elkridge, MD * Weaver Construction, Anaheim, CA Project Start Date: January, 2009 Project End Date: December, 2012 *Congressionally directed project Fiscal Year (FY) 2012 Objectives Procure core equipment for the California State *

314

CIVILIAN POWER REACTOR PROGRAM. PART I. SUMMARY OF TECHNICAL AND ECONOMIC STATUS AS OF 1960. HEAVY WATER-MODERATED POWER REACTORS  

SciTech Connect

A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)

Hutton, J.H.; Davis, S.A.; Graves, C.C.; Duffy, J.G. comps.

1960-08-19T23:59:59.000Z

315

ORGANIC COOLANT REACTOR PROGRAM QUARTERLY REPORT, JANUARY 1-MARCH 31, 1962  

DOE Green Energy (OSTI)

The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe can figure in the formation of film and of the iron percarbide observed. The program of synthesis of pure samples of polyphenyls neared completion, and the attention was shifted to synthesis of new candidate coolants. Fused-ring structures, partially hydrog-enated, such as dihydrophenanthrene were made and proved of interest. Similar studies from the stabilizer investigation indicate the same thing. Other groups in which synthetic activity was initiated are the substituted triazines, pyridines, and other heterocyclic nonbenzenoid types. The industrial coolant candidates from petroleum and coal tar were found to be lacking in thermal stability above 700 deg F. Only the hydrodealkylated decant oil appeared to have promise for future development. The study of hydrocracking high boiler neared completion. Very good results were obtained using unfractionated coolants. and with the most recent high boiler produced at OMRE. An economic survey of processing high boiler to reclaim coolant is nearing completion. Close technical liaison continued throughout the quarter with AEC- IDO and Fluor Corp on the Title ll design of the Coolant Technology Loop (CTL) and the Fuel Technology Loop (FTL). Title I review of the loop handling equipment was completed. The scheduled completion date for the loops is currently being revised. However, procurement of material and equipment is progressing adequately to meet the required dates for field installation. Construction of the Component Development Test Loop (CDTL) was completed and operational shakedown of the loop started. Successful operation at 550 deg F was realized. lnitial operation and testing of a single-stage Chempump in the CDTL showed a high mass transfer of the hot (up to 550 deg F) pumped fluid from the pump discharge, through the rotor chamber, and back to the pump suction. The necessary parts were returned to the manufacturer for modification. lnitial testing of the ball valve has shown acceptable results. A report, IDO16675, containing complete details of the EOCR control rod latch reliability test was issued. A conceptual design of the FTL nuclear mockup was completed. This mockup will duplicate the nuclear characteristics of the in-pile tube containing a fuel-follower sample for the A-3 core loading. Detailed design of the approach-to-power samples is nearing completion. The eight driver elements being instrumented are D-4, D-6, D-9, D-10, D-11, D-12, D-16, and P-12. These elements were chosen on the basis of coolant flow, flux distribution, core symmetry, and rod programming. A successful run was made demonstrating displacement of Santowax OMP with ethylene glycol from a small model fuel element.

None

1962-06-29T23:59:59.000Z

316

Venice Sustainability Advisory Panel  

E-Print Network (OSTI)

Venice Sustainability Advisory PanelFINAL REPORT Venice Sustainability Advisory Panel FinalInvestigator The Venice Sustainability Advisory Panel (

2009-01-01T23:59:59.000Z

317

Interagency Sustainability Working Group | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Areas » Sustainable Buildings & Campuses » Interagency Program Areas » Sustainable Buildings & Campuses » Interagency Sustainability Working Group Interagency Sustainability Working Group October 4, 2013 - 5:00pm Addthis The Interagency Sustainability Working Group (ISWG) is the coordinating body for sustainable buildings in the Federal Government. The ISWG: Serves as a forum for information exchange and promotes agency implementation of goals for high-performance and sustainable buildings Develops policy and reporting guidance that fosters the widespread adoption of sustainable design and operations in the Federal sector Develops technical guidance and tools to support implementation of agency sustainability policies for Federally owned, operated, and leased buildings. The ISWG is also charged with providing assistance for implementing the

318

Materials Reliability Program: An Assessment of the Control Rod Drive Mechanism (CRDM) Alloy 600 Reactor Vessel Head Penetration PWS CC Remedial Techniques (MRP-61)  

Science Conference Proceedings (OSTI)

Service experience over the past decade with control rod drive mechanism (CRDM) penetrations in pressurized water reactors (PWRs) worldwide confirmed primary water stress corrosion cracking (PWSCC) in alloy 600 base metal at several plants. This report summarizes the evaluations and results of an autoclave-accelerated stress corrosion cracking (SCC) test program designed to assess the effectiveness of selected surface remedial techniques to mitigate alloy 600 PWSCC in PWR vessel head penetration base and...

2003-07-14T23:59:59.000Z

319

A Three Dimensional Heterogeneous Coarse Mesh Transport Method for Reactor Calculations.  

E-Print Network (OSTI)

??Current advancements in nuclear reactor core design are pushing reactor cores towards greater heterogeneity in an attempt to make nuclear power more sustainable in terms… (more)

Forget, Benoit

2006-01-01T23:59:59.000Z

320

In Search of Sustainability  

E-Print Network (OSTI)

Review: In Search of Sustainability By Jenny Goldie, Boband Bryan Furnass. In Search of Sustainability. Collingwood,in sustainability. In Search of Sustainability opens with an

Hamilton-Smith, Elery

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Reactor Vessel Internals Inspection and Reactor Pressure Vessel Surveillance Program Summaries for R.E. Ginna and Nine Mile Point Unit 1  

Science Conference Proceedings (OSTI)

This report provides a summary of project activities involving the reactor pressure vessel and internals for the nuclear power plants included in the joint Electric Power Research Institute (EPRI), Department of Energy (DOE), and Constellation Energy Nuclear Group (CENG) Nuclear Plant Life Extension demonstration project.BackgroundThe project focused on continuing operations at two CENG nuclear units that are currently operating in their extended license ...

2013-12-18T23:59:59.000Z

322

LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water Reactor Sustainability (LWRS) Program and EPRI's Long-Term Operations (LTO) Program. To ensure that a proper linkage is maintained between the programs, DOE-NE and EPRI executed a Memorandum of Understanding in late 2010 to "establish guiding principles under which research activities (between LWRS and LTO) could be

323

LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan LWRS Program and EPRI Long-Term Operations Program - Joint R&D Plan To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy's (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE's Light Water Reactor Sustainability (LWRS) Program and EPRI's Long-Term Operations (LTO) Program. To ensure that a proper linkage is maintained between the programs, DOE-NE and EPRI executed a Memorandum of Understanding in late 2010 to "establish guiding principles under which research activities (between LWRS and LTO) could be

324

DOE_Sustainability_and_Green_Zia_Awards  

NLE Websites -- All DOE Office Websites (Extended Search)

prevention practices and for excellence and long-term environmental and economic sustainability. In place since 1996, the Green Zia Environmental Leadership Program is a part of...

325

California National Guard Sustainability Planning, Hydrogen Fuel...  

NLE Websites -- All DOE Office Websites (Extended Search)

Army National Guard, Environmental Programs Directorate California National Guard Sustainability Planning, Hydrogen Fuel Goals 27 Oct 08 Lt Col Reuben Sendejas Lt Col Reuben...

326

City of Jacksonville - Sustainable Public Buildings (Florida...  

Open Energy Info (EERE)

http:www.coj.netdepartmentsneighborhoodsenvironmental-qualityoffice-of-sustainability-initiativessustainable-building-program.aspx Date added to DSIRE 2010-11-05 Last...

327

Environmental Sustainability  

NLE Websites -- All DOE Office Websites (Extended Search)

Environment » Environment » Environmental Stewardship » Environmental Sustainability /community-environment/_assets/images/icon_earthday.jpg Environmental Sustainability: Creating the Future Exercising our commitment to operating a sustainable site by creating a 50-year horizon of planning and preparing for effective environmental stewardship while executing national mission. Sustainability Goals» Recycling» Green Purchasing» Pollution Prevention» Reusing Water» Feature Stories» LOOK INTO LANL - highlights of our science, people, technologies close Novel cellulose structure requires fewer enzymes to process biomass to fuel Improved methods for breaking down cellulose nanofibers are central to cost-effective biofuel production. READ MORE An enzyme (shown in blue) pulls out individual cellulose chains (pink) from the pretreated nanofiber surface (green) and then breaks them apart into simple sugars. Image credit, Shishir Chundawat, Great Lakes Bioenergy Research Center.

328

Reactor sharing experience at the MIT research reactor  

SciTech Connect

This paper provides a number of examples of how educational institutions in the Boston area and elsewhere that do not possess nuclear reactors for training and research purposes have successfully enriched their programs through utilization of the Massachusetts Institute of Technology Research Reactor (MITR) with assistance from the Reactor Sharing Program of the US Department of Energy (DOE).

Clark, L. Jr.; Fecych, W.; Young, H.H.

1985-01-01T23:59:59.000Z

329

Evaluation of Local Enforcement of Energy Efficiency Standards and Labeling Program in China  

E-Print Network (OSTI)

was supported by the China Sustainable Energy Program of thewas supported by the China Sustainable Energy Program of the

Zheng, Nina

2013-01-01T23:59:59.000Z

330

Compliance and Verification of Standards and Labeling Programs in China: Lessons Learned  

E-Print Network (OSTI)

was supported by the China Sustainable Energy Program of thewas supported by the China Sustainable Energy Program of the

Saheb, Yamina

2011-01-01T23:59:59.000Z

331

Generation -IV Reactor Concepts  

NLE Websites -- All DOE Office Websites (Extended Search)

Generation-IV Reactor Concepts Generation-IV Reactor Concepts Thomas H. Fanning Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439, USA The Generation-IV International Forum (GIF) is a multi-national research and development (R&D) collaboration. The GIF pursues the development of advanced, next generation reactor technology with goals to improve: a) sustainability (effective fuel utilization and minimization of waste) b) economics (competitiveness with respect to other energy sources) c) safety and reliability (e.g., no need for offsite emergency response), and d) proliferation resistance and physical protection The GIF Technology Roadmap exercise selected six generic systems for further study: the Gas- cooled Fast Reactor (GFR), the Lead-cooled Fast Reactor (LFR), the Molten Salt Reactor (MSR),

332

Y-12 Site Sustainability Plan  

SciTech Connect

The accomplishments to date and the long-range planning of the Y-12 Energy Management and Sustainability and Stewardship programs support the U.S. Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) vision for a commitment to energy effi ciency and sustainability and to achievement of the Guiding Principles. Specifi cally, the Y-12 vision is to support the Environment, Safety and Health Policy and the DOE Strategic Sustainability Performance Plan, while promoting overall sustainability and reduction of greenhouse gas emissions. The mission of the Y-12 Energy Management program is to incorporate energy-effi cient technologies site-wide and to position Y-12 to meet NNSA energy requirement needs through 2025 and beyond. The plan addresses greenhouse gases, buildings, fleet management, water use, pollution prevention, waste reduction, sustainable acquisition, electronic stewardship and data centers, site innovation and government-wide support.

Spencer, Charles G

2012-12-01T23:59:59.000Z

333

Materials Reliability Program: Background of Reactor Vessel Material Surveillance Programs and Recommended Data Validation Protocol for the Radiation Embrittlement Archive Project (REAP) Database (MRP-369)  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) staff is currently developing an updated, comprehensive reactor vessel surveillance database as a replacement for the Power Reactor Embrittlement Database Version 3 (PR-EDB). The new database—called “Radiation Embrittlement Archive Project,” or REAP—will be available to the public via the Internet. The REAP database contains essential information on the materials and test results from surveillance capsules in U.S. plants; these ...

2013-07-25T23:59:59.000Z

334

Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel  

Science Conference Proceedings (OSTI)

Expanding interest in nuclear power and advanced fuel cycles indicate that use of mixed-oxide (MOX) fuel in the current and new U.S. reactor fleet could become an option for utilities in the coming decades. In light of this renewed interest, EPRI has reviewed the substantial knowledge base on MOX fuel irradiation in light water reactors (LWRs). The goal was to evaluate the technical feasibility of MOX fuel use in the U.S. reactor fleet for both existing and advanced LWR designs (Generation III/III+).

2009-05-29T23:59:59.000Z

335

Fuel Reliability Program: Post-Irradiation Examination and Performance Assessment of ATRIUM-10 BWR Fuel from Browns Ferry-3 Reactor  

Science Conference Proceedings (OSTI)

ATRIUM-10 design (10x10 lattice) fuel was irradiated for one 24-month period during Cycle 12 to 25 MWd/kgU rod-average exposure at Tennessee Valley Authority's Browns Ferry Unit 3 reactor. The project goal was to characterize the behavior of modern boiling water reactor (BWR) fuel at low exposures to assess early-life performance in a well-documented reactor environment. This report includes results from hot cell post-irradiation examinations. In a future Electric Power Research Institute (EPRI) report, ...

2011-06-09T23:59:59.000Z

336

Programming  

Science Conference Proceedings (OSTI)

The First TMS Summit on Creating and Sustaining Diversity in the Minerals, Metals, and Materials Professions (DMMM1): Honoring the First Female Member of ...

337

Sustainable Polymers Staff  

Science Conference Proceedings (OSTI)

Sustainable Polymers Staff Directory. Kathryn Beers, Group Leader. ... Contact. Sustainable Polymers Kathryn L. Beers, Group Leader. ...

2013-07-09T23:59:59.000Z

338

High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1980  

SciTech Connect

Research activities are described concerning HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; HTR core evaluation; reactor physics; shielding; application and project assessments; and HTR Core Flow Test Loop studies.

Not Available

1981-08-01T23:59:59.000Z

339

FEMP Resources for Sustainable Buildings | Open Energy Information  

Open Energy Info (EERE)

FEMP Resources for Sustainable Buildings FEMP Resources for Sustainable Buildings Jump to: navigation, search Tool Summary Name: FEMP Resources for Sustainable Buildings Agency/Company /Organization: United States Department of Energy Sector: Energy Focus Area: Buildings Resource Type: Training materials Website: www1.eere.energy.gov/femp/program/sustainable_resources.html References: FEMP Resources for Sustainable Buildings[1] Logo: FEMP Resources for Sustainable Buildings This resource offers many helpful resources about sustainable design and operations to Federal facility managers and other personnel. FEMP also offers training opportunities about sustainable design and practices. Overview "Many helpful resources about sustainable design and operations are available to Federal facility managers and other personnel. These resources

340

Program on Technology Innovation: Weld Metals and Welding Processes for Fabrication of Advanced Light Water Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Light water reactors have traditionally been constructed using roll-formed plates for the reactor pressure vessel (RPV) shells, which were assembled via horizontal and vertical seam welds. Weld filler metals often contained significant quantities of copper, other residual elements such as vanadium, and nonmetallic elements such as phosphorous and sulfur. Low-alloy steel weld filler metals of this chemical composition contributed to the degree of neutron radiation-induced embrittlement of vessel ...

2013-06-26T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

NP-3319, January 1984: Physically Based Regression Correlations of Embrittlement Data From Reactor Pressure Vessel Surveillance Programs  

Science Conference Proceedings (OSTI)

The first physically based model for forecasting the embrittlement behavior of irradiation-damaged steels proved much more accurate than earlier models. Thisadvance offers utilities greater precision in establishing operating pressure-temperature limits for PWRs and in assessing the ability of reactor vessels to withstand pressurized thermal shock transients.BackgroundBombardment by high-energy neutrons in the belt line of nuclear reactors can ...

1984-01-31T23:59:59.000Z

342

Materials Reliability Program: Pressurized Water Reactor Issue Management Table, PWR-IMT Consequence of Failure (MRP-156)  

Science Conference Proceedings (OSTI)

The Industry Initiative on the Management of Materials Issues provides a proactive, safety-focused approach to the management of materials degradation. In support of this initiative, EPRI formed the Materials Degradation Assessment/Issue Management Table Ad-Hoc Committee and developed an Issue Management Table (IMT) for reactor coolant system components. This report provides initial input to the IMT to address the consequences of failure for the identified components in the reactor coolant system for ope...

2005-12-16T23:59:59.000Z

343

Prepared by the FAS Green Program, a partnership between the FAS Office of Physical Resources and Planning and Harvard's Office for Sustainability Website: green.harvard.edu/fas Email: energy@fas FAS Campus Sustainability Report  

E-Print Network (OSTI)

with green move-in, followed with waste reduction, water and energy conservation, and finishing with green is to promote energy and water con- servation, and recycling and waste reduc- tion. 67% HUDS staff participated and Planning and Harvard's Office for Sustainability Website: green.harvard.edu/fas Email: energy@fas 1 FAS

Paulsson, Johan

344

Economic Sustainability  

E-Print Network (OSTI)

This report is part of a series of research studies into alternative energy and resource pathways for the global economy. In addition to disseminating original research findings, these studies are intended to contribute to policy dialog and public awareness about environment-economy linkages and sustainable growth. All opinions expressed here are those of the author and should not be attributed to their affiliated institutions. For this project on Energy Pathways, we express thanks to Next 10, who recognized the importance of this issue for California’s sustainable growth agenda and provided conceptual impetus and financial support. Thanks are also due for outstanding research assistance by the following:

David Roland-holst; Fredrich Kahrl; Jennifer Baranoff; Alex Cheng; Adrian Li; Jennifer Ly; Cristy Sanada; Lawrence Shing; Sam Beckerman; Billie Chow; Deal Shelley Jiang; Tom Lueker; Xian Ming Li; Mehmet Seflek; F. Noel Perry; Morrow Cater; Sarah Henry; Adam Rose; John A. “skip

2009-01-01T23:59:59.000Z

345

TMS 2012: Technical Program  

Science Conference Proceedings (OSTI)

This programming track focuses such energy related issues as developing advanced new systems, improving existing energy systems, sustainable production of ...

346

TMS 2011: Technical Program  

Science Conference Proceedings (OSTI)

This programming track focuses such energy related isues as developing advanced new systems, improving existing energy systems, sustainable production of ...

347

Baldrige Program Transition  

Science Conference Proceedings (OSTI)

The Baldrige Performance Excellence Program is transitioning to a Sustainable, Enterprise Model. ... A Vision to Be Among the Best. ...

2013-08-06T23:59:59.000Z

348

EL Program: Sustainable Engineered Materials  

Science Conference Proceedings (OSTI)

... surface damage, electrical aging, and dispersion of ... power industry and utilities, construction and infrastructure materials specifiers ...

2013-01-02T23:59:59.000Z

349

Reactor Materials Program - Baseline Material Property Handbook - Mechanical Properties of 1950's Vintage Stainless Steel Weldment Components, Task Number 89-23-A-1  

SciTech Connect

The Process Water System (primary coolant) piping of the nuclear production reactors constructed in the 1950''s at Savannah River Site is comprised primarily of Type 304 stainless steel with Type 308 stainless steel weld filler. A program to measure the mechanical properties of archival PWS piping and weld materials (having approximately six years of service at temperatures between 25 and 100 degrees C) has been completed. The results from the mechanical testing has been synthesized to provide a mechanical properties database for structural analyses of the SRS piping.

Stoner, K.J.

1999-11-05T23:59:59.000Z

350

Sustainability | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainability Sustainability Subscribe to RSS - Sustainability Sustainability is a set of practices in business, government and at home aimed at minimizing humans' impact on the environment and cutting greenhouse gas emissions by reducing waste, recycling, composting, conserving natural parks and numerous other efforts. Another Gold for PPPL: Laboratory Wins 2nd Gold GreenBuy Award PPPL has received a gold GreenBuy award from the U.S. Department of Energy for its green purchasing program in 2012 - winning the award for the second year. The Laboratory was only one of four laboratories to receive the highest honors for its green buying program and one of two, with the DOE's National Renewable Energy Laboratory in Golden, Colo., to receive the award for the second year.

351

In Search of Sustainability  

E-Print Network (OSTI)

Review: In Search of Sustainability By Jenny Goldie, BobFurnass. In Search of Sustainability. Collingwood, Victoria,the movement towards sustainability. It inevitably reflects

Hamilton-Smith, Elery

2005-01-01T23:59:59.000Z

352

Sustainability of products.  

E-Print Network (OSTI)

???Sustainability is a hot topic for years and sustainability assessment has been generally used as an approach to assess the level of sustainability. For the… (more)

???.

2012-01-01T23:59:59.000Z

353

Review: Hijacking Sustainability  

E-Print Network (OSTI)

addressing the attack on sustainability, Sharon Beder’s 2002Review: Hijacking Sustainability By Adrian Parr Reviewed byParr, Adrian. Hijacking Sustainability. Cambridge, MA: MIT

Antonelli, Monika

2010-01-01T23:59:59.000Z

354

The Illusion of Sustainability  

E-Print Network (OSTI)

K.M. Aziz. (1996). “Sustainability of a Water, SanitationFrom Rio to Iragua: Sustainability versus Efficiency andThe Illusion of Sustainability* Michael Kremer Department of

Kremer, Michael Robert; Miguel, Edward A.

2004-01-01T23:59:59.000Z

355

Sustainability and Transport  

E-Print Network (OSTI)

2005. Integrating Sustainability into the Trans- portationTHOUGHT PIECE Sustainability and Transport by Richardof the concept of sustainability to transport planning. In

Gilbert, Richard

2006-01-01T23:59:59.000Z

356

System Engineering Program Applicability for the High Temperature Gas-Cooled Reactor (HTGR) Component Test Capability (CTC)  

SciTech Connect

This white paper identifies where the technical management and systems engineering processes and activities to be used in establishing the High Temperature Gas-cooled Reactor (HTGR) Component Test Capability (CTC) should be addressed and presents specific considerations for these activities under each CTC alternative

Jeffrey Bryan

2009-06-01T23:59:59.000Z

357

Fission reactors and materials  

SciTech Connect

The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions.

Frost, B.R.T.

1981-12-01T23:59:59.000Z

358

Technology gap analysis on sodium-cooled reactor fuel handling system supporting advanced burner reactor development.  

Science Conference Proceedings (OSTI)

The goals of the Global Nuclear Energy Partnership (GNEP) are to expand the use of nuclear energy to meet increasing global energy demand in an environmentally sustainable manner, to address nuclear waste management issues without making separated plutonium, and to address nonproliferation concerns. The advanced burner reactor (ABR) is a fast reactor concept which supports the GNEP fuel cycle system. Since the integral fast reactor (IFR) and advanced liquid-metal reactor (ALMR) projects were terminated in 1994, there has been no major development on sodium-cooled fast reactors in the United States. Therefore, in support of the GNEP fast reactor program, the history of sodium-cooled reactor development was reviewed to support the initiation of this technology within the United States and to gain an understanding of the technology gaps that may still remain for sodium fast reactor technology. The fuel-handling system is a key element of any fast reactor design. The major functions of this system are to receive, test, store, and then load fresh fuel into the core; unload from the core; then clean, test, store, and ship spent fuel. Major requirements are that the system must be reliable and relatively easy to maintain. In addition, the system should be designed so that it does not adversely impact plant economics from the viewpoints of capital investment or plant operations. In this gap analysis, information on fuel-handling operating experiences in the following reactor plants was carefully reviewed: EBR-I, SRE, HNPF, Fermi, SEFOR, FFTF, CRBR, EBR-II, DFR, PFR, Rapsodie, Phenix, Superphenix, KNK, SNR-300, Joyo, and Monju. The results of this evaluation indicate that a standardized fuel-handling system for a commercial fast reactor is yet to be established. However, in the past sodium-cooled reactor plants, most major fuel-handling components-such as the rotatable plug, in-vessel fuel-handling machine, ex-vessel fuel transportation cask, ex-vessel sodium-cooled storage, and cleaning stations-have accumulated satisfactory construction and operation experiences. In addition, two special issues for future development are described in this report: large capacity interim storage and transuranic-bearing fuel handling.

Chikazawa, Y.; Farmer, M.; Grandy, C.; Nuclear Engineering Division

2009-03-01T23:59:59.000Z

359

Canada-Sustainable Communities Leadership Academy (SCLA) | Open Energy  

Open Energy Info (EERE)

Canada-Sustainable Communities Leadership Academy (SCLA) Canada-Sustainable Communities Leadership Academy (SCLA) Jump to: navigation, search Logo: Canada-Sustainable Communities Leadership Academy (SCLA) Name Canada-Sustainable Communities Leadership Academy (SCLA) Agency/Company /Organization Institute for Sustainable Communities (ISC) Partner Smart Growth America, Housing and Urban Development (HUD) Sector Climate, Energy Focus Area Buildings, Economic Development, Energy Efficiency, Food Supply, Greenhouse Gas, Land Use, People and Policy, Transportation, Water Conservation Topics Adaptation, Finance, Implementation, Low emission development planning, Policies/deployment programs Program Start 2008 Program End 2015 Country Canada Northern America References Sustainable Communities Leadership Academy[1]

360

United States-Sustainable Communities Leadership Academy (SCLA) | Open  

Open Energy Info (EERE)

United States-Sustainable Communities Leadership Academy (SCLA) United States-Sustainable Communities Leadership Academy (SCLA) Jump to: navigation, search Logo: United States-Sustainable Communities Leadership Academy (SCLA) Name United States-Sustainable Communities Leadership Academy (SCLA) Agency/Company /Organization Institute for Sustainable Communities (ISC) Partner Smart Growth America, Housing and Urban Development (HUD) Sector Climate, Energy Focus Area Buildings, Economic Development, Energy Efficiency, Food Supply, Greenhouse Gas, Land Use, People and Policy, Transportation, Water Conservation Topics Adaptation, Finance, Implementation, Low emission development planning, Policies/deployment programs Program Start 2008 Program End 2015 Country United States Northern America References Sustainable Communities Leadership Academy[1]

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Y-12 Site Sustainability Plan  

Science Conference Proceedings (OSTI)

The accomplishments to date and the long-range planning of the Y-12 Energy Management and Sustainability and Stewardship programs support the DOE and the National Nuclear Security Administration (NNSA) vision for a commitment to energy efficiency and sustainability and to achievement of the Guiding Principles. Specifically, the Y-12 vision is to support the Environment, Safety and Health Policy and the DOE Strategic Sustainability Performance Plan (SSPP) while promoting overall sustainability and reduction of greenhouse gas (GHG) emissions. Table ES.2 gives a comprehensive overview of Y-12's performance status and planned actions. B&W Y-12's Energy Management mission is to incorporate renewable energy and energy efficient technologies site-wide and to position Y-12 to meet NNSA energy requirement needs through 2025 and beyond. During FY 2011, the site formed a sustainability team (Fig. ES.1). The sustainability team provides a coordinated approach to meeting the various sustainability requirements and serves as a forum for increased communication and consistent implementation of sustainability activities at Y-12. The sustainability team serves as an information exchange mechanism to promote general awareness of sustainability information, while providing a system to document progress and to identify resources. These resources are necessary to implement activities that support the overall goals of sustainability, including reducing the use of resources and conserving energy. Additionally, the team's objectives include: (1) Foster a Y-12-wide philosophy to conserve resources; (2) Reduce the impacts of production operations in a cost-effective manner; (3) Increase materials recycling; (4) Use a minimum amount of energy and fuel; (5) Create a minimum of waste and pollution in achieving Y-12-strategic objectives; (6) Develop and implement techniques, technologies, process modifications, and programs that support sustainable acquisition; (7) Minimize the impacts to resources, including energy/fuel, water, waste, pesticides, and pollution generation; (8) Incorporate sustainable design principles into the design and construction of facility upgrades, new facilities, and infrastructure; and (9) Comply with federal and state regulations, executive orders, and DOE requirements. Y-12 is working to communicate its sustainment vision through procedural, engineering, operational, and management practices. The site will make informed decisions based on the application of the five Guiding Principles for HPSBs to the maximum extent possible.

Sherry, T. D.; Kohlhorst, D. P.; Little, S. K.

2011-12-01T23:59:59.000Z

362

Federal Energy Management Program: Determine Institutional Change  

NLE Websites -- All DOE Office Websites (Extended Search)

Determine Determine Institutional Change Sustainability Goals to someone by E-mail Share Federal Energy Management Program: Determine Institutional Change Sustainability Goals on Facebook Tweet about Federal Energy Management Program: Determine Institutional Change Sustainability Goals on Twitter Bookmark Federal Energy Management Program: Determine Institutional Change Sustainability Goals on Google Bookmark Federal Energy Management Program: Determine Institutional Change Sustainability Goals on Delicious Rank Federal Energy Management Program: Determine Institutional Change Sustainability Goals on Digg Find More places to share Federal Energy Management Program: Determine Institutional Change Sustainability Goals on AddThis.com... Sustainable Buildings & Campuses

363

Sustainability’s Correlation to Profit.  

E-Print Network (OSTI)

??Sustainability and its correlation to profits in hospitality institutions is the subject of this paper. The lack of knowledge about sustainability and the benefits of… (more)

Drummond, Cheryl Annissa

2011-01-01T23:59:59.000Z

364

The Integral Fast Reactor  

SciTech Connect

Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs.

Till, C.E.; Chang, Y.I. (Argonne National Lab., IL (USA)); Lineberry, M.J. (Argonne National Lab., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

365

Building Technologies Program | Clean Energy | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Office,Office of Weatherization and Intergovernmental Program, Policy and International Affairs, Concentrating Solar Power Program, Sustainability Performance Office, and...

366

Sustainability | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainability Sustainability Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration...

367

Enabling Materials Resource Sustainability  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... REWAS 2013: Enabling Materials Resource Sustainability: Enabling Sustainability through Education and Consumer Awareness Sponsored ...

368

Sustainable Manufacturing Briefing  

Science Conference Proceedings (OSTI)

... enhance their brands. • Is sustainability an opportunity or cost? There is no ... demonstrate, deploy, and accredit new sustainable manufacturing ...

2012-08-29T23:59:59.000Z

369

Evergreen Sustainable Development Standard for Affordable Housing |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Evergreen Sustainable Development Standard for Affordable Housing Evergreen Sustainable Development Standard for Affordable Housing Evergreen Sustainable Development Standard for Affordable Housing < Back Eligibility Low-Income Residential Savings Category Heating & Cooling Commercial Heating & Cooling Heating Home Weatherization Commercial Weatherization Sealing Your Home Cooling Appliances & Electronics Construction Design & Remodeling Ventilation Heat Pumps Commercial Lighting Lighting Water Heating Solar Buying & Making Electricity Program Info State District of Columbia Program Type Green Building Incentive Provider Housing Trust Fund The Washington State Department of Commerce created the Evergreen Sustainable Development Standard, a set of green building criteria that is required for any affordable housing project applying for state funds

370

Current status of the Run-Beyond-Cladding Breach (RBCB) tests for the Integral Fast Reactor (IFR). Metallic Fuels Program  

Science Conference Proceedings (OSTI)

This paper describes the results from the Integral Fast Reactor (IFR) metallic fuel Run-Beyond-Cladding-Breach (RBCB) experiments conducted in the Experimental Breeder Reactor II (EBR-II). Included in the report are scoping test results and the data collected from the prototypical tests as well as the exam results and discussion from a naturally occurring breach of one of the lead IFR fuel tests. All results showed a characteristic delayed neutron and fission gas release pattern that readily allows for identification and evaluation of cladding breach events. Also, cladding breaches are very small and do not propagate during extensive post breach operation. Loss of fuel from breached cladding was found to be insignificant. The paper will conclude with a brief description of future RBCB experiments planned for irradiation in EBR-II.

Batte, G.L.; Pahl, R.G. [Argonne National Lab., Idaho Falls, ID (United States); Hofman, G.L. [Argonne National Lab., IL (United States)

1993-09-01T23:59:59.000Z

371

Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors  

SciTech Connect

The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

2010-01-21T23:59:59.000Z

372

Light Water Reactor Sustainability Nondestructive Evaluation...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to the safety of LWR plants include the containment building, spent fuel pool, and cooling towers. This use has made its long-term performance crucial for the safe operation...

373

Proceedings of the 2000 International Conference on Fatigue of Reactor Components (MRP-46): PWR Materials Reliability Program (PWRMR P)  

Science Conference Proceedings (OSTI)

This report contains information presented at the First International Conference on Fatigue of Reactor Components held July 31 - August 2, 2000, in Napa, California. The conference -- sponsored by EPRI, the Organisation for Economic Co-operation and Development Nuclear Energy Agency/Committee on the Safety of Nuclear Installations (OECD NEA/CSNI), and the U.S. Nuclear Regulatory Commission (U.S. NRC) -- provided a forum for the technical discussion of fatigue issues that affect the integrity and operatio...

2001-06-25T23:59:59.000Z

374

Program on Technology Innovation: Technical Support for GE Economic Simplified Boiling Water Reactor (ESBWR)-Radwaste System Design  

Science Conference Proceedings (OSTI)

EPRI has undertaken a review of advanced nuclear plant (ANP) radioactive waste system designs. This work updates EPRI's Utility Requirements Document (URD) for the design of Advanced Light Water Reactor plants. The goal is to capture the radwaste elements that have led to the dramatic improvement in radioactive waste processing in terms of technology advances and improved operating strategy seen in today's operating U.S. plants. This work will form the basis for radioactive waste processing systems in th...

2006-11-21T23:59:59.000Z

375

Materials Reliability Program: Sensitivity Studies for Functionality Analysis of Reactor Internals of Westinghouse-Designed Power Plants (MRP-356)  

Science Conference Proceedings (OSTI)

In developing the Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Rev. 0), a semi-empirical material behavior model for irradiated austenitic stainless steels was developed for the degradation mechanisms applicable to the internals. Functionality analyses predicting aging up to 60 years were performed using the material model. MRP-230 results indicate that susceptibility to irradiation-assisted stress corrosion cracking (IASCC) is governed by two competing ...

2013-08-13T23:59:59.000Z

376

Materials Reliability Program: Inspection and Evaluation Guidelines for Reactor Vessel Bottom-Mounted Nozzles in U.S. PWR Plants (MR P-206)  

Science Conference Proceedings (OSTI)

This report presents inspection and evaluation guidelines for reactor vessel bottom-mounted nozzles in U.S. pressurized water reactor (PWR) plants.

2009-03-23T23:59:59.000Z

377

Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants  

SciTech Connect

The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters. The workshop was attended by 30 experts in materials, electrical engineering, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), NDE instrumentation development, universities, commercial NDE services and cable manufacturers, and Electric Power Research Institute (EPRI). The motivation for the R&D roadmap comes from the need to address the aging management of in-containment cables at nuclear power plants (NPPs).

Simmons, Kevin L.; Ramuhalli, Pradeep; Brenchley, David L.; Coble, Jamie B.; Hashemian, Hash; Konnik, Robert; Ray, Sheila

2012-09-14T23:59:59.000Z

378

Sustainable Electricity | Clean Energy | ORNL  

NLE Websites -- All DOE Office Websites (Extended Search)

Transportation Transportation Clean Energy Home | Science & Discovery | Clean Energy | Research Areas | Sustainable Electricity SHARE Sustainable Electricity Outdoor power line accelerated testing. Oak Ridge National Laboratory's Energy Efficiency and Electricity Technologies Program develops technologies to create a cleaner environment, a stronger economy, and a more secure future for our nation. The Program is committed to expanding energy resource options and to improving efficiency in every element of energy production and use, and to ensuring a reliable and secure grid that fully integrates central generation with distributed resources, manages power flows, facilitates recovery from disruptions to the energy supply, and meets the nation's need for increasing electric

379

Recent Progress in the NSTX/NSTX-U Lithium Program and Prospects for Reactor-Relevant Liquid-Lithium Based Divertor Development  

Science Conference Proceedings (OSTI)

Developing a reactor compatible divertor has been identified as a particularly challenging technology problem for magnetic confinement fusion. While tungsten has been identified as the most attractive solid divertor material, the NSTX/NSTX-U lithium (Li) program is investigating the viability of liquid lithium (LL) as a potential reactor compatible divertor plasma facing component (PFC) . In the near term, operation in NSTX-U is projected to provide reactor-like divertor heat loads heat load on the Liquid Lithium Divertor (LLD) was observed, attributable to enhanced divertor bolometric radiation. This reduced divertor heat flux through radiation observed in the NSTX LLD experiment is consistent with the results from other lithium experiments and calculations. These results motivate an LL-based closed radiative divertor concept proposed here for NSTX-U and fusion reactors. With an LL coating, the Li is evaporated from the divertor strike point surface due to the intense heat. The evaporated Li is readily ionized by the plasma due to its low ionization energies, and the ionized Li ions can radiate strongly, resulting in a significant reduction in the divertor heat flux. Due to the rapid plasma transport in divertor plasma, the radiation values can be significantly enhanced up to ~ 11 MJ/cc of LL. This radiative process has the desired function of spreading the focused divertor heat load to the entire divertor chamber facilitating the divertor heat removal. The LL divertor surface can also provide a "sacrificial" surface to protect the substrate solid material from transient high heat flux such as the ones caused by the ELMs. The closed radiative LLD concept has the advantages of providing some degree of partition in terms of plasma disruption forces on the LL, Li particle divertor retention, and strong divertor pumping action from the Li-coated divertor chamber wall. By operating at a lower temperature than the first wall, the LLD can serve to purify the entire reactor chamber, as impurities generally migrate toward lower temperature Li-condensed surfaces. To maintain the LL purity, a closed LL loop system with a modest capacity (e.g., ~ 1 Liter/sec for ~ 1% level "impurities") is envisioned for a steady-state 1 GW-electric class fusion power plant.

M. Ono, et al.

2012-10-27T23:59:59.000Z

380

Recent Progress in the NSTX/NSTX-U Lithium Program and Prospects for Reactor-Relevant Liquid-Lithium Based Divertor Development  

SciTech Connect

Developing a reactor compatible divertor has been identified as a particularly challenging technology problem for magnetic confinement fusion. While tungsten has been identified as the most attractive solid divertor material, the NSTX/NSTX-U lithium (Li) program is investigating the viability of liquid lithium (LL) as a potential reactor compatible divertor plasma facing component (PFC) . In the near term, operation in NSTX-U is projected to provide reactor-like divertor heat loads < 40 MW/m^2 for 5 s. During the most recent NSTX campaign, ~ 0.85 kg of Li was evaporated onto the NSTX PFCs where a ~50% reduction in heat load on the Liquid Lithium Divertor (LLD) was observed, attributable to enhanced divertor bolometric radiation. This reduced divertor heat flux through radiation observed in the NSTX LLD experiment is consistent with the results from other lithium experiments and calculations. These results motivate an LL-based closed radiative divertor concept proposed here for NSTX-U and fusion reactors. With an LL coating, the Li is evaporated from the divertor strike point surface due to the intense heat. The evaporated Li is readily ionized by the plasma due to its low ionization energies, and the ionized Li ions can radiate strongly, resulting in a significant reduction in the divertor heat flux. Due to the rapid plasma transport in divertor plasma, the radiation values can be significantly enhanced up to ~ 11 MJ/cc of LL. This radiative process has the desired function of spreading the focused divertor heat load to the entire divertor chamber facilitating the divertor heat removal. The LL divertor surface can also provide a "sacrificial" surface to protect the substrate solid material from transient high heat flux such as the ones caused by the ELMs. The closed radiative LLD concept has the advantages of providing some degree of partition in terms of plasma disruption forces on the LL, Li particle divertor retention, and strong divertor pumping action from the Li-coated divertor chamber wall. By operating at a lower temperature than the first wall, the LLD can serve to purify the entire reactor chamber, as impurities generally migrate toward lower temperature Li-condensed surfaces. To maintain the LL purity, a closed LL loop system with a modest capacity (e.g., ~ 1 Liter/sec for ~ 1% level "impurities") is envisioned for a steady-state 1 GW-electric class fusion power plant.

M. Ono, et al.

2012-10-27T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Materials Sustainability: Digital Resource Center -- Sustainability ...  

Science Conference Proceedings (OSTI)

FORUMS > SUSTAINABILITY: ECONOMICS, LIFECYCLE ANALYSIS, GREEN HOUSE GASES, AND CLIMATE CHANGE, Replies, Views, Originator, Last Post  ...

382

Princeton Plasma Physics Lab - Sustainability  

NLE Websites -- All DOE Office Websites (Extended Search)

sustainability Sustainability is a set sustainability Sustainability is a set of practices in business, government and at home aimed at minimizing humans' impact on the environment and cutting greenhouse gas emissions by reducing waste, recycling, composting, conserving natural parks and numerous other efforts. en Another Gold for PPPL: Laboratory Wins 2nd Gold GreenBuy Award http://www.pppl.gov/news/2013/09/another-gold-pppl-laboratory-wins-2nd-gold-greenbuy-award

PPPL has received a gold GreenBuy award from the U.S. Department of Energy for its green purchasing program in 2012 - winning the award for the second year.The Laboratory was only one of four laboratories

383

Gas reactor international cooperative program interim report: United States/Federal Republic of Germany nuclear licensing comparison  

SciTech Connect

In order to compare US and FRG Nuclear Licensing, a summary description of United States Nuclear Licensing is provided as a basis. This is followed by detailed information on the participants in the Nuclear Licensing process in the Federal Republic of Germany (FRG). FRG licensing procedures are described and the rules and regulations imposed are summarized. The status of gas reactor licensing in both the U.S. and the FRG is outlined and overall conclusions are drawn as to the major licensing differences. An appendix describes the most important technical differences between US and FRG criteria.

1978-09-01T23:59:59.000Z

384

Summary report on the HFED (High-Uranium-Loaded Fuel Element Development) miniplate irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program  

SciTech Connect

An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl/sub x/, UAl/sub 2/, U/sub 3/O/sub 8/, U/sub 3/SiAl, U/sub 3/Si, U/sub 3/Si/sub 1.5/, U/sub 3/Si/sub 2/, U/sub 3/SiCu, USi, U/sub 6/Fe, and U/sub 6/Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from /approximately/27 to 98 at. % /sup 235/U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.

Senn, R.L.

1989-04-01T23:59:59.000Z

385

Mechanical Testing of Core Fast Reactor Materials for the Advanced ...  

Science Conference Proceedings (OSTI)

To achieve this goal, the core fast reactor materials (cladding and duct) must be ... in situ Mechanical Test Methods in the US Fusion Reactor Materials Program.

386

Supporting Entrepreneurs for Sustainable Development (SEED) | Open Energy  

Open Energy Info (EERE)

Sustainable Development (SEED) Sustainable Development (SEED) Jump to: navigation, search Logo: Supporting Entrepreneurs for Sustainable Development (SEED) Name Supporting Entrepreneurs for Sustainable Development (SEED) Agency/Company /Organization United Nations Development Programme, United Nations Environment Programme Sector Energy, Land Focus Area Renewable Energy, Industry Topics Policies/deployment programs Website http://www.seedinit.org/ Program Start 2002 References SEED[1] "The SEED Initiative is a global partnership for action on sustainable development and the green economy. Founded by UNEP, UNDP and IUCN at the 2002 World Summit on Sustainable Development in Johannesburg, SEED supports innovative small-scale and locally driven entrepreneurships around the globe which integrate social

387

Federal Energy Management Program: Identify Institutional Change Rules for  

NLE Websites -- All DOE Office Websites (Extended Search)

Rules for Sustainability to someone by E-mail Rules for Sustainability to someone by E-mail Share Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on Facebook Tweet about Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on Twitter Bookmark Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on Google Bookmark Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on Delicious Rank Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on Digg Find More places to share Federal Energy Management Program: Identify Institutional Change Rules for Sustainability on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance

388

Federal Energy Management Program: Identify Institutional Change Roles for  

NLE Websites -- All DOE Office Websites (Extended Search)

Roles for Sustainability to someone by E-mail Roles for Sustainability to someone by E-mail Share Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on Facebook Tweet about Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on Twitter Bookmark Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on Google Bookmark Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on Delicious Rank Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on Digg Find More places to share Federal Energy Management Program: Identify Institutional Change Roles for Sustainability on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance

389

Federal Energy Management Program: Identify Institutional Change Tools for  

NLE Websites -- All DOE Office Websites (Extended Search)

Tools for Sustainability to someone by E-mail Tools for Sustainability to someone by E-mail Share Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on Facebook Tweet about Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on Twitter Bookmark Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on Google Bookmark Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on Delicious Rank Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on Digg Find More places to share Federal Energy Management Program: Identify Institutional Change Tools for Sustainability on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance

390

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

SciTech Connect

The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

Douglas Morrell

2011-03-01T23:59:59.000Z

391

ICLEI Sustainable Urban Energy Planning | Open Energy Information  

Open Energy Info (EERE)

ICLEI Sustainable Urban Energy Planning ICLEI Sustainable Urban Energy Planning Jump to: navigation, search Tool Summary LAUNCH TOOL Name: ICLEI Sustainable Urban Energy Planning Agency/Company /Organization: ICLEI - Local Governments for Sustainability Sector: Energy Focus Area: Renewable Energy, Energy Efficiency Topics: Background analysis, Implementation, Low emission development planning, Policies/deployment programs Website: www.iclei.org/ References: ICLEI Homepage [1] "ICLEI - Local Governments for Sustainability is an international association of local governments as well as national and regional local government organizations that have made a commitment to sustainable development."[1] Sustainable Urban Energy Planning: A handbook for cities and towns in developing countries

392

Sustainable Energy Fund (Metropolitan Edison) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Energy Fund (Metropolitan Edison) Sustainable Energy Fund (Metropolitan Edison) Sustainable Energy Fund (Metropolitan Edison) < Back Eligibility Commercial Industrial Local Government Nonprofit Schools Savings Category Bioenergy Commercial Heating & Cooling Manufacturing Buying & Making Electricity Alternative Fuel Vehicles Hydrogen & Fuel Cells Water Heating & Cooling Solar Heating Water Heating Wind Maximum Rebate Varies; $25,000 for some types of projects Program Info State Pennsylvania Program Type Local Grant Program Rebate Amount Varies according to project Provider Community Foundation of the Alleghenies FirstEnergy (formerly GPU) established the Metropolitan Edison Company Sustainable Energy Fund and the Penelec Sustainable Energy Fund in 2000. The Community Foundation for the Alleghenies in Johnstown, Pennsylvania

393

The Sustainability of Sustainable Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 S. Duclos 2010-11-30 Research Priorities for More Efficient Use of Critical Materials from a U.S. Corporate Perspective Trans-Atlantic Workshop on Rare Earth Elements and Other Critical Materials for a Clean Energy Future Steven Duclos Chief Scientist Manager, Material Sustainability GE Global Research Niskayuna, NY December 3, 2010 2 /4 S. Duclos 2010-11-30 GE Criticality Diagram Supply and Price Risk Impact on GE Lower Higher Lower Higher Proportional to spend Rare Earth Elements area Re 3 /4 S. Duclos 2010-11-30 OEM Technology Options in Addressing Metals Supply Challenges Sourcing Manufacturing Engineering/R&D Each element and each application will use a unique mix of options *Volume material buys *Diversification *Hedging *Global sourcing *Strategic inventory reserves

394

Lincoln Electric System (Commercial and Industrial) - Sustainable Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Commercial and Industrial) - Sustainable Commercial and Industrial) - Sustainable Energy Program Lincoln Electric System (Commercial and Industrial) - Sustainable Energy Program < Back Eligibility Commercial Industrial Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Manufacturing Home Weatherization Commercial Weatherization Sealing Your Home Ventilation Construction Heat Pumps Appliances & Electronics Commercial Lighting Lighting Maximum Rebate '''General Incentive Limits''' Commercial Industrial Lighting Retrofit: $100,000 per program year Commercial and Industrial Energy Efficiency: $100,000 per program year Program Info State Nebraska Program Type Utility Rebate Program Rebate Amount Commercial Industrial Lighting Retrofit Lighting Retrofit: $500/kW of peak-demand reduction

395

Program management plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

The primary mission of the Molten Salt Reactor Experiment (MSRE) Remediation Project is to effectively implement the risk-reduction strategies and technical plans to stabilize and prevent further migration of uranium within the MSRE facility, remove the uranium and fuel salts from the system, and dispose of the fuel and flush salts by storage in appropriate depositories to bring the facility to a surveillance and maintenance condition before decontamination and decommissioning. This Project Management Plan (PMP) for the MSRE Remediation Project details project purpose; technical objectives, milestones, and cost objectives; work plan; work breakdown structure (WBS); schedule; management organization and responsibilities; project management performance measurement planning, and control; conduct of operations; configuration management; environmental, safety, and health compliance; quality assurance; operational readiness reviews; and training.

NONE

1996-09-01T23:59:59.000Z

396

A unified analysis of the reactor neutrino program towards the measurement of the theta_13 mixing angle  

E-Print Network (OSTI)

We present in this article a detailed quantitative discussion of the measurement of the leptonic mixing angle theta_13 through currently scheduled reactor neutrino oscillation experiments. We thus focus on Double Chooz (Phase I & II), Daya Bay (Phase I & II) and RENO experiments. We perform a unified analysis, including systematics, backgrounds and accurate experimental setup in each case. Each identified systematic error and background impact has been assessed on experimental setups following published data when available and extrapolating from Double Chooz acquired knowledge otherwise. After reviewing the experiments, we present a new analysis of their sensitivities to sin^2(2 theta_13) and study the impact of the different systematics based on the pulls approach. Through this generic statistical analysis we discuss the advantages and drawbacks of each experimental setup.

Guillaume Mention; Thierry Lasserre; Dario Motta

2007-04-04T23:59:59.000Z

397

Advanced Reactor Technologies | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Advanced Reactor Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies Advanced Reactor Technologies The Office of Advanced Reactor Technologies (ART) sponsors research, development and deployment (RD&D) activities through its Next Generation Nuclear Plant (NGNP), Advanced Reactor Concepts (ARC), and Advanced Small Modular Reactor (aSMR) programs to promote safety, technical, economical, and environmental advancements of innovative Generation IV nuclear energy technologies. The Office of Nuclear Energy (NE) will pursue these advancements through RD&D activities at the Department of Energy (DOE) national laboratories and U.S. universities, as well as through collaboration with industry and international partners. These activities will focus on advancing scientific

398

Baldrige Program Business Plan Summary  

Science Conference Proceedings (OSTI)

... This summary describes the Baldrige Performance Excellence Program's transition from funding via federal appropriations to a self-sustaining ...

2013-02-14T23:59:59.000Z

399

H. R. 1001: A Bill to authorize appropriations for the Reduced Enrichment Research and Test Reactors Program of the Department of Energy. Introduced in the House of Representatives, One Hundred Third Congress, First Session, February 18, 1993  

SciTech Connect

This Act may be cited as the [open quotes]Bomb-Grade Uranium Export Substitution Act of 1993[close quotes]. The purpose of this Bill is to authorize appropriations for the Reduced Enrichment Research and Test Reactors Program of the Department of Energy. This document presents Congressional findings and a statement of authorization of appropriations.

1993-01-01T23:59:59.000Z

400

External > Programs > Supporting Activities > Diversity Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

ORO Diversity Programs & Employee Concerns Office Welcome The Oak Ridge Office is a recognized leader in developing and sustaining a high performing, diverse workforce. Reasonable...

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

SEM: enterprise modeling of JSF global sustainment  

Science Conference Proceedings (OSTI)

The Joint Strike Fighter (JSF) Program is implementing a paradigm shift to a performance-based logisties environment for force sustainment. This approach produces the necessary levels of performance at a significantly reduced cost of ownership. The resulting ...

V. Devon Smith; Donald G. Searles; Bruce M. Thompson; Robert M. Cranwell

2006-12-01T23:59:59.000Z

402

Federal Energy Management Program: Institutional Change Basics...  

NLE Websites -- All DOE Office Websites (Extended Search)

Basics for Sustainability to someone by E-mail Share Federal Energy Management Program: Institutional Change Basics for Sustainability on Facebook Tweet about Federal Energy...

403

Programming  

NLE Websites -- All DOE Office Websites (Extended Search)

Programming for Exascale Computers William Gropp and Marc Snir April 15, 2013 Abstract Exascale systems will present programmers with many challenges. We review the...

404

Mundaneum of sustainability.  

E-Print Network (OSTI)

??The Mundaneum of Sustainability focuses on influencing people's consciousness of sustainability in their daily lives, by creating a place where people senses are triggered through… (more)

De Ruijter, P.

2011-01-01T23:59:59.000Z

405

Sustainable Energy Systems Group  

NLE Websites -- All DOE Office Websites (Extended Search)

Sustainable Energy Systems Group The Sustainable Energy Systems Group studies the impacts of energy generation and use, manufacturing, and other activities on the environment, the...

406

2012 DOE Sustainability Awards  

NLE Websites -- All DOE Office Websites (Extended Search)

2012 DOE Sustainability Awards PSO Site Title EE National Renewable Energy Laboratory Comprehensive Energy Management EM Headquarters - EM Environmental Management's Sustainability...

407

M-1 N-Reactor fuel development. Excerpts from N-Reactor Department Research and Development Budget for FY-1967 and Revision of Budget for FY-1966  

SciTech Connect

The use of metallic uranium fuel elements on a large scale in a pressurized water cooled graphite moderated power reactor environment in N-Reactor not only represents an extrapolation from previous Hanford fuel technology but it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites. The major benefit to be achieved through an extensive and continuing fuel program is attainment of the full capabilities of the N-Reactor at much reduced fuel cycle costs. The current N-Reactor fuel design represents the best engineering judgment of what is required for adequate performance. While the design is intentionally conservative, some features may not fully provide the level of performance required to sustain efficient reactor operation. Results of production-scale irradiation experience and special test irradiations will provide direction to a continuing program to correct any excesses or deficiencies in the initial fuel design. Reduction of unwarranted conservatism in the design will lower fuel fabrication costs, and correction of deficiencies will lower irradiation costs through increased time operated efficiency. Costs of this program are summarized for 1965, 66, and 67. The paper describes the scope of the program, its relationship to other programs, and technical progress in FY-1965 which included improved performance of the fuel elements even with the large number of rapid shutdowns of the reactor.

1965-04-19T23:59:59.000Z

408

EERE: Federal Energy Management Program Home Page  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Map About the Program Program Plans, Implementation, and Results Interagency Coordination Interagency Energy Management Task Force Contacts Program Areas Sustainable Buildings...

409

FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Quarterly Progress Report for November 1, 1959 to January 31, 1960  

SciTech Connect

A variety of spherical uranium--graphite fuel elements for the Pebble Bed Reactor (PBR) was fabricated. Poor results with sintered alumina coated UO/ sub 2/ particles led to the development of slumina coating by vspor deposition, for which good results have been obtained. A variety of sub-surface metal, metal carbide, and ceramic coatings located between an unfueled graphite shell and the fueled core of a PBR fuel element was prepared and examined. Most of the materials and processes showed poor results. Excellent metal recoveries were achieved from the metal oxide--graphite system using the grind-leach technique of reprocessing. Test results on Si-- SiC coated fuel elements showed good fission product retention in neutron activation tests, a self-welding tendency between adjacent spheres at 2500 deg F surface temperature, and no evidence of failure when an interanl gas pressure of 300 psi was applied. Fission product release rates from a pyrolytic carbon coated specimen under low-level irradiation were obtained at 150 to 1900 deg F. The design of the in-pile loop to study the behavior of fission products escaping from PBR fuel elements wss established. (C.J.G.)

1960-10-31T23:59:59.000Z

410

Sustainably Priced Energy Enterprise Development (SPEED) Goals | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainably Priced Energy Enterprise Development (SPEED) Goals Sustainably Priced Energy Enterprise Development (SPEED) Goals Sustainably Priced Energy Enterprise Development (SPEED) Goals < Back Eligibility Investor-Owned Utility Municipal Utility Rural Electric Cooperative Savings Category Bioenergy Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Solar Heating & Cooling Water Heating Wind Program Info State Vermont Program Type Renewables Portfolio Standard Provider Vermont Public Service Board Vermont's Sustainably Priced Energy Enterprise Development (SPEED) Program was created by legislation in 2005 to promote renewable energy development. The SPEED program itself is not a renewable portfolio goal or standard. However, if the Vermont Public Service Board (PSB) determines that the

411

DuPont's Safety Model and Sustainability Initiatives | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Initiatives More Documents & Publications Sustainability Outreach Program Brochure Gosling, The Manhattan Project: Making the Atomic Bomb TheManhattanProject2010.pdf...

412

International Forum for Reactor Aging Management (IFRAM)  

SciTech Connect

The Nuclear Regulatory Commission has undertaken a program to lay the groundwork for defining proactive actions to manage degradation of materials in light water reactors (LWRs). This article discusses the international forum for reactor aging management.

Bond, Leonard J.

2010-11-01T23:59:59.000Z

413

Federal Energy Management Program: Institutional Change Principles for  

NLE Websites -- All DOE Office Websites (Extended Search)

Principles for Fostering Sustainability to someone by E-mail Principles for Fostering Sustainability to someone by E-mail Share Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on Facebook Tweet about Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on Twitter Bookmark Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on Google Bookmark Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on Delicious Rank Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on Digg Find More places to share Federal Energy Management Program: Institutional Change Principles for Fostering Sustainability on AddThis.com...

414

Federal Energy Management Program: Resources on Institutional Change for  

NLE Websites -- All DOE Office Websites (Extended Search)

Resources on Resources on Institutional Change for Sustainability to someone by E-mail Share Federal Energy Management Program: Resources on Institutional Change for Sustainability on Facebook Tweet about Federal Energy Management Program: Resources on Institutional Change for Sustainability on Twitter Bookmark Federal Energy Management Program: Resources on Institutional Change for Sustainability on Google Bookmark Federal Energy Management Program: Resources on Institutional Change for Sustainability on Delicious Rank Federal Energy Management Program: Resources on Institutional Change for Sustainability on Digg Find More places to share Federal Energy Management Program: Resources on Institutional Change for Sustainability on AddThis.com... Sustainable Buildings & Campuses

415

Technical Program  

Science Conference Proceedings (OSTI)

Mar 11, 2008 ... program (High Amperage and Low Energy) was a successful assets ...... structures, fusion reactors, and heat management systems due to their ...... intensity, which have migrated from process innovation research to enterprise.

416

SUSTAINABLE COMPOSITES: CELLULOSE NANOFIBERS  

Science Conference Proceedings (OSTI)

SUSTAINABLE COMPOSITES: CELLULOSE NANOFIBERS. Iulia Sacui and Jeffrey Gilman. Our main focus is on using cellulose ...

417

Sustainable warehouse management  

Science Conference Proceedings (OSTI)

Sustainable warehouse is about integrating, balancing and managing the economic, environmental and social inputs and outputs of the warehouse operations. Sustainability is a core value to many businesses but they find it hard to implement in their current ... Keywords: sustainability modelling, sustainable warehouse management, system dynamics

Kah-Shien Tan; M. Daud Ahmed; David Sundaram

2009-06-01T23:59:59.000Z

418

Perspective on the fusion-fission hybrid reactor  

SciTech Connect

The hybrid reactor's role as a source of fuel for fission converter reactors is investigated. The role of the hybrid reactor in the energy economy, the interface between the hybrid reactor and the present fusion program, implications of the Carter Energy Plan, and the rationale for further hybrid reactor studies are discussed.

Bender, D.J.; Lee, J.D.; Moir, R.W.

1977-10-01T23:59:59.000Z

419

Helping Wisconsin Small Businesses Increase Sustainability | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Wisconsin Small Businesses Increase Sustainability Wisconsin Small Businesses Increase Sustainability Helping Wisconsin Small Businesses Increase Sustainability June 28, 2012 - 3:51pm Addthis The Wisconsin Profitable Sustainability Initiative (PSI), an innovative, customizable and highly-effective program of the Wisconsin Manufacturing Extension Partnership (WMEP), demonstrates the range of economic, social and environmental benefits that can be realized by the state's small and midsize manufacturers through the implementation of sustainable business practices. Kristin Swineford Communication Specialist, Weatherization and Intergovernmental Programs What Does the Future Look Like? Electricity demand from these participants will be reduced by nearly 13 million kilowatt hours. 9,000 tons of solid waste will be diverted from landfills.

420

Hopi Sustainable Energy Plan  

SciTech Connect

The Hopi Tribal Government as part of an initiative to ?Regulate the delivery of energy and energy services to the Hopi Reservation and to create a strategic business plan for tribal provision of appropriate utility, both in a manner that improves the reliability and cost efficiency of such services,? established the Hopi Clean Air Partnership Project (HCAPP) to support the Tribe?s economic development goals, which is sensitive to the needs and ways of the Hopi people. The Department of Energy (DOE) funded, Formation of Hopi Sustainable Energy Program results are included in the Clean Air Partnership Report. One of the Hopi Tribe?s primary strategies to improving the reliability and cost efficiency of energy services on the Reservation and to creating alternative (to coal) economic development opportunities is to form and begin implementation of the Hopi Sustainable Energy Program. The Hopi Tribe through the implementation of this grant identified various economic opportunities available from renewable energy resources. However, in order to take advantage of those opportunities, capacity building of tribal staff is essential in order for the Tribe to develop and manage its renewable energy resources. As Arizona public utilities such as APS?s renewable energy portfolio increases the demand for renewable power will increase. The Hopi Tribe would be in a good position to provide a percentage of the power through wind energy. It is equally important that the Hopi Tribe begin a dialogue with APS and NTUA to purchase the 69Kv transmission on Hopi and begin looking into financing options to purchase the line.

Norman Honie, Jr.; Margie Schaff; Mark Hannifan

2004-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Overview of NE Research Programs  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NE Research Programs NE Research Programs Sue Lesica Office of Nuclear Energy U.S. Department of Energy July 31, 2013 2 R&D Budgets FY 2013 FY 2014 Congressional Request House Mark Senate Mark SMR Licensing Technical Support 62,999 70,000 110,000 70,000 Small Modular Reactor R&D 23,958 20,000 20,000 20,000 Next Generation Nuclear Plant 38,720 0 0 0 LWR Sustainability 24,218 21,500 21,500 21,500 Advanced Reactor Concepts 21,178 31,000 45,000 21,000 Reactor Concepts RD&D 108,075 72,500 86,500 62,500 Modeling and Simulation Hub 24,588 24,300 24,300 24,300 Crosscutting Technology Development 17,242 13,901 27,885 25,437 NEAMS 13,646 9,536 National Scientific Users Facility 14,563 14,563 14,563 14,563 Nuclear Energy Enabling Technologies 70,040 62,300 66,748 62,300

422

Sustainable Communities Leadership Academy (SCLA) | Open Energy Information  

Open Energy Info (EERE)

Leadership Academy (SCLA) Leadership Academy (SCLA) Jump to: navigation, search Logo: Sustainable Communities Leadership Academy (SCLA) Name Sustainable Communities Leadership Academy (SCLA) Agency/Company /Organization Institute for Sustainable Communities (ISC) Partner Smart Growth America, Housing and Urban Development (HUD) Sector Climate, Energy Focus Area Buildings, Economic Development, Energy Efficiency, Food Supply, Greenhouse Gas, Land Use, People and Policy, Transportation, Water Conservation Topics Adaptation, Finance, Implementation, Low emission development planning, Policies/deployment programs Program Start 2008 Program End 2015 Country Canada, United States Northern America, Northern America References Sustainable Communities Leadership Academy[1] Overview

423

Haiti-Caribbean Community (CARICOM) Sustainable Energy Roadmap and Strategy  

Open Energy Info (EERE)

Haiti-Caribbean Community (CARICOM) Sustainable Energy Roadmap and Strategy Haiti-Caribbean Community (CARICOM) Sustainable Energy Roadmap and Strategy Jump to: navigation, search Name Haiti-Caribbean Community (CARICOM) Sustainable Energy Roadmap and Strategy Agency/Company /Organization Inter-American Development Bank, World Watch Institute (WWI) Sector Climate, Energy Focus Area Renewable Energy, Economic Development, Energy Efficiency, Greenhouse Gas, Grid Assessment and Integration, Industry, People and Policy, Transportation Topics Background analysis, Baseline projection, Finance, GHG inventory, Implementation, Low emission development planning, -Roadmap, Market analysis, Policies/deployment programs, Resource assessment, Technology characterizations Program Start 2012 Program End 2012 Country Haiti Caribbean References CARICOM Sustainable Energy Roadmap and Strategy [1]

424

Sustainable Building Design Revolving Loan Fund | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Building Design Revolving Loan Fund Sustainable Building Design Revolving Loan Fund Sustainable Building Design Revolving Loan Fund < Back Eligibility State Government Savings Category Home Weatherization Commercial Weatherization Sealing Your Home Heating & Cooling Commercial Heating & Cooling Cooling Construction Design & Remodeling Other Windows, Doors, & Skylights Ventilation Heating Appliances & Electronics Commercial Lighting Lighting Water Heating Maximum Rebate 100% project financing Program Info Start Date 1/8/2010 State Arkansas Program Type State Loan Program Rebate Amount 100% project financing Provider Arkansas Energy Office The Sustainable Building Design Revolving Loan Fund (RLF) is funded by the American Recovery and Reinvestment Act of 2009 (ARRA). The Arkansas Energy

425

Voluntary Agreements for Energy Efficiency or GHG Emissions Reduction in Industry: An Assessment of Programs Around the World  

E-Print Network (OSTI)

Final Report. Dublin: Sustainable Energy Ireland. Buttermanpotential for sustainable energy-efficiency investments,Foundation’s China Sustainable Energy Program for providing

Price, Lynn

2005-01-01T23:59:59.000Z

426

Materials Reliability Program: Evaluation of the Reactor Vessel Beltline Shell Forgings of Operating U.S. PWRs for Quasi-Laminar Indications (MRP-367)  

Science Conference Proceedings (OSTI)

In 2012, quasi-laminar indications were discovered in the beltline ring forgings of two Belgian pressurized water reactors (PWRs) during ultrasonic inspection (UT). This report assesses the implications of that discovery for U.S. reactor pressure vessels.BackgroundThe Doel 3 PWR has been operating in Belgium since 1982, Tihange 2 PWR since 1983. In 2012, UT of the ring forgings that constitute the cylindrical shells of the reactor pressure vessels (RPVs) ...

2013-11-14T23:59:59.000Z

427

Operation of a steam hydro-gasifier in a fluidized bed reactor  

E-Print Network (OSTI)

Using Self-Sustained Hydro- Gasification." [0011] In aprocess, using a steam hydro-gasification reactor (SHR) thepyrolysis and hydro-gasification in a single step. This

Park, Chan Seung; Norbeck, Joseph N.

2008-01-01T23:59:59.000Z

428

Sustainable Energy Trust Fund | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Sustainable Energy Trust Fund Sustainable Energy Trust Fund Sustainable Energy Trust Fund < Back Eligibility Commercial General Public/Consumer Industrial Institutional Residential Utility Savings Category Bioenergy Buying & Making Electricity Solar Heating & Cooling Commercial Heating & Cooling Heating Water Heating Wind Program Info State District of Columbia Program Type Public Benefits Fund Provider Energy Division The District of Columbia's Retail Electric Competition and Consumer Protection Act of 1999 required the DC Public Service Commission (PSC) to establish a public benefits fund to provide energy assistance to low-income residents, and to support energy-efficiency programs and renewable-energy programs. This fund, known as the Reliable Energy Trust Fund (RETF), took effect in 2001. In October 2008, the District of Columbia enacted the Clean

429

NUCLEAR REACTOR  

DOE Patents (OSTI)

A boiling-water nuclear reactor is described wherein control is effected by varying the moderator-to-fuel ratio in the reactor core. This is accomplished by providing control tubes containing a liquid control moderator in the reactor core and providing means for varying the amount of control moderatcr within the control tubes.

Treshow, M.

1961-09-01T23:59:59.000Z

430

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A reactor in which at least a portion of the moderator is in the form of movable refractory balls is described. In addition to their moderating capacity, these balls may serve as carriers for fissionable material or fertile material, or may serve in a coolant capacity to remove heat from the reactor. A pneumatic system is used to circulate the balls through the reactor.

Daniels, F.

1959-10-27T23:59:59.000Z

431

Corporate sustainability assessment methodology  

E-Print Network (OSTI)

Sustainability is a vague concept specifically in the context of a corporate world. There are numerous definitions for corporate sustainability and just as many ways of evaluating it. This work attempts to define, structure ...

Pinchuk, Natallia

2011-01-01T23:59:59.000Z

432

Material Reliability Program Technical Basis Document Concerning Irradiation-Induced Stress Relaxation and Void Swelling in Pressuri zed Water Reactor Vessel Internals Components (MRP-50)  

Science Conference Proceedings (OSTI)

Irradiation-induced swelling and irradiation-enhanced stress relaxation are two potential degradation mechanisms that could affect reactor vessel (RV) core internals components in pressurized water reactors (PWRs). This report describes current knowledge of these two potential degradation mechanisms, available relevant data and known functional relationships, and a qualitative assessment of these two mechanisms' combined and separate effects on PWR internals components.

2001-10-18T23:59:59.000Z

433

Earth System Analysis for Sustainability  

E-Print Network (OSTI)

Earth System Analysis for Sustainability By Hans JoachimSystem Analysis for Sustainability. MIT Press, Cambridge,the factors shaping sustainability yet undertaken and makes

Hamilton-Smith, Elery

2005-01-01T23:59:59.000Z

434

Sustainable Energy: Choosing Among Options  

E-Print Network (OSTI)

Review: Sustainable Energy: Choosing Among Options Byand William A. Peters. Sustainable Energy: Choosing AmongAll the authors of Sustainable Energy are associated with

Mirza, Umar Karim

2006-01-01T23:59:59.000Z

435

Bioenergy Technologies Office: Sustainability  

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

Overview Financial Opportunities Publications Contact Us Sustainability The Bioenergy Technologies Office's activities are guided by a commitment to environmental, economic,...

436

Small Business Programs  

National Nuclear Security Administration (NNSA)

Business At A Time NNSA is responsible for the management and security of the nation's nuclear weapons, nuclear nonproliferation, and naval reactor programs. It also responds to...

437

Rewarding Green: NETL Recognized for Sustainable Buildings | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Rewarding Green: NETL Recognized for Sustainable Buildings Rewarding Green: NETL Recognized for Sustainable Buildings Rewarding Green: NETL Recognized for Sustainable Buildings November 14, 2013 - 8:26am Addthis DOEñ€™s recognition program for high-performance sustainable buildings acknowledges buildings like B39 and promotes adherence to the guiding principles in all new DOE construction, renovations, and building alterations. The Sustainability Performance Office strives to ensure that, per Executive Order 13514, at least 15 percent of DOE buildings meet the requirements of the guiding principles by 2015, improving building sustainability on a national scale. DOE's recognition program for high-performance sustainable buildings acknowledges buildings like B39 and promotes adherence to the guiding principles in all new DOE construction, renovations, and building

438

CONVECTION REACTOR  

DOE Patents (OSTI)

An homogeneous nuclear power reactor utilizing convection circulation of the liquid fuel is proposed. The reactor has an internal heat exchanger looated in the same pressure vessel as the critical assembly, thereby eliminating necessity for handling the hot liquid fuel outside the reactor pressure vessel during normal operation. The liquid fuel used in this reactor eliminates the necessity for extensive radiolytic gas rocombination apparatus, and the reactor is resiliently pressurized and, without any movable mechanical apparatus, automatically regulates itself to the condition of criticality during moderate variations in temperature snd pressure and shuts itself down as the pressure exceeds a predetermined safe operating value.

Hammond, R.P.; King, L.D.P.

1960-03-22T23:59:59.000Z

439

Characterization and explanation of the sustainability of the European wood manufacturing industries: A quantitative approach  

Science Conference Proceedings (OSTI)

This paper has a twofold purpose. First, to characterize the sustainability of the European wood manufacturing industry. In this way, a ranking of the European countries analyzed in terms of sustainability is established. To undertake this task the sustainability ... Keywords: Econometric models, Goal programming, Indicators, Sustainability, Wood manufacturing industry

Roberto Voces; Luis Diaz-Balteiro; Carlos Romero

2012-06-01T23:59:59.000Z

440

Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program  

E-Print Network (OSTI)

Simulations for two series of anticipated transients phics. without scram (ATWS) events have been carried out for a small, hypothetical, research reactor based on the High Flux Australian Reador HIFAR using the RELAPS/MOD3.Z computer program. The first series simulated the ATWS events associated with pump transients and the second series simulated the ATWS events associated with heat exchanger transients. In the first series, two cases were simulated: (1) the non-availability of one of the two primary pumps and (2) the non-availability of one pump and 50 % operation of the other pimp. In the second series, three cases were simulated: (1) the non-availability of one of the three heat enchanters (2) the non-availability of two of the three heat enchanters and (3) the non-availability of all the three heat enchanters. To carry out the above simulations, modifications were incorporated to the critical heat flux (CHF) correlations of the RELAP program to account for the annular geometry of the fuel elements. The results of the simulated plump transients indicated that the mass flow rate would decrease to 270 Kg/s in the first transient and to 133 Kg/s in transient 2. The maximum rise in the coolant temperatures in the primly circuit would be 50C and the maximum rise in the central fuel element temperature would be 23[]C. The results of the first two cases of the heat exchanger transients indicated that the maximum rise in the coolant temperatures in the primary circuit would be 18.5[]C and the maximum rise in the central fuel element temperature would be 6[]C. However, during the simulation of the non-availability of all the three heat enchanters, primary coolant temperature started increasing rapidly. Void generation occurred in the central fuel element annuli at 408.5 seconds into the transient with saturation conditions being attained in the annulus. The phase change resulted in the expulsion of fluid from the annulus. Consequently, temperature in the second fuel ring exceeded 800K, resulting in its failure.

Hari, Sridhar

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor sustainability program" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Environmental Management Education Program: Building Environmental Stewardship  

SciTech Connect

The BES program enhanced the capability to integrate environmental sustainability concepts and social justice into multi-dimensional curricula.

Chulock, Hilary N.

2004-01-14T23:59:59.000Z

442

Program  

Office of Scientific and Technical Information (OSTI)

Extremophiles 2004 Extremophiles 2004 5th International Conference on Extremophiles SEPTEMBER 19 -23, 2004 CAMBRIDGE, MARYLAND Extremophiles 2004 5th International Conference on Extremophiles © 2004, American Society for Microbiology 1752 N Street, N.W. Washington, DC 20036-2904 Phone: 202-737-3600 World Wide Web: www.asm.org All Rights Reserved Printed in the United States of America ISBN: 1-55581 324-0 TABLE OF CONTENTS General Information Scientific Program Abstracts for Oral Sessions Abstracts for Poster Sessions Index 4 10 18 42 144 4 ASM Conferences EXECUTIVE COMMITTEE Frank Robb, Chair University of Maryland Biotechnology Institute Michael W. Adams University of Georgia Koki Horikoshi Japan Agency for Marine-Earth Science and Technology Robert M. Kelly North Carolina State University Jennifer Littlechild

443

Copy of Lake Worth Utilities - Energy Conservation Rebate Program...  

Open Energy Info (EERE)

Website http:www.coj.netDepartmentsEnvironmental+and+ComplianceOffice+of+SustainabilitySustainable+Building+Program.htm Date added to DSIRE 2010-11-05 Last DSIRE Review...

444

NREL: Sustainable NREL - About  

NLE Websites -- All DOE Office Websites (Extended Search)

About Sustainable NREL About Sustainable NREL NR EL proactively pursues sustainability in all its operations to meet the lab's environmental stewardship goals. NREL is also charged with providing leadership within the U.S. Department of Energy (DOE) complex to achieve energy and environmental goals as described in DOE Executive Order 13423 and Executive Order 13514. Sustainability Integrated in Mission and Operation Fully integrated in the lab's mission and operations, sustainability leadership is demonstrated by our involvement in optimizing resources, reducing waste, reducing greenhouse gas emissions, protecting the environment, and reaching out to the community. NREL Sustainability Efforts In addition to implementing on-site energy efficiency and renewable energy technologies, NREL has rigorous sustainability policies that facilitate:

445

NREL: Sustainable NREL Home Page  

NLE Websites -- All DOE Office Websites (Extended Search)

and renewable energy technologies. NREL's sustainability model can be replicated by homeowners, universities, industry, and government agencies. At NREL, sustainability...

446

Strategies for Sustainable Institute Operations  

Science Conference Proceedings (OSTI)

... 2 ? What we heard and read: ? NNMI RFI Responses to sustainability questions ... Blueprint for Action: Sustainable Operations Outline Page 3. ...

2013-01-23T23:59:59.000Z

447

City of San Diego - Sustainable Building Policy | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

San Diego - Sustainable Building Policy San Diego - Sustainable Building Policy City of San Diego - Sustainable Building Policy < Back Eligibility Commercial Construction Local Government Residential Savings Category Heating & Cooling Commercial Heating & Cooling Cooling Home Weatherization Construction Commercial Weatherization Design & Remodeling Appliances & Electronics Heat Pumps Commercial Lighting Lighting Water Heating Bioenergy Solar Windows, Doors, & Skylights Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Heating Wind Program Info State California Program Type Energy Standards for Public Buildings Provider San Diego Environmental Services Department The City of San Diego's Sustainable Building Policy is directed by Council Policy 900-14. The policy contains regulations regarding building

448

Materials Reliability Program: Loading Effects on the Low-Temperature Crack Propagation Phenomenon in 182 Weld Metal in a Pressurize d Water Reactor Environment (MRP-285)  

Science Conference Proceedings (OSTI)

This report summarizes results of a study of loading effects on the low-temperature crack propagation (LTCP) phenomenon in 182 weld metal in a pressurized water reactor (PWR) environment.

2010-12-20T23:59:59.000Z

449

Cuba: Energy, Sustainability and Independence  

NLE Websites -- All DOE Office Websites (Extended Search)

Cuba: Energy, Sustainability and Independence Cuba: Energy, Sustainability and Independence Speaker(s): Victor Bruno Henriquez Perez Date: May 10, 2001 - 12:00pm Location: b Seminar Host/Point of Contact: Kristina LaCommare Cubasolar (http://www.cubasolar.cu) is Cuba's NGO of over 400 scientists researching and implementing projects in energy efficiency and conservation as well as renewable energy. This year Cubasolar wil receive a Global 500 award from the United Nations Environmental Program for its work in raising energy consciousness in Cuba and other nations of the developing world. Since its founding in 1994, Cubasolar has installed solar panels on over 300 family doctor clinics in rural Cuba and is in the process of installing 1800 panels in rural elementary schools. Cubasolar is also involved in

450

Alliance for Sustainable Energy, LLC  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

27, 2013 27, 2013 Dr. Dan Arvizu, President Alliance for Sustainable Energy, LLC National Renewable Energy Laboratory 15013 Denver West Parkway Golden, Colorado 80401 WEL-2013-04 Dear Dr. Arvizu: The Office of Health, Safety and Security's Office of Enforcement and Oversight evaluated a drum rupture and flash event that occurred on February 8, 2013, at the National Renewable Energy Laboratory (NREL) Thermochemical User Facility (TCUF). Alliance for Sustainable Energy, LLC (Alliance) manages and operates NREL under a contract with the Department of Energy (DOE) and is subject to the provisions of DOE's Worker Safety and Health Program rule (10 C.F.R. Part 851). The Office of Enforcement and Oversight is issuing this enforcement

451

NEUTRONIC REACTOR  

DOE Patents (OSTI)

A neutronic reactor in which neutron moderation is achieved primarily in its reflector is described. The reactor structure consists of a cylindrical central "island" of moderator and a spherical moderating reflector spaced therefrom, thereby providing an annular space. An essentially unmoderated liquid fuel is continuously passed through the annular space and undergoes fission while contained therein. The reactor, because of its small size, is particularly adapted for propulsion uses, including the propulsion of aircraft. (AEC)

Fraas, A.P.; Mills, C.B.

1961-11-21T23:59:59.000Z

452

REACTOR COOLING  

DOE Patents (OSTI)

A nuclear reactor with provisions for selectively cooling the fuel elements is described. The reactor has a plurality of tubes extending throughout. Cylindrical fuel elements are disposed within the tubes and the coolant flows through the tubes and around the fuel elements. The fuel elements within the central portion of the reactor are provided with roughened surfaces of material. The fuel elements in the end portions of the tubes within the reactor are provlded with low conduction jackets and the fuel elements in the region between the central portion and the end portions are provided with smooth surfaces of high heat conduction material.

Quackenbush, C.F.

1959-09-29T23:59:59.000Z

453

Final safeguards analysis, High Temperature Lattice Test Reactor  

SciTech Connect

Information on the HTLTR Reactor is presented concerning: reactor site; reactor buildings; reactor kinetics and design characteristics; experimental and test facilitles; instrumentation and control; maintenance and modification; initial tests and operations; administration and procedural safeguards; accident analysis; seifterminated excursions; main heat exchanger leak; training program outline; and reliability analysis of safety systems. (7 references) (DCC)

Hanthorn, H.E.; Brown, W.W.; Clark, R.G.; Heineman, R.E.; Humes, R.M.

1966-01-01T23:59:59.000Z

454

Multi-Scale, Sustainable Reaction Engineering - A New Departmental Initiative  

E-Print Network (OSTI)

but it remains a continuing strength for the Department, underpinned by many new developments Illustration by Current/ Future Research Reactor and Reaction Efficiency Sustainable Energy Generation Transport Biofuels Modelling Reactor and Reaction... from Biomass via Iron Oxide Looping Dennis & Scott (2006). A.I.Ch.E.J., 52, 3325-3328. EPSRC Grant EP/F027435/1. Transport Biofuels Biomass Conversion to Fuel - Issues Options (i) gasification/GTL (ii) hydrolysis/fermentation Need...

Dennis, John

2008-07-29T23:59:59.000Z

455

Renewables for sustainable village power  

DOE Green Energy (OSTI)

It is estimated that two billion people live without electricity and its services. In addition, there is a sizeable number of rural villages that have limited electrical service, with either part-day operation by diesel gen-sets or partial electrification (local school or community center and several nearby houses). For many villages connected to the grid, power is often sporadically available and of poor quality. The U.S. National Renewable Energy Laboratory (NREL) in Golden, Colorado, has initiated a program to address these potential electricity opportunities in rural villages through the application of renewable energy (RE) technologies. The objective of this program is to develop and implement applications that demonstrate the technical performance, economic competitiveness, operational viability, and environmental benefits of renewable rural electric solutions, compared to the conventional options of line extension and isolated diesel mini-grids. These four attributes foster sustainability; therefore, the program is entitled Renewables for Sustainable Village Power (RSVP). The RSVP program is a multi-technology, multi-application program composed of six activities, including village applications development, computer model development, systems analysis, pilot project development, technical assistance, and Internet-based village power project data base. While the current program emphasizes wind, photovoltaics (PV), and their hybrids with diesel gen-sets, micro-hydro and micro-biomass technologies may be integrated in the future. NREL`s RSVP team is currently involved in rural electricity projects in thirteen countries, with U.S., foreign, and internationally based agencies and institutions. The integration of the technology developments, institutional experiences, and the financial solutions for the implementation of renewables in the main line rural electrification processes in both the developing world and remote regions of the developed world is the goal.

Flowers, L.

1997-03-01T23:59:59.000Z

456

FUNDAMENTALS IN THE OPERATION OF NUCLEAR TEST REACTORS. VOLUME 1. REACTOR SCIENCE AND TECHNOLOGY  

SciTech Connect

A resume of nuclear physics basic to reactor operation precedes discussion of aspects of reactor physics, engineering, chemistry, metallurgy, instrumentation, control, kinetics, and safety. The object is to provide an approach to and understanding of problems in irradiation test programs in the Materials Testing and Engineering Test Reactors. (D.C.W.)

1963-06-01T23:59:59.000Z

457

Update Sustainable Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

on the significant impacts and breadth of transportation science research at ORNL and new directions to achieve efficient, clean, and sustainable mobility. Ron's talk attracted...

458

NREL: Sustainable NREL - News  

NLE Websites -- All DOE Office Websites (Extended Search)

News Below are news stories related to NREL's sustainability efforts. September 3, 2013 Architects and Building Engineers Flock to NREL National ASHRAE and AIA conferences in...

459

Toward a sustainable UGA.  

E-Print Network (OSTI)

??Sustainability of the college campus is a growing trend and complex pursuit. While The University of Georgia is making strides in several areas of campus… (more)

Kirsche, Kevin Michael

2008-01-01T23:59:59.000Z

460