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1

Secretary Chu Statement on AP1000 Reactor Design Certification | Department  

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

Secretary Chu Statement on AP1000 Reactor Design Certification Secretary Chu Statement on AP1000 Reactor Design Certification Secretary Chu Statement on AP1000 Reactor Design Certification December 22, 2011 - 3:25pm Addthis Washington, D.C. - U.S. Energy Secretary Steven Chu issued the following statement today in support of the Nuclear Regulatory Commission's (NRC) decision to certify Westinghouse Electric's AP1000 nuclear reactor design, a significant step towards constructing a new generation of U.S. nuclear reactors. In February 2010, the Obama Administration announced the offer of a conditional commitment for a $8.33 billion loan guarantee for the construction and operation of two AP1000 reactors at Alvin W. Vogtle Electric Generation Plant in Burke, Georgia. "The Administration and the Energy Department are committed to restarting

2

Advanced light water reactor plants System 80+{trademark} design certification program. Annual progress report, October 1, 1994--September 30, 1995  

SciTech Connect (OSTI)

The purpose of this report is to provide the status of the progress that was made towards Design Certification of System 80+{trademark} during the US government`s 1995 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.

NONE

1998-09-01T23:59:59.000Z

3

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

SciTech Connect (OSTI)

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

4

Use of phenomena identification and ranking (PIRT) process in research related to design certification of the AP600 advanced passive light water reactor (LWR)  

SciTech Connect (OSTI)

The AP600 LWR is a new advanced passive design that has been submitted to the USNRC for design certification. Within the certification process the USNRC will perform selected system thermal hydraulic response audit studies to help confirm parts of the vendor`s safety analysis submittal. Because of certain innovative design features of the safety systems, new experimental data and related advances in the system thermal hydraulic analysis computer code are being developed by the USNRC. The PIRT process is being used to focus the experimental and analytical work to obtain a sufficient and cost effective research effort. The objective of this paper is to describe the application and most significant results of the PIRT process, including several innovative features needed in the application to accommodate the short design certification schedule. The short design certification schedule has required that many aspects of the USNRC experimental and analytical research be performed in parallel, rather than in series as was normal for currently operating LWRS. This has required development and use of management techniques that focus and integrate the various diverse parts of the research. The original PIRTs were based on inexact knowledge of an evolving reactor design, and concentrated on the new passive features of the design. Subsequently, the PIRTs have evolved in two more stages as the design became more firm and experimental and analytical data became available. A fourth and final stage is planned and in progress to complete the PIRT development. The PIRTs existing at the end of each development stage have been used to guide the experimental program, scaling analyses and code development supporting the audit studies.

Wilson, G.E.; Fletcher, C.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Eltawila, F. [Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research

1996-07-01T23:59:59.000Z

5

Remedial Action Certification Docket - Sodium Reactor Experiment (SRE)  

Office of Legacy Management (LM)

c~-?i-- c~-?i-- I ,3-l Remedial Action Certification Docket - Sodium Reactor Experiment (SRE) .Complex and the Hot Cave Facility (Bldg. 003), Santa Susana ,Fie!d Laboratory, Chatsworth, California ..:'..~::Yerlette Gatl in, MA-232 I am attaching for entry into the Public Document Room, one copy of the N -23 subject documentat ion. These documents are the backup data for the certification that the facilfties are radiologically acceptable for b- unrestricted use as noted in the certification statement published in the &aney Federal Register. Inasmuch as the certification for unrestricted use is 9/2(/85 being published in the Federal Register, it is prudent that the attached documentation also be available to the public. These documents should be retained In accordance with DOE Order 1324.2--disposal schedule 25.

6

Thermionic Reactor Design Studies  

SciTech Connect (OSTI)

Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

Schock, Alfred

1994-08-01T23:59:59.000Z

7

Thermionic Reactor Design Studies  

SciTech Connect (OSTI)

During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic losses in the electrodes of full-core-height diodes. Moreover, placing the fuel on the outside of the diode makes possible reactors with much higher fuel volume fractions, which enable power-flattened fast reactors scalable to very low power levels without the need for life-limiting hydride moderators or the use of efficiency-limiting driver fuel. In addition, with the fuel on the outside its swelling does not increase the emitter diameter or reduce the interelectrode gap. This should permit long lifetimes even with closer spacings, which can significantly improve the system efficiences. This was confirmed by coupled neutronic, thermal, thermionic, and electrical system analyses - some of which are presented in this paper - and by subsequent experiments. A companion paper presented next describes the fabrication and testing of full-scale converter elements, both fueled and unfueled, and summarizes the test results obtained. There is a duplicate copy in the file.

Schock, Alfred

1994-06-01T23:59:59.000Z

8

Nuclear Reactor Safety Design Criteria  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

1993-01-19T23:59:59.000Z

9

Evaluation of the economic simplified boiling water reactor human reliability analysis using the SHARP framework .  

E-Print Network [OSTI]

??General Electric plans to complete a design certification document for the Economic Simplified Boiling Water Reactor to have the new reactor design certified by the… (more)

Dawson, Phillip Eng

2007-01-01T23:59:59.000Z

10

System 80+{trademark} Standard Design: CESSAR design certification. Volume 3: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This report, Volume 3, in conjunction with Volume 2, provides the design of structures, components, equipment and systems.

Not Available

1990-12-21T23:59:59.000Z

11

System 80+{trademark} Standard Design: CESSAR design certification. Volume 2: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This report, Volume 2, in conjunction with Volume 3, provides the design of structures, components, equipment and systems.

Not Available

1990-12-21T23:59:59.000Z

12

System 80+{trademark} Standard Design: CESSAR design certification. Volume 11: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80{sup +}{trademark} Standard Design. This volume 11 discusses Radiation Protection, Conduct of Operations, and the Initial Test Program.

Not Available

1990-12-21T23:59:59.000Z

13

System 80+{trademark} Standard Design: CESSAR design certification. Volume 17: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describes the Combustion Engineering, Inc. System 80+{trademark} Standard Design. This Volume 17 provides Appendix A of this report, closure of unresolved and Genetic Safety Issues.

Not Available

1990-12-21T23:59:59.000Z

14

System 80+{trademark} Standard Design: CESSAR design certification. Volume 1: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These Volumes, describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This document, Volume 1, provides an introduction and general description of plant and site envelope characteristics.

Not Available

1990-12-21T23:59:59.000Z

15

System 80+{trademark} Standard Design: CESSAR design certification. Volume 8: Amendment I  

SciTech Connect (OSTI)

This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80{sup +}{trademark} Standard Design. This volume 8 provides a description of instrumentation and controls.

Not Available

1990-12-21T23:59:59.000Z

16

NRC review of the CANDU-3 reactor design  

SciTech Connect (OSTI)

This paper presents an overview of the US Nuclear Regulatory Commission's (NRC's) effort to complete an early review of the Canada deuterium uranium (CANDU)-3 reactor design prior to formal submittal of an application for standard design certification. The NRC is conducting a review of the CANDU-3 design in support of a request by AECL Technologics, the US sponsor of the design. The purpose of this review is to encourage early interactions by applicants, vendors, and government agencies with the NRC. The CANDU-3 design is being developed by Atomic Energy of Canada, Limited (AECL), whose CANDU operations are based in Mississauga, Ontario. AECL Technologies, a US subsidiary of AECL, Incorporated, informed the NRC of its intent to seek design certification of the CANDU-3 design under the provisions of 10CFR52 in a letter to the NRC dated May 25, 1989. This paper describes the commission's basis for this type of early review, its purposes and objectives, key elements of the review, the intended product, and the schedule.

Kennedy, J.L. (Nuclear Regulatory Commission, Washington, DC (United States))

1993-01-01T23:59:59.000Z

17

13 - Generation IV reactor designs, operation and fuel cycle  

Science Journals Connector (OSTI)

Abstract: This chapter looks at Generation IV nuclear reactors, such as the very high-temperature reactor (VHTR), the supercritical water reactor (SCWR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the lead-cooled fast reactor (LFR) and the gas-cooled fast reactor (GFR). Reactor designs and fuel cycles are also described.

N. Cerullo; G. Lomonaco

2012-01-01T23:59:59.000Z

18

Ordered bed modular reactor design proposal  

SciTech Connect (OSTI)

The Ordered Bed Modular Reactor (OBMR) is a design as an advanced modular HTGR in which the annular reactor core is filled with an ordered bed of fuel spheres. This arrangement allows fuel elements to be poured into the core cavity which is shaped so that an ordered bed is formed and to be discharged from the core through the opening holes in the reactor top. These operations can be performed in a shutdown shorter time. The OBMR has the most of advantages from both the pebble bed reactor and block type reactor. Its core has great structural flexibility and stability, which allow increasing reactor output power and outlet gas temperature as well as decreasing core pressure drop. This paper introduces ordered packing bed characteristics, unloading and loading technique of the fuel spheres and predicted design features of the OBMR. (authors)

Tian, J. [Inst. of Nuclear Energy Technology, Tsinghua Univ., Beijing 100084 (China)

2006-07-01T23:59:59.000Z

19

W. Alexander Williams, Ph.D Designation and Certification Manager  

Office of Legacy Management (LM)

March 20, 1995 March 20, 1995 W. Alexander Williams, Ph.D Designation and Certification Manager EM-421 Quince Orchard U.S. Department of Energy Washington, DC 20585-0002 L -=kj SUBJECT: FINAL REPORT-RADIOLOGICAL SURVEY OF THE F AMERICAN MANUFACTURING COMPANY OF TEXA WORTH, TEXAS I ,d Sl I lRMER , FORT Dear Dr. Williams: The Environmental,Survey and Site Assessment Program (ESSAP) of the C for Science and Education (ORISE) conducted radiological survey activii American Manufacturing Company of Texas Site in Fort Worth, Texas October 3 through 5, 1994. The survey activities consisted of document revi surface activity measurements, smears for removable activity, exposure rate m soil and miscellaneous sampling. k Ridge Institute :s at the former wing the period

20

Generic small modular reactor plant design.  

SciTech Connect (OSTI)

This report gives an overview of expected design characteristics, concepts, and procedures for small modular reactors. The purpose of this report is to provide those who are interested in reducing the cost and improving the safety of advanced nuclear power plants with a generic design that possesses enough detail in a non-sensitive manner to give merit to their conclusions. The report is focused on light water reactor technology, but does add details on what could be different in a more advanced design (see Appendix). Numerous reactor and facility concepts were used for inspiration (documented in the bibliography). The final design described here is conceptual and does not reflect any proposed concept or sub-systems, thus any details given here are only relevant within this report. This report does not include any design or engineering calculations.

Lewis, Tom Goslee,; Cipiti, Benjamin B.; Jordan, Sabina Erteza; Baum, Gregory A.

2012-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Mirror Advanced Reactor Study interim design report  

SciTech Connect (OSTI)

The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design.

Not Available

1983-04-01T23:59:59.000Z

22

Design options for a bunsen reactor.  

SciTech Connect (OSTI)

This work is being performed for Matt Channon Consulting as part of the Sandia National Laboratories New Mexico Small Business Assistance Program (NMSBA). Matt Channon Consulting has requested Sandia's assistance in the design of a chemical Bunsen reactor for the reaction of SO2, I2 and H2O to produce H2SO4 and HI with a SO2 feed rate to the reactor of 50 kg/hour. Based on this value, an assumed reactor efficiency of 33%, and kinetic data from the literature, a plug flow reactor approximately 1%E2%80%9D diameter and and 12 inches long would be needed to meet the specification of the project. Because the Bunsen reaction is exothermic, heat in the amount of approximately 128,000 kJ/hr would need to be removed using a cooling jacket placed around the tubular reactor. The available literature information on Bunsen reactor design and operation, certain support equipment needed for process operation and a design that meet the specification of Matt Channon Consulting are presented.

Moore, Robert Charles

2013-10-01T23:59:59.000Z

23

Annular Core Research Reactor - Critical to Science-Based Weapons...  

National Nuclear Security Administration (NNSA)

Annular Core Research Reactor - Critical to Science-Based Weapons Design, Certification | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People...

24

Computer simulations help design new nuclear reactors  

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

Computer simulations help design new nuclear reactors 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 Reprinted from "Argonne Now" - Spring 2008 Physicist Won-Sik Yang and computer scientist Andrew Siegel hold a fuel rod assembly in front of a model of the Experimental Breeder Reactor-II

25

The Argonaut Reactor - Reactors designed/built by Argonne National  

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

Achievements > Achievements > Argonne Reactors > Training Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

26

Helium circulator design considerations for modular high temperature gas-cooled reactor plant  

SciTech Connect (OSTI)

Efforts are in progress to develop a standard modular high temperature gas-cooled reactor (MHTGR) plant that is amenable to design certification and serial production. The MHTGR reference design, based on a steam cycle power conversion system, utilizes a 350 MW(t) annular reactor core with prismatic fuel elements. Flexibility in power rating is afforded by utilizing a multiplicity of the standard module. The circulator, which is an electric motor-driven helium compressor, is a key component in the primary system of the nuclear plant, since it facilitates thermal energy transfer from the reactor core to the steam generator; and, hence, to the external turbo-generator set. This paper highlights the helium circulator design considerations for the reference MHTGR plant and includes a discussion on the major features of the turbomachine concept, operational characteristics, and the technology base that exists in the U.S.

McDonald, C.F.; Nichols, M.K.

1987-01-01T23:59:59.000Z

27

Helium circulator design considerations for modular high temperature gas-cooled reactor plant  

SciTech Connect (OSTI)

Efforts are in progress to develop a standard modular high temperature gas-cooled reactor (MHTGR) plant that is amenable to design certification and serial production. The MHTGR reference design, based on a steam cycle power conversion system, utilizes a 350 MW(t) annular reactor core with prismatic fuel elements. Flexibility in power rating is afforded by utilizing a multiplicity of the standard module. The circulator, which is an electric motor-driven helium compressor, is a key component in the primary system of the nuclear plant, since it facilitates thermal energy transfer from the reactor core to the steam generator; and, hence, to the external turbo-generator set. This paper highlights the helium circulator design considerations for the reference MHTGR plant and includes a discussion on the major features of the turbomachine concept, operational characteristics, and the technology base that exists in the US.

McDonald, C.F.; Nichols, M.K.

1986-12-01T23:59:59.000Z

28

Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 1, Chapters 1--14  

SciTech Connect (OSTI)

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE`s System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report.

Not Available

1994-08-01T23:59:59.000Z

29

Using reactor operating experience to improve the design of a new Broad Application Test Reactor  

SciTech Connect (OSTI)

Increasing regulatory demands and effects of plant aging are limiting the operation of existing test reactors. Additionally, these reactors have limited capacities and capabilities for supporting future testing missions. A multidisciplinary team of experts developed sets of preliminary safety requirements, facility user needs, and reactor design concepts for a new Broad Application Test Reactor (BATR). Anticipated missions for the new reactor include fuels and materials irradiation testing, isotope production, space testing, medical research, fusion testing, intense positron research, and transmutation doping. The early BATR design decisions have benefited from operating experiences with existing reactors. This paper discusses these experiences and highlights their significance for the design of a new BATR.

Fletcher, C.D.; Ryskamp, J.M.; Drexler, R.L.; Leyse, C.F.

1993-07-01T23:59:59.000Z

30

International Effort to Design Nuclear Fusion Reactor Launched  

Science Journals Connector (OSTI)

International Effort to Design Nuclear Fusion Reactor Launched ... Their mission is to draw up a design concept for a thermonuclear fusion reactor by December 1990. ... The work at Garching is a direct outgrowth of the recently signed International Thermonuclear Experimental Reactor (ITER) pact involving the European Community, Japan, the Soviet Union, and the U.S. (C&EN, April 25, page 19). ...

DERMOT A. O'SULLLVAN

1988-05-23T23:59:59.000Z

31

Advanced thermionic reactor systems design code  

SciTech Connect (OSTI)

An overall systems design code is under development to model an advanced in-core thermionic nuclear reactor system for space applications at power levels of 10 to 50 kWe. The design code is written in an object-oriented programming environment that allows the use of a series of design modules, each of which is responsible for the determination of specific system parameters. The code modules include a neutronics and core criticality module, a core thermal hydraulics module, a thermionic fuel element performance module, a radiation shielding module, a module for waste heat transfer and rejection, and modules for power conditioning and control. The neutronics and core criticality module determines critical core size, core lifetime, and shutdown margins using the criticality calculation capability of the Monte Carlo Neutron and Photon Transport Code System (MCNP). The remaining modules utilize results of the MCNP analysis along with FORTRAN programming to predict the overall system performance.

Lewis, B.R.; Pawlowski, R.A.; Greek, K.J.; Klein, A.C. (Department of Nuclear Engineering, Radiation Center, C116, Oregon State University, Corvallis, Oregon 97331-5902 (US))

1991-01-01T23:59:59.000Z

32

Neutron transport analysis for nuclear reactor design  

DOE Patents [OSTI]

Replacing regular mesh-dependent ray tracing modules in a collision/transfer probability (CTP) code with a ray tracing module based upon combinatorial geometry of a modified geometrical module (GMC) provides a general geometry transfer theory code in two dimensions (2D) for analyzing nuclear reactor design and control. The primary modification of the GMC module involves generation of a fixed inner frame and a rotating outer frame, where the inner frame contains all reactor regions of interest, e.g., part of a reactor assembly, an assembly, or several assemblies, and the outer frame, with a set of parallel equidistant rays (lines) attached to it, rotates around the inner frame. The modified GMC module allows for determining for each parallel ray (line), the intersections with zone boundaries, the path length between the intersections, the total number of zones on a track, the zone and medium numbers, and the intersections with the outer surface, which parameters may be used in the CTP code to calculate collision/transfer probability and cross-section values.

Vujic, Jasmina L. (Lisle, IL)

1993-01-01T23:59:59.000Z

33

A Methodology for the Neutronics Design of Space Nuclear Reactors  

SciTech Connect (OSTI)

A methodology for the neutronics design of space power reactors is presented. This methodology involves balancing the competing requirements of having sufficient excess reactivity for the desired lifetime, keeping the reactor subcritical at launch and during submersion accidents, and providing sufficient control over the lifetime of the reactor. These requirements are addressed by three reactivity values for a given reactor design: the excess reactivity at beginning of mission, the negative reactivity at shutdown, and the negative reactivity margin in submersion accidents. These reactivity values define the control worth and the safety worth in submersion accidents, used for evaluating the merit of a proposed reactor type and design. The Heat Pipe-Segmented Thermoelectric Module Converters space reactor core design is evaluated and modified based on the proposed methodology. The final reactor core design has sufficient excess reactivity for 10 years of nominal operation at 1.82 MW of fission power and is subcritical at launch and in all water submersion accidents.

King, Jeffrey C.; El-Genk, Mohamed S. [Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM 87131 (United States); Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM 87131 (United States)

2004-02-04T23:59:59.000Z

34

Design of Complex Systems to Achieve Passive Safety: Natural Circulation Cooling of Liquid Salt Pebble Bed Reactors  

E-Print Network [OSTI]

a tool for reactor design optimization, and for design ofdesign tool for reactor design optimization, and for designdesign tool for reactor design optimization, and for design

Scarlat, Raluca Olga

2012-01-01T23:59:59.000Z

35

Manhattan Project: Production Reactor (Pile) Design, Met Lab, 1942  

Office of Scientific and Technical Information (OSTI)

Schematic of the X-10 Graphite Reactor, Oak Ridge PRODUCTION REACTOR (PILE) DESIGN Schematic of the X-10 Graphite Reactor, Oak Ridge PRODUCTION REACTOR (PILE) DESIGN (Met Lab, 1942) Events > The Plutonium Path to the Bomb, 1942-1944 Production Reactor (Pile) Design, 1942 DuPont and Hanford, 1942 CP-1 Goes Critical, December 2, 1942 Seaborg and Plutonium Chemistry, 1942-1944 Final Reactor Design and X-10, 1942-1943 Hanford Becomes Operational, 1943-1944 By 1942, scientists had established that some of the uranium exposed to radioactivity in a reactor (pile) would eventually decay into plutonium, which could then be separated by chemical means from the uranium. Important theoretical research on this was ongoing, but the work was scattered at various universities from coast to coast. In early 1942, Arthur Compton arranged for all pile research to be moved to the Met Lab at the University of Chicago.

36

TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO  

E-Print Network [OSTI]

GA­A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO by C.P.C. WONG and R.D. STAMBAUGH or reflect those of the United States Government or any agency thereof. #12;GA­A23168 TOKAMAK REACTOR DESIGNS JULY 1999 #12;C.P.C. WONG AND R.D. STAMBAUGH TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

California at Los Angeles, University of

37

InterIor DesIgn CERTIFICATE PROGRAM  

E-Print Network [OSTI]

sketchUp Your Design 12 hours, $325 Learn to build computer generated models of interior spaces with ease in this hands-on opportunity to utilize Google SketchUp to convey your design ideas and boost your design and developing interior spaces in detail. Google SketchUp is a free download at www.sketchup.google.com. topics

Fork, Richard

38

Cost-Shared Development of Innovative Small Modular Reactor Designs |  

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

Cost-Shared Development of Innovative Small Modular Reactor Designs Cost-Shared Development of Innovative Small Modular Reactor Designs Cost-Shared Development of Innovative Small Modular Reactor Designs The Small Modular Reactor (SMR) Licensing Technical Support (LTS) program, sponsored by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), through this Funding Opportunity Announcement (FOA) seeks to facilitate the development of innovative SMR designs that have the potential to address the nation's economic, environmental and energy security goals. Specifically, the Department is soliciting applications for SMR designs that offer unique and innovative solutions for achieving the objectives of enhanced safety, operations, and performance relative to currently certified designs. This FOA focuses on design development and

39

Cost-Shared Development of Innovative Small Modular Reactor Designs |  

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

Cost-Shared Development of Innovative Small Modular Reactor Designs Cost-Shared Development of Innovative Small Modular Reactor Designs Cost-Shared Development of Innovative Small Modular Reactor Designs The Small Modular Reactor (SMR) Licensing Technical Support (LTS) program, sponsored by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), through this Funding Opportunity Announcement (FOA) seeks to facilitate the development of innovative SMR designs that have the potential to address the nation's economic, environmental and energy security goals. Specifically, the Department is soliciting applications for SMR designs that offer unique and innovative solutions for achieving the objectives of enhanced safety, operations, and performance relative to currently certified designs. This FOA focuses on design development and

40

Design of a 25-kWe Surface Reactor System Based on SNAP Reactor Technologies  

SciTech Connect (OSTI)

A Hastelloy-X clad, sodium-potassium (NaK-78) cooled, moderated spectrum reactor using uranium zirconium hydride (UZrH) fuel based on the SNAP program reactors is a promising design for use in surface power systems. This paper presents a 98 kWth reactor for a power system the uses multiple Stirling engines to produce 25 kWe-net for 5 years. The design utilizes a pin type geometry containing UZrHx fuel clad with Hastelloy-X and NaK-78 flowing around the pins as coolant. A compelling feature of this design is its use of 49.9% enriched U, allowing it to be classified as a category III-D attractiveness and reducing facility costs relative to highly-enriched space reactor concepts. Presented below are both the design and an analysis of this reactor's criticality under various safety and operations scenarios.

Dixon, David D. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Hiatt, Matthew T. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Department of Nuclear Engineering, Texas A and M University, College Station, TX 77843 (United States); Poston, David I.; Kapernick, Richard J. [Nuclear Systems Design Group, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

2006-01-20T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Design of chemical reactors of the heat exchanger type  

E-Print Network [OSTI]

Operating Profile - Example I 23 , 53 Heat Rate Comparison - Example I Operating Profile - Example 2 Operating Profile - Example 3 Operating Profile - Example 4 Equations (113) and (114) at 790 Reactor Profile - Exan piss 5 and 6 Heat of Reaction.... simple inathematical function of time. While his work was a step forward, it is not directly applicable to the problem of reactor design. Hougen and Watsor. (3), and recently Fair and Rase (4), illustra- ted an exact non-machine method of reactor...

McBeth, Lloyd Theodore

2012-06-07T23:59:59.000Z

42

DESIGN OF A TOKAMAK FUSION REACTOR FIRST WALL ARMOR AGAINST NEUTRAL BEAM IMPINGEMENT  

E-Print Network [OSTI]

et. a1. , "A Conceptual Tokamak Reactor Design, umtAK-II,"et. al.. "A Non-Circular Tokamak 'Power Reactor Design,"Contt'ol in Near Term Tokamak Reactors," Proceedings of the

Myers, Richard Allen

2011-01-01T23:59:59.000Z

43

High temperature gas cooled reactor steam-methane reformer design  

SciTech Connect (OSTI)

The concept of the long distance transportation of process heat energy from a High Temperature Gas Cooled Reactor (HTGR) heat source, based on the steam-methane reforming reaction, is being evaluated by the Department of Energy as an energy source/application for use early in the 21st century. This paper summaries the design of a helium heated steam reformer utilized in conjunction with an intermediate loop, 850/degree/C reactor outlet temperature, HTGR process heat plant concept. This paper also discusses various design considerations leading to the mechanical design features, the thermochemical performance, the materials selection and the structural design analysis. 12 refs.

Impellezzeri, J.R.; Drendel, D.B.; Odegaard, T.K.

1981-01-01T23:59:59.000Z

44

Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor  

E-Print Network [OSTI]

A design for a large, passive, light water reactor has been developed. The proposed concept is a pressure tube reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid SiC-coated ...

Hejzlar, P.

45

Safety and core design of large liquid-metal cooled fast breeder reactors  

E-Print Network [OSTI]

reactor core design 7 Assembly Design and Optimization codePhysics Optimization of Breed and Burn Fast Reactor Systems.OPTIMIZATION CODE (ADOPT) Table 7.4: SWR B&B Reference Reactor

Qvist, Staffan Alexander

2013-01-01T23:59:59.000Z

46

Generation III reactors safety requirements and the design solutions  

SciTech Connect (OSTI)

Nuclear energy's public acceptance, and hence its development, depends on its safety. As a reactor designer, we will first briefly remind the basic safety principles of nuclear reactors' design. We will then show how the industry, and in particular Areva with its EPR, made design evolution in the wake of the Three Miles Island accident in 1979. In particular, for this new generation of reactors, severe accidents are taken into account beyond the standard design basis accidents. Today, Areva's EPR meets all so-called 'generation III' safety requirements and was licensed by several nuclear safety authorities in the world. Many innovative solutions are integrated in the EPR, some of which will be introduced here.

Felten, P. [Areva NP (France)

2009-03-31T23:59:59.000Z

47

Status of Fusion Reactor Blanket Design  

Science Journals Connector (OSTI)

Blanket Design and Evaluation / Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986)

D. L. Smith; D.-K. Sze

48

High-resolution coupled physics solvers for analysing fine-scale nuclear reactor design problems  

Science Journals Connector (OSTI)

...solvers for analysing fine-scale nuclear reactor design problems Vijay S. Mahadevan...analysis of current and future nuclear reactor models is being investigated...in radiation hydrodynamics, nuclear reactor analysis, fluid-structure...

2014-01-01T23:59:59.000Z

49

RAMI Analysis Program Design and Research for CFETR (Chinese Fusion Engineering Testing Reactor) Tokamak Machine  

Science Journals Connector (OSTI)

Chinese Fusion Engineering Testing Reactor (CFETR) is a test reactor which shall be constructed by National Integration Design Group for Magnetic Confinement Fusion Reactor of China with an ambitious scientific ...

Shijun Qin; Yuntao Song; Damao Yao; Yuanxi Wan; Songtao Wu…

2014-10-01T23:59:59.000Z

50

Fast Reactor Subassembly Design Modifications for Increasing Electricity Generation Efficiency  

SciTech Connect (OSTI)

Suggested for Track 7: Advances in Reactor Core Design and In-Core Management _____________________________________________________________________________________ Fast Reactor Subassembly Design Modifications for Increasing Electricity Generation Efficiency R. Wigeland and K. Hamman Idaho National Laboratory Given the ability of fast reactors to effectively transmute the transuranic elements as are present in spent nuclear fuel, fast reactors are being considered as one element of future nuclear power systems to enable continued use and growth of nuclear power by limiting high-level waste generation. However, a key issue for fast reactors is higher electricity cost relative to other forms of nuclear energy generation. The economics of the fast reactor are affected by the amount of electric power that can be produced from a reactor, i.e., the thermal efficiency for electricity generation. The present study is examining the potential for fast reactor subassembly design changes to improve the thermal efficiency by increasing the average coolant outlet temperature without increasing peak temperatures within the subassembly, i.e., to make better use of current technology. Sodium-cooled fast reactors operate at temperatures far below the coolant boiling point, so that the maximum coolant outlet temperature is limited by the acceptable peak temperatures for the reactor fuel and cladding. Fast reactor fuel subassemblies have historically been constructed using a large number of small diameter fuel pins contained within a tube of hexagonal cross-section, or hexcan. Due to this design, there is a larger coolant flow area next to the hexcan wall as compared to flow area in the interior of the subassembly. This results in a higher flow rate near the hexcan wall, overcooling the fuel pins next to the wall, and a non-uniform coolant temperature distribution. It has been recognized for many years that this difference in sodium coolant temperature was detrimental to achieving greater thermal efficiency, since it causes the fuel pins in the center of the subassembly to operate at higher temperatures than those near the hexcan walls, and it is the temperature limit(s) for those fuel pins that limits the average coolant outlet temperature. Fuel subassembly design changes are being investigated using computational fluid dynamics (CFD) to quantify the effect that the design changes have on reducing the intra-subassembly coolant flow and temperature distribution. Simulations have been performed for a 19-pin test subassembly geometry using typical fuel pin diameters and wire wrap spacers. The results have shown that it may be possible to increase the average coolant outlet temperature by 20 C or more without changing the peak temperatures within the subassembly. These design changes should also be effective for reactor designs using subassemblies with larger numbers of fuel pins. R. Wigeland, Idaho National Laboratory, P.O. Box 1625, Mail Stop 3860, Idaho Falls, ID, U.S.A., 83415-3860 email – roald.wigeland@inl.gov fax (U.S.) – 208-526-2930

R. Wigeland; K. Hamman

2009-09-01T23:59:59.000Z

51

Certificate Ethics Certificate Program  

E-Print Network [OSTI]

Ethics Certificate Program Passion Purpose Rigor #12;#12;Ethics Certificate Program From, the Ethics Certificate provides you with the skills and confidence you need to create and evaluate solutions to ethical dilemmas. Does a government have the right to insist on another government's adherence to human

Zhou, Pei

52

System modeling and reactor design studies of the Advanced Thermionic Initiative space nuclear reactor  

SciTech Connect (OSTI)

In-core thermionic space reactor design concepts that operate at a nominal power output range of 20 to 50 kW(electric) are described. Details of the neutronic, thermionic, thermal hydraulics, and shielding performance are presented. Because of the strong absorption of thermal neutrons by natural tungsten and the large amount of natural tungsten within the reactor core, two designs are considered. An overall system design code has been developed at Oregon State University to model advanced in-core thermionic energy conversion-based nuclear reactor systems for space applications. The results show that the driverless single-cell Advanced Thermionic Initiative (ATI) configuration, which does not have driver fuel rods, proved to be more efficient than the driven core, which has driver rods. The results also show that the inclusion of the true axial and radial power distribution decrease the overall conversion efficiency. The flattening of the radial power distribution by three different methods would lead to a higher efficiency. The results show that only one TFE works at the optimum emitter temperature; all other TFEs are off the optimum performance and result in a 40% decrease of the efficiency of the overall system. The true axial profile is significantly different as there is a considerable amount of neutron leakage out of the top and bottom of the reactor. The analysis reveals that the axial power profile actually has a chopped cosine shape. For this axial profile, the reactor core overall efficiency for the driverless ATI reactor version is found to be 5.84% with a total electrical power of 21.92 kW(electric). By considering the true axial power profile instead of the uniform power profile, each TFE loses {approximately}80 W(electric).

Lee, H.H.; Abdul-Hamid, S.; Klein, A.C. [Oregon State Univ., Corvallis, OR (United States). Dept. of Nuclear Engineering Radiation Center] [Oregon State Univ., Corvallis, OR (United States). Dept. of Nuclear Engineering Radiation Center

1996-07-01T23:59:59.000Z

53

System 80+{trademark} standard design: CESSAR design certification. Volume 5: Amendment I  

SciTech Connect (OSTI)

This report has been prepared in support of the industry effort to standardize nuclear plant designs. The documents in this series describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design.

Not Available

1990-12-21T23:59:59.000Z

54

Assigning Seismic Design Category to Large Reactors: A Case Study of the ATR  

Broader source: Energy.gov [DOE]

Assigning Seismic Design Category to Large Reactors: A Case Study of the ATR Stuart Jensen October 21, 2014

55

Nuclear Design of the HOMER-15 Mars Surface Fission Reactor  

SciTech Connect (OSTI)

The next generation of robotic missions to Mars will most likely require robust power sources in the range of 3 to 20 kWe. Fission systems are well suited to provide safe, reliable, and economic power within this range. The goal of this study is to design a compact, low-mass fission system that meets Mars surface power requirements, while maintaining a high level of safety and reliability at a relatively low cost. The Heat pipe Power System (HPS) is one possible approach for producing near-term, low-cost, space fission power. The goal of the HPS project is to devise an attractive space fission system that can be developed quickly and affordably. The primary ways of doing this are by using existing technology and by designing the system for inexpensive testing. If the system can be designed to allow highly prototypic testing with electrical heating, then an exhaustive test program can be carried out quickly and inexpensively, and thorough testing of the actual flight unit can be performed - which is a major benefit to reliability. Over the past 4 years, three small HPS proof-of-concept technology demonstrations have been conducted, and each has been highly successful. The Heat pipe-Operated Mars Exploration Reactor (HOMER) is a derivative of the HPS designed especially for producing power on the surface of Mars. The HOMER-15 is a 15-kWt reactor that couples with a 3-kWe Stirling engine power system. The reactor contains stainless-steel (SS)-clad uranium nitride (UN) fuel pins that are structurally and thermally bonded to SS/sodium heat pipes. Fission energy is conducted from the fuel pins to the heat pipes, which then carry the heat to the Stirling engine. This paper describes conceptual design and nuclear performance the HOMER-15 reactor. (author)

Poston, David I. [Nuclear Systems Design Group, Decision Applications Division, Los Alamos National Laboratory, Los Alamos, New Mexico, 87545 (United States)

2002-07-01T23:59:59.000Z

56

Design, fabrication, and certification of advanced modular PV power systems. Final technical progress report  

SciTech Connect (OSTI)

Solar Electric Specialties Company (SES) has completed a two and a half year effort under the auspices of the US Department of Energy (DOE) PVMaT (Photovoltaic Manufacturing Technology) project. Under Phase 4A1 of the project for Product Driven System and Component Technology, the SES contract ``Design, Fabrication and Certification of Advanced Modular PV Power Systems`` had the goal to reduce installed system life cycle costs through development of certified (Underwriters Laboratories or other listing) and standardized prototype products for two of the product lines, MAPPS{trademark} (Modular Autonomous PV Power Supply) and Photogensets{trademark}. MAPPS are small DC systems consisting of Photovoltaic modules, batteries and a charge controller and producing up to about a thousand watt-hours per day. Photogensets are stand-alone AC systems incorporating a generator as backup for the PV in addition to a DC-AC inverter and battery charger. The program tasks for the two-year contract consisted of designing and fabricating prototypes of both a MAPPS and a Photogenset to meet agency listing requirements using modular concepts that would support development of families of products, submitting the prototypes for listing, and performing functionality testing at Sandia and NREL. Both prototypes were candidates for UL (Underwriters Laboratories) listing. The MAPPS was also a candidate for FM (Factory Mutual) approval for hazardous (incendiary gases) locations.

Lambarski, T.; Minyard, G. [Solar Electric Specialties Co., Willits, CA (United States)

1998-10-01T23:59:59.000Z

57

Energy Department Issues Green Building Certification System...  

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

Issues Green Building Certification System Final Rule to Support Increased Energy Measurement and Efficient Building Design Energy Department Issues Green Building Certification...

58

Novel Reactor Design for Solid Fuel Chemical Looping Combustion  

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

Novel Reactor Design for Solid Fuel Novel Reactor Design for Solid Fuel Chemical Looping Combustion Opportunity Research is active on the patent pending technology, titled "Apparatus and Method for Solid Fuel Chemical Looping Combustion." This technology is available for licensing and/or further collaborative research from the U.S. Department of Energy's National Energy Technology Laboratory. Overview The removal of CO2 from power plants is challenging because existing methods to separate CO2 from the gas mixture requires a significant fraction of the power plant output. Chemical-looping combustion (CLC) is a novel technology that utilizes a metal oxide oxygen carrier to transport oxygen to the fuel thereby avoiding direct contact between fuel and air. The use of CLC has the advantages of reducing the energy penalty while

59

OPTIMAL DESIGN OF A HIGH PRESSURE ORGANOMETALLIC CHEMICAL VAPOR DEPOSITION REACTOR  

E-Print Network [OSTI]

OPTIMAL DESIGN OF A HIGH PRESSURE ORGANOMETALLIC CHEMICAL VAPOR DEPOSITION REACTOR K.J. BACHMANN of computer simulations as an optimal design tool which lessens the costs in time and effort in experimental vapor deposition (HPOMCVD) reactor for use in thin film crystal growth. The advantages of such a reactor

60

Effects of an Advanced Reactor’s Design, Use of Automation, and Mission on Human Operators  

SciTech Connect (OSTI)

The roles, functions, and tasks of the human operator in existing light water nuclear power plants (NPPs) are based on sound nuclear and human factors engineering (HFE) principles, are well defined by the plant’s conduct of operations, and have been validated by years of operating experience. However, advanced NPPs whose engineering designs differ from existing light-water reactors (LWRs) will impose changes on the roles, functions, and tasks of the human operators. The plans to increase the use of automation, reduce staffing levels, and add to the mission of these advanced NPPs will also affect the operator’s roles, functions, and tasks. We assert that these factors, which do not appear to have received a lot of attention by the design engineers of advanced NPPs relative to the attention given to conceptual design of these reactors, can have significant risk implications for the operators and overall plant safety if not mitigated appropriately. This paper presents a high-level analysis of a specific advanced NPP and how its engineered design, its plan to use greater levels of automation, and its expanded mission have risk significant implications on operator performance and overall plant safety.

Jeffrey C. Joe; Johanna H. Oxstrand

2014-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Achievements: Nuclear Reactors designed/built by Argonne National  

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

Achievements > Achievements > Argonne National Laboratory Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy

62

Design, optimization and evaluation of a free-fall biomass fast pyrolysis reactor and its products.  

E-Print Network [OSTI]

??The focus of this work is a radiatively heated, free-fall, fast pyrolysis reactor. The reactor was designed and constructed for the production of bio-oil from… (more)

Ellens, Cody James

2009-01-01T23:59:59.000Z

63

Fast reactor power plant design having heat pipe heat exchanger  

DOE Patents [OSTI]

The invention relates to a pool-type fission reactor power plant design having a reactor vessel containing a primary coolant (such as liquid sodium), and a steam expansion device powered by a pressurized water/steam coolant system. Heat pipe means are disposed between the primary and water coolants to complete the heat transfer therebetween. The heat pipes are vertically oriented, penetrating the reactor deck and being directly submerged in the primary coolant. A U-tube or line passes through each heat pipe, extended over most of the length of the heat pipe and having its walls spaced from but closely proximate to and generally facing the surrounding walls of the heat pipe. The water/steam coolant loop includes each U-tube and the steam expansion device. A heat transfer medium (such as mercury) fills each of the heat pipes. The thermal energy from the primary coolant is transferred to the water coolant by isothermal evaporation-condensation of the heat transfer medium between the heat pipe and U-tube walls, the heat transfer medium moving within the heat pipe primarily transversely between these walls.

Huebotter, P.R.; McLennan, G.A.

1984-08-30T23:59:59.000Z

64

Fast reactor power plant design having heat pipe heat exchanger  

DOE Patents [OSTI]

The invention relates to a pool-type fission reactor power plant design having a reactor vessel containing a primary coolant (such as liquid sodium), and a steam expansion device powered by a pressurized water/steam coolant system. Heat pipe means are disposed between the primary and water coolants to complete the heat transfer therebetween. The heat pipes are vertically oriented, penetrating the reactor deck and being directly submerged in the primary coolant. A U-tube or line passes through each heat pipe, extended over most of the length of the heat pipe and having its walls spaced from but closely proximate to and generally facing the surrounding walls of the heat pipe. The water/steam coolant loop includes each U-tube and the steam expansion device. A heat transfer medium (such as mercury) fills each of the heat pipes. The thermal energy from the primary coolant is transferred to the water coolant by isothermal evaporation-condensation of the heat transfer medium between the heat pipe and U-tube walls, the heat transfer medium moving within the heat pipe primarily transversely between these walls.

Huebotter, Paul R. (Western Springs, IL); McLennan, George A. (Downers Grove, IL)

1985-01-01T23:59:59.000Z

65

Early Exploration - Reactors designed/built by Argonne National Laboratory  

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

Early Exploration Early Exploration About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

66

DOI Designates B Reactor at DOE's Hanford Site as a National Historic  

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

DOI Designates B Reactor at DOE's Hanford Site as a National DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark August 25, 2008 - 3:20pm Addthis DOE to offer regular public tours in 2009 WASHINGTON, DC - U.S. Department of the Interior (DOI) Deputy Secretary Lynn Scarlett and U.S. Department of Energy (DOE) Acting Deputy Secretary Jeffrey F. Kupfer today announced the designation of DOE's B Reactor as a National Historic Landmark and unveiled DOE's plan for a new public access program to enable American citizens to visit B Reactor during the 2009 tourist season. The B Reactor at DOE's Hanford Site in southeast Washington State was the world's first industrial-scale nuclear reactor and produced plutonium for the atomic weapon that was dropped on Nagasaki,

67

DOI Designates B Reactor at DOE's Hanford Site as a National Historic  

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

DOI Designates B Reactor at DOE's Hanford Site as a National DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark DOI Designates B Reactor at DOE's Hanford Site as a National Historic Landmark August 25, 2008 - 3:20pm Addthis DOE to offer regular public tours in 2009 WASHINGTON, DC - U.S. Department of the Interior (DOI) Deputy Secretary Lynn Scarlett and U.S. Department of Energy (DOE) Acting Deputy Secretary Jeffrey F. Kupfer today announced the designation of DOE's B Reactor as a National Historic Landmark and unveiled DOE's plan for a new public access program to enable American citizens to visit B Reactor during the 2009 tourist season. The B Reactor at DOE's Hanford Site in southeast Washington State was the world's first industrial-scale nuclear reactor and produced plutonium for the atomic weapon that was dropped on Nagasaki,

68

Design Windows for a He Cooled Fusion Reactor* Dai-Kai Sze and Ahmed Hassanein  

E-Print Network [OSTI]

Design Windows for a He Cooled Fusion Reactor* Dai-Kai Sze and Ahmed Hassanein Argonne National Laboratory 9700 South Cass Avenue, Argonne, IL 60439 EQUATIONDERIVATION ABSTRACT A design window concept is developed for a He-cooled fusion reactor blanket and divertor design. This concept allows study

Harilal, S. S.

69

Innovative fusion reactor design analysis: Annual performance report, May 15, 1988--January 31, 1989  

SciTech Connect (OSTI)

This report discusses the following topics on fusion reactor component design: FLiBe intermediate heat exchanger design analysis; FLiBe properties; design methodology; FLiBe system steam generator freezeup; FLiBe reactor systems studies; tritium breeding ratio control; analysis of original objectives; and budget analysis. 15 refs., 13 figs., 3 tabs. (LSP)

Klein, A.C.

1989-01-31T23:59:59.000Z

70

The Integral Fast Reactor (IFR) - Reactors designed/built by Argonne  

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

Integral Fast Reactor Integral Fast Reactor About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

71

Improved Design of Nuclear Reactor Control System | U.S. DOE...  

Office of Science (SC) Website

instrumentation: Improved Design of Nuclear Reactor Control System Developed at: Oak Ridge National Laboratory, Holifield Radioactive Ion Beam Facility (HRIBF) Developed...

72

Radiochemical characteristics of tritium to be considered in fusion reactor facility design  

Science Journals Connector (OSTI)

The results of research and development related to radiochemical characteristics of tritium to be considered in a fusion reactor facility design are summarized. Reactions induced by...

S. O’hira; T. Hayashi; W. Shu; T. Yamanishi

2007-06-01T23:59:59.000Z

73

High Flux Isotope Reactor cold neutron source reference design concept  

SciTech Connect (OSTI)

In February 1995, Oak Ridge National Laboratory`s (ORNL`s) deputy director formed a group to examine the need for upgrades to the High Flux Isotope Reactor (HFIR) system in light of the cancellation of the Advanced neutron Source Project. One of the major findings of this study was that there was an immediate need for the installation of a cold neutron source facility in the HFIR complex. In May 1995, a team was formed to examine the feasibility of retrofitting a liquid hydrogen (LH{sub 2}) cold source facility into an existing HFIR beam tube. The results of this feasibility study indicated that the most practical location for such a cold source was the HB-4 beam tube. This location provides a potential flux environment higher than the Institut Laue-Langevin (ILL) vertical cold source and maximizes the space available for a future cold neutron guide hall expansion. It was determined that this cold neutron beam would be comparable, in cold neutron brightness, to the best facilities in the world, and a decision was made to complete a preconceptual design study with the intention of proceeding with an activity to install a working LH{sub 2} cold source in the HFIR HB-4 beam tube. During the development of the reference design the liquid hydrogen concept was changed to a supercritical hydrogen system for a number of reasons. This report documents the reference supercritical hydrogen design and its performance. The cold source project has been divided into four phases: (1) preconceptual, (2) conceptual design and testing, (3) detailed design and procurement, and (4) installation and operation. This report marks the conclusion of the conceptual design phase and establishes the baseline reference concept.

Selby, D.L.; Lucas, A.T.; Hyman, C.R. [and others

1998-05-01T23:59:59.000Z

74

Small Modular Fast Reactor Design Description Joint Effort  

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

July 1, 2005 ANL-SMFR-1 July 1, 2005 ANL-SMFR-1 Small Modular Fast Reactor Design Description Joint Effort by Argonne National Laboratory (ANL) Commissariat a l'Energie Atomique (CEA) and Japan Nuclear Cycle Development Institute (JNC) Project Leaders Y. I. Chang and C. Grandy, ANL P. Lo Pinto, CEA M. Konomura, JNC Technical Contributors ANL: J. Cahalan, F. Dunn, M. Farmer, S. Kamal, L. Krajtl, A. Moisseytsev, Y. Momozaki, J. Sienicki, Y. Park, Y. Tang, C. Reed, C. Tzanos, S. Wiedmeyer, and W. Yang CEA: P. Allegre, J. Astegiano, F. Baque, L. Cachon, M. S. Chenaud, J-L Courouau, Ph. Dufour, J. C. Klein, C. Latge, C. Thevenot, and F. Varaine JNC: M. Ando, Y. Chikazawa, M. Nagamura, Y. Okano, Y. Sakamoto,

75

Why Nuclear Energy? - Reactors designed/built by Argonne National  

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

Nuclear Energy: Nuclear Energy: Why Nuclear Energy? About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

76

High flux isotope reactor cold source preconceptual design study report  

SciTech Connect (OSTI)

In February 1995, the deputy director of Oak Ridge National Laboratory (ORNL) formed a group to examine the need for upgrades to the High Flux Isotope Reactor (HFIR) system in light of the cancellation of the Advanced Neutron Source Project. One of the major findings of this study was that there was an immediate need for the installation of a cold neutron source facility in the HFIR complex. The anticipated cold source will consist of a cryogenic LH{sub 2} moderator plug, a cryogenic pump system, a refrigerator that uses helium gas as a refrigerant, a heat exchanger to interface the refrigerant with the hydrogen loop, liquid hydrogen transfer lines, a gas handling system that includes vacuum lines, and an instrumentation and control system to provide constant system status monitoring and to maintain system stability. The scope of this project includes the development, design, safety analysis, procurement/fabrication, testing, and installation of all of the components necessary to produce a working cold source within an existing HFIR beam tube. This project will also include those activities necessary to transport the cold neutron beam to the front face of the present HFIR beam room. The cold source project has been divided into four phases: (1) preconceptual, (2) conceptual design and research and development (R and D), (3) detailed design and procurement, and (4) installation and operation. This report marks the conclusion of the preconceptual phase and establishes the concept feasibility. The information presented includes the project scope, the preliminary design requirements, the preliminary cost and schedule, the preliminary performance data, and an outline of the various plans for completing the project.

Selby, D.L.; Bucholz, J.A.; Burnette, S.E. [and others

1995-12-01T23:59:59.000Z

77

High-resolution coupled physics solvers for analysing fine-scale nuclear reactor design problems  

Science Journals Connector (OSTI)

...methodology and software interfaces of...often used in radiation hydrodynamics...reactor design and safety analyses. In...enable appropriate software interfaces...Ragusa. 2007 Software design of SHARP...nuclear reactor safety: multi-scale...methods for the radiation-diffusion equations...

2014-01-01T23:59:59.000Z

78

Conceptual design of an annular-fueled superheat boiling water reactor  

E-Print Network [OSTI]

The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron ...

Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

2011-01-01T23:59:59.000Z

79

GCRA review and appraisal of HTGR reactor-core-design program. [HTGR-SC, -R, -NHSDR  

SciTech Connect (OSTI)

The reactor-core-design program has as its principal objective and responsibility the design and resolution of major technical issues for the reactor core and core components on a schedule consistent with the plant licensing and construction program. The task covered in this review includes three major design areas: core physics, core thermal and hydraulic performance fuel element design, and in-core fuel performance evaluation.

Not Available

1980-09-01T23:59:59.000Z

80

Nuclear Power 2010 Program Lessons Learned Report on the Combined Construction and Operating License/Design Certification Demonstration Projects  

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

Nuclear Power 2010 Program Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report August 30, 2012 Prepared by Longenecker and Associates DISCLAIMER 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, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not

Note: This page contains sample records for the topic "reactor design certification" 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

A Basic LEGO Reactor Design for the Provision of Lunar Surface Power  

SciTech Connect (OSTI)

A final design has been established for a basic Lunar Evolutionary Growth-Optimized (LEGO) Reactor using current and near-term technologies. The LEGO Reactor is a modular, fast-fission, heatpipe-cooled, clustered-reactor system for lunar-surface power generation. The reactor is divided into subcritical units that can be safely launched with lunar shipments from Earth, and then emplaced directly into holes drilled into the lunar regolith to form a critical reactor assembly. The regolith would not just provide radiation shielding, but serve as neutron-reflector material as well. The reactor subunits are to be manufactured using proven and tested materials for use in radiation environments, such as uranium-dioxide fuel, stainless-steel cladding and structural support, and liquid-sodium heatpipes. The LEGO Reactor system promotes reliability, safety, and ease of manufacture and testing at the cost of an increase in launch mass per overall rated power level and a reduction in neutron economy when compared to a single-reactor system. A single unshielded LEGO Reactor subunit has an estimated mass of approximately 448 kg and provides approximately 5 kWe. The overall envelope for a single subunit with fully extended radiator panels has a height of 8.77 m and a diameter of 0.50 m. Six subunits could provide sufficient power generation throughout the initial stages of establishing a lunar outpost. Portions of the reactor may be neutronically decoupled to allow for reduced power production during unmanned periods of base operations. During later stages of lunar-base development, additional subunits may be emplaced and coupled into the existing LEGO Reactor network, subject to lunar base power demand. Improvements in reactor control methods, fuel form and matrix, shielding, as well as power conversion and heat rejection techniques can help generate an even more competitive LEGO Reactor design. Further modifications in the design could provide power generative opportunities for use on other extraterrestrial surfaces.

John Darrell Bess

2008-06-01T23:59:59.000Z

82

Parallel Reacting Flow Calculations for Chemical Vapor Deposition Reactor Design 1  

E-Print Network [OSTI]

National Laboratories Albuquerque, NM 87185­1111 (To be published in Proceedings of the International at the synthesis of two important research areas: 3D flow and transport modeling of reactors and the simulationParallel Reacting Flow Calculations for Chemical Vapor Deposition Reactor Design 1 Andrew G

Devine, Karen

83

Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396  

SciTech Connect (OSTI)

Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimize the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new perspective in the post Fukushima -accident era. Accidents at the Fukushima Daiichi reactors in the aftermath of the devastating earthquake and tsunami of March 11, 2011 have slowed down the nuclear renaissance world-wide and may have accelerated decommissioning either because some countries have decided to halt or reduce nuclear, or because the new safety requirements may reduce life-time extensions. Even in countries such as the UK and France that favor nuclear energy production existing nuclear sites are more likely to be chosen as sites for future NPPs. Even as the site recovery efforts continue at Fukushima and any decommissioning decisions are farther into the future, the accidents have focused attention on the reactor designs in general and specifically on the Fukushima type BWRs. The regulatory authorities in many countries have initiated a re-examination of the design of the systems, structures and components and considerations of the capability of the station to cope with beyond-design basis events. Enhancements to SSCs and site features for the existing reactors and the reactors that will be built will also impact the decommissioning phase activities. The newer reactor designs of today not only have enhanced safety features but also take into consideration the features that will facilitate future decommissioning. Lessons learned from past management and operation of reactors as well as the lessons from decommissioning are incorporated into the new designs. However, in the post-Fukushima era, the emphasis on beyond-design-basis capability may lead to significant changes in SSCs, which eventually will also have impact on the decommissioning phase. Additionally, where some countries decide to phase out the nuclear power, many reactors may enter the decommissioning phase in the coming decade. While the formal updating and expanding of existing guidance documents for accident cleanup and decommissioning would benefit by waiting until the Fukushima project has progressed sufficiently for that experience to be reliably interpreted, the development of structured on-li

Devgun, Jas S. [Nuclear Power Technologies, Sargent and Lundy LLC, Chicago, IL (United States); Laraia, Michele [private consultant, formerly from IAEA, Kolonitzgasse 10/2, 1030, Vienna (Austria); Pescatore, Claudio [OECD, Nuclear Energy Agency, Issy-les-Moulineaux, Paris (France); Dinner, Paul [International Atomic Energy Agency, Wagramerstrasse 5, A-1400 Vienna (Austria)

2012-07-01T23:59:59.000Z

84

Improved Design of Nuclear Reactor Control System | U.S. DOE Office of  

Office of Science (SC) Website

Improved Design of Nuclear Reactor Improved Design of Nuclear Reactor Control System Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff Archives SBIR/STTR Applications of Nuclear Science and Technology Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information » Spinoff Archives Improved Design of Nuclear Reactor Control System Print Text Size: A A A RSS Feeds FeedbackShare Page Application/instrumentation: Improved Design of Nuclear Reactor Control System Developed at: Oak Ridge National Laboratory, Holifield Radioactive Ion Beam Facility (HRIBF)

85

Conversion of methanol to light olefins on SAPO-34: kinetic modeling and reactor design  

E-Print Network [OSTI]

design of an MTO reactor, accounting for the strong exothermicity of the process. Multi-bed adiabatic and fluidized bed technologies show good potential for the industrial process for the conversion of methanol into olefins....

Al Wahabi, Saeed M. H.

2005-02-17T23:59:59.000Z

86

Design of Batch Tube Reactor 377 Applied Biochemistry and Biotechnology Vol. 9193, 2001  

E-Print Network [OSTI]

Design of Batch Tube Reactor 377 Applied Biochemistry and Biotechnology Vol. 91­93, 2001 Copyright Biochemistry and Biotechnology Vol. 91­93, 2001 pretreatment represents the most expensive single step

California at Riverside, University of

87

Reactor Design, Cold-Model Experiment and CFD Modeling for Chemical Looping Combustion  

Science Journals Connector (OSTI)

Chemical looping combustion (CLC) is an efficient, clean and...2...capture, and an interconnected fluidized bed is more appropriate solution for CLC. This paper aims to design a reactor system for CLC, carry out ...

Shaohua Zhang; Jinchen Ma; Xintao Hu…

2013-01-01T23:59:59.000Z

88

Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor  

E-Print Network [OSTI]

Molten salt is a promising coolant candidate for Advanced High Temperature Reactor (AHTR) Gen-IV designs. The low neutron absorption, high thermal capacity, chemical inertness, and high boiling point at low pressure of ...

Bean, Malcolm K.

2011-08-01T23:59:59.000Z

89

Power conversion system design for supercritical carbon dioxide cooled indirect cycle nuclear reactors  

E-Print Network [OSTI]

The supercritical carbon dioxide (S-CO?) cycle is a promising advanced power conversion cycle which couples nicely to many Generation IV nuclear reactors. This work investigates the power conversion system design and ...

Gibbs, Jonathan Paul

2008-01-01T23:59:59.000Z

90

Design, construction and evaluation of a facility for the simulation of fast reactor blankets  

E-Print Network [OSTI]

A facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by ...

Forbes, Ian Alexander

1970-01-01T23:59:59.000Z

91

Design of Slurry Bubble Column Reactors: Novel Technique for Optimum Catalyst Size Selection  

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

Slurry Bubble Column Reactors: Novel Technique Slurry Bubble Column Reactors: Novel Technique for Optimum Catalyst Size Selection Opportunity The Department of Energy's National Energy Technology Laboratory (NETL) is seeking licensing partners interested in implementing United States Patent Number 7,619,011 entitled "Design of Slurry Bubble Column Reactors: Novel Technique for Optimum Catalyst Size Selection." Disclosed in this patent is a method to determine the optimum catalyst particle size for application in a fluidized bed reactor, such as a slurry bubble column reactor (SBCR), to convert synthesis gas into liquid fuels. The reactor can be gas-solid, liquid- solid, or gas-liquid-solid. The method considers the complete granular temperature balance based on the kinetic theory of

92

Inertial Fusion Energy reactor design studies: Prometheus-L, Prometheus-H. Volume 2, Final report  

SciTech Connect (OSTI)

This report contains a review of design studies for Inertial Confinement reactor. This second of three volumes discussions is some detail the following: Objectives, requirements, and assumptions; rationale for design option selection; key technical issues and R&D requirements; and conceptual design selection and description.

Waganer, L.M.; Driemeyer, D.E.; Lee, V.D.

1992-03-01T23:59:59.000Z

93

Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors  

SciTech Connect (OSTI)

A boron carbide capsule has been designed and used for spectral-tailoring experiments at the TRIGA reactor at Washington State University. Irradiations were conducted in pulsed mode and in continuous operation for up to 4 hours. A cadmium cover was used to reduce thermal heating. The neutron spectrum calculated with MCNP was found to be in good agreement with reactor dosimetry measurements using the STAY'SL computer code. The neutron spectrum resembles that of a fast reactor. Design of a capsule using boron carbide enriched in {sup 10}B shows that it is possible to produce a neutron spectrum similar to {sup 235}U fission.

Greenwood, Lawrence R.; Wittman, Richard S.; Pierson, Bruce D.; Metz, Lori A.; Payne, Rosara F.; Finn, Erin C.; Friese, Judah I.

2012-03-01T23:59:59.000Z

94

11/04/02 G. W. Rubloff AVS 2002 MS MoA5 1 Spatially Programmable Reactor Design  

E-Print Network [OSTI]

optimization is constrained by fixed reactor design manufacturing #12;11/04/02 G. W. Rubloff ­ AVS 2002 ­ MS Mo spatial conditions in programmable reactor Uniformity unacceptable Produce high uniformity with optimal11/04/02 G. W. Rubloff ­ AVS 2002 ­ MS MoA5 1 Spatially Programmable Reactor Design: Toward a New

Rubloff, Gary W.

95

Design of a nuclear reactor system for lunar base applications  

E-Print Network [OSTI]

disadvantages. U02 and Pu02 fuels both have extremely poor ther mal conductivities, about 4 W/m K at 500 C, which would normally limit the maximum linear power in the reactor core to unacceptably low levels. For tunately, the ver y high melting temperatur es... conversion, however, high reactor exit temperatures are both necessary and desirable. The efficiency of the power conversion cycle is directly related to the difference between the high and low temperatur es in the system. Since the heat rejection...

Griffith, Richard Odell

2012-06-07T23:59:59.000Z

96

Seismic design technology for Breeder Reactor structures. Volume 3: special topics in reactor structures  

SciTech Connect (OSTI)

This volume is divided into six chapters: analysis techniques, equivalent damping values, probabilistic design factors, design verifications, equivalent response cycles for fatigue analysis, and seismic isolation. (JDB)

Reddy, D.P. (ed)

1983-04-01T23:59:59.000Z

97

Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor  

SciTech Connect (OSTI)

The Deep-Burn (DB) concept focuses on the destruction of transuranic nuclides from used light water reactor fuel. These transuranic nuclides are incorporated into TRISO coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes between passes. In particular, the concept does not call for reprocessing of the fuel between passes. In principle, the DB pebble bed concept employs the same reactor designs as the presently envisioned low-enriched uranium core designs, such as the 400 MWth Pebble Bed Modular Reactor (PBMR-400). Although it has been shown in the previous Fiscal Year (2009) that a PuO2 fueled pebble bed reactor concept is viable, achieving a high fuel burnup, while remaining within safety-imposed prescribed operational limits for fuel temperature, power peaking and temperature reactivity feedback coefficients for the entire temperature range, is challenging. The presence of the isotopes 239-Pu, 240-Pu and 241-Pu that have resonances in the thermal energy range significantly modifies the neutron thermal energy spectrum as compared to a ”standard,” UO2-fueled core. Therefore, the DB pebble bed core exhibits a relatively hard neutron energy spectrum. However, regions within the pebble bed that are near the graphite reflectors experience a locally softer spectrum. This can lead to power and temperature peaking in these regions. Furthermore, a shift of the thermal energy spectrum with increasing temperature can lead to increased absorption in the resonances of the fissile Pu isotopes. This can lead to a positive temperature reactivity coefficient for the graphite moderator under certain operating conditions. The effort of this task in FY 2010 has focused on the optimization of the core to maximize the pebble discharge burnup level, while retaining its inherent safety characteristics. Using generic pebble bed reactor cores, this task will perform physics calculations to evaluate the capabilities of the pebble bed reactor to perform utilization and destruction of LWR used-fuel transuranics. The task will use established benchmarked models, and will introduce modeling advancements appropriate to the nature of the fuel considered (high TRU content and high burn-up).

B. Boer; A. M. Ougouag

2010-09-01T23:59:59.000Z

98

Modular high temperature gas-cooled reactor plant design duty cycle. Revision 3  

SciTech Connect (OSTI)

This document defines the Plant Design Duty Cycle (PCDC) for the Modular High Temperature Gas-cooled Reactor (MHTGR). The duty cycle is a set of events and their design number of occurrences over the life of the plant for which the MHTGR plant shall be designed to ensure that the plant meets all the top-level requirements. The duty cycle is representative of the types of events to be expected in multiple reactor module-turbine plant configurations of the MHTGR. A synopsis of each PDDC event is presented to provide an overview of the plant response and consequence. 8 refs., 1 fig., 4 tabs.

Chan, T.

1989-12-31T23:59:59.000Z

99

Manhattan Project: Final Reactor Design and X-10, 1942-1943  

Office of Scientific and Technical Information (OSTI)

Schematic of the X-10 Graphite Reactor, Oak Ridge FINAL REACTOR DESIGN AND X-10 Schematic of the X-10 Graphite Reactor, Oak Ridge FINAL REACTOR DESIGN AND X-10 (Met Lab and Oak Ridge [Clinton], 1942-1943) Events > The Plutonium Path to the Bomb, 1942-1944 Production Reactor (Pile) Design, 1942 DuPont and Hanford, 1942 CP-1 Goes Critical, December 2, 1942 Seaborg and Plutonium Chemistry, 1942-1944 Final Reactor Design and X-10, 1942-1943 Hanford Becomes Operational, 1943-1944 Before any plutonium could be chemically separated from uranium for a bomb, however, that uranium would first have to be irradiated in a production pile. CP-1 had been a success as a scientific experiment, but the pile was built on such a small scale that recovering any significant amounts of plutonium from it was impractical. In the fall of 1942, scientists of the Met Lab had decided to build a second Fermi pile at Argonne as soon as his experiments on the first were completed and to proceed with the "Mae West" design for a helium-cooled production pile as well. When DuPont engineers assessed the Met Lab's plans in the late fall, they agreed that helium should be given first priority. They placed heavy water second and urged an all-out effort to produce more of this highly effective moderator. Bismuth and water were ranked third and fourth in DuPont's analysis. Priorities began to change when Enrico Fermi's CP-1 calculations demonstrated a higher value for the neutron reproduction factor k (for a theoretical reactor of infinite size) than anyone had anticipated. Met Lab scientists concluded that a water-cooled pile was now feasible. Crawford Greenewalt, head of the DuPont effort, continued, however, to support helium cooling.

100

Material Control and Accounting Design Considerations for High-Temperature Gas Reactors  

SciTech Connect (OSTI)

The subject of this report is domestic safeguards and security by design (2SBD) for high-temperature gas reactors, focusing on material control and accountability (MC&A). The motivation for the report is to provide 2SBD support to the Next Generation Nuclear Plant (NGNP) project, which was launched by Congress in 2005. This introductory section will provide some background on the NGNP project and an overview of the 2SBD concept. The remaining chapters focus specifically on design aspects of the candidate high-temperature gas reactors (HTGRs) relevant to MC&A, Nuclear Regulatory Commission (NRC) requirements, and proposed MC&A approaches for the two major HTGR reactor types: pebble bed and prismatic. Of the prismatic type, two candidates are under consideration: (1) GA's GT-MHR (Gas Turbine-Modular Helium Reactor), and (2) the Modular High-Temperature Reactor (M-HTR), a derivative of Areva's Antares reactor. The future of the pebble-bed modular reactor (PBMR) for NGNP is uncertain, as the PBMR consortium partners (Westinghouse, PBMR [Pty] and The Shaw Group) were unable to agree on the path forward for NGNP during 2010. However, during the technology assessment of the conceptual design phase (Phase 1) of the NGNP project, AREVA provided design information and technology assessment of their pebble bed fueled plant design called the HTR-Module concept. AREVA does not intend to pursue this design for NGNP, preferring instead a modular reactor based on the prismatic Antares concept. Since MC&A relevant design information is available for both pebble concepts, the pebble-bed HTGRs considered in this report are: (1) Westinghouse PBMR; and (2) AREVA HTR-Module. The DOE Office of Nuclear Energy (DOE-NE) sponsors the Fuel Cycle Research and Development program (FCR&D), which contains an element specifically focused on the domestic (or state) aspects of SBD. This Material Protection, Control and Accountancy Technology (MPACT) program supports the present work summarized in this report, namely the development of guidance to support the consideration of MC&A in the design of both pebble-bed and prismatic-fueled HTGRs. The objective is to identify and incorporate design features into the facility design that will cost effectively aid in making MC&A more effective and efficient, with minimum impact on operations. The theft of nuclear material is addressed through both MC&A and physical protection, while the threat of sabotage is addressed principally through physical protection.

Trond Bjornard; John Hockert

2011-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Use of sensitivity and uncertainty analysis in reactor design verification Part II: Flux measurement analysis  

Science Journals Connector (OSTI)

Abstract As for any new reactor design, the ACR-1000® design has to go through a comprehensive design verification process. One of the activities for supporting the ACR physics design calculations using the ACR physics code toolset, namely WIMS-AECL/DRAGON/RFSP, is to compare the flux distributions resulting from the calculation using this toolset at various power calibration monitor (PCM) detector locations against the flux measurement data from the Japanese Advanced Thermal Reactor (ATR) FUGEN. The discussion of this particular design verification exercise will be presented in a two-part paper. The usage of data from the FUGEN reactor qualifies this exercise as design verification by alternate analysis. In order to have meaningful results at the end of the design verification process, the similarity between the ACR-1000 and FUGEN reactors has to be demonstrated. It is accomplished through the sensitivity and uncertainty analysis using the TSUNAMI (Tools for Sensitivity and Uncertainty Analysis Methodology Implementation) methodology. The results from the similarity comparison have been presented in Part I of the paper. In Part II, results from flux distribution comparison will be presented. Favourable results from this design verification exercise give a high level of confidence that using the same physics toolset in calculating the flux distribution for ACR-1000 reactor will produce results with acceptable fidelity. In addition, the results will also give an indication of expected margins in the design calculations, not only at the locations of the PCM detectors but also at the derived bundle and channel powers obtained through the flux mapping calculation.

Doddy Kastanya; Mohamed Dahmani

2013-01-01T23:59:59.000Z

102

Microsoft Word - 3b - Basis for Reactor Design comments 081710...  

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

on the demonstration power plant core design developed earlier by PBMR (Ltd) of South Africa, includes a direct Brayton cycle gas turbine for electricity production. The...

103

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor  

SciTech Connect (OSTI)

The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

2010-09-01T23:59:59.000Z

104

Strategic planning for LEED certification  

E-Print Network [OSTI]

Intel Corporation has recently implemented a "green building" policy, which states that Intel will design all new facilities to achieve a minimum LEED-Silver certification. LEED (Leadership in Energy and Environmental ...

Capuzzi, Angelo Michael

2010-01-01T23:59:59.000Z

105

Recommended practices in elevated temperature design: A compendium of breeder reactor experiences (1970-1986): An overview  

SciTech Connect (OSTI)

Significant experiences have been accumulated in the establishment of design methods and criteria applicable to the design of Liquid Metal Fast Breeder Reactor (LMFBR) components. The Subcommittee of the Elevated Temperature Design under the Pressure Vessel Research Council (PVRC) has undertaken to collect, on an international basis, design experience gained, and the lessons learned, to provide guidelines for next generation advanced reactor designs. This paper shall present an overview and describe the highlights of the work.

Wei, B.C.; Cooper, W.L. Jr.; Dhalla, A.K.

1987-09-01T23:59:59.000Z

106

Energy Department Issues Green Building Certification System...  

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

Department Issues Green Building Certification System Final Rule to Support Increased Energy Measurement and Efficient Building Design Energy Department Issues Green Building...

107

Initial Design of a Dual Fluidized Bed Reactor  

E-Print Network [OSTI]

fluidized bed gaisifers (CFB) (Figure 1.6) 1.3.1. Bubblingbed gasifiers (BFB and CFB) have great features for SH.employed for the SHR design. CFB enables a circulation of

Yun, Minyoung

2014-01-01T23:59:59.000Z

108

Modularity in design of the MIT Pebble Bed Reactor  

E-Print Network [OSTI]

The future of new nuclear power plant construction will depend in large part on the ability of designers to reduce capital, operations, and maintenance costs. One of the methods proposed, is to enhance the modularity of ...

Berte, Marc Vincent, 1977-

2004-01-01T23:59:59.000Z

109

Design, Fabrication, and Certification of Advanced Modular PV Power Systems Final Technical Progress Report  

SciTech Connect (OSTI)

This report describes the overall accomplishments and benefits of Solar Electric Specialties Co. (SES) under this Photovoltaic Manufacturing Technology (PVMaT) subcontract. SES addressed design issues related to their modular autonomous PV power supply (MAPPS) and a mobile photogenset. MAPPS investigations included gel-cell batteries mounted horizontally; redesign of the SES power supply; modified battery enclosure for increased safety and reduced cost; programmable, interactive battery charge controllers; and UL and FM listings. The photogenset systems incorporate generators, battery storage, and PV panels for a mobile power supply. The unit includes automatic oil-change systems for the propane generators, collapsible array mounts for the PV enclosure, and internal stowage of the arrays. Standardizing the products resulted in product lines of MAPPS and Photogensets that can be produced more economically and with shorter lead times, while increasing product quality and reliability. Product assembly and quality control have also been improved and streamlined with the development of standardized assembly processes and QC testing procedures. SES offers the UL-listed MAPPS at about the same price as its previous non-standardized, unlisted products.

Lambarski, T.; Minyard, G. (Solar Electric Specialties Co., Willits, California)

1998-10-06T23:59:59.000Z

110

Design and Status of RERTR Irradiation Tests in the Advanced Test Reactor  

SciTech Connect (OSTI)

Irradiation testing of U-Mo based fuels is the central component of the Reduced Enrichment for Research and Test Reactors (RERTR) program fuel qualification plan. Several RERTR tests have recently been completed or are planned for irradiation in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory in Idaho Falls, ID. Four mini-plate experiments in various stages of completion are described in detail, including the irradiation test design, objectives, and irradiation conditions. Observations made during and after the in-reactor RERTR-7A experiment breach are summarized. The irradiation experiment design and planned irradiation conditions for full-size plate test are described. Progress toward element testing will be reviewed.

Daniel M. Wachs; Richard G. Ambrosek; Gray Chang; Mitchell K. Meyer

2006-10-01T23:59:59.000Z

111

Shielding design aspects of thermionic space nuclear reactors  

SciTech Connect (OSTI)

It has been well documented that nuclear power sources will be required for the future exploration of space. Higher power levels (>10 kW (electric)) will be enabling, if not absolutely necessary, for the continued expansion of a human presence in the solar system and beyond. Space missions that will directly benefit continued life on Earth, including the monitoring for climate change and global warming, high-capacity communication satellites, and large, space-based radar systems to monitor the flow of airline traffic, will require progressively larger amounts of electrical power. Military applications, even with the ending of the Cold War, will continue to be needed for treaty verification activities. A thermionic energy conversion-based nuclear reactor system is one of the many different technologies proposed for the utilization of nuclear energy in space. How the energy conversion is accomplished and the equipment requiring shielding have a profound effect on the overall shielding requirements for the system. There exist two configurations of this technology that can be exploited and will have a significant effect on shielding needs. The paper discusses in-core thermionic conversion and out-of-core conversion concepts.

Klein, A.C.

1991-01-01T23:59:59.000Z

112

High-temperature gas-cooled-reactor steam-methane reformer design  

SciTech Connect (OSTI)

The concept of the long distance transportation of process heat energy from a High Temperature Gas Cooled Reactor (HTGR) heat source, based on the steam reforming reaction, is currently being evaluated as an energy source/application for use early in the 21st century. The steam-methane reforming reaction is an endothermic reaction at temperatures approximately 700/sup 0/C and higher, which produces hydrogen, carbon monoxide and carbon dioxide. The heat of the reaction products can then be released, after being pumped to industrial site users, in a methanation process producing superheated steam and methane which is then returned to the reactor plant site. In this application the steam reforming reaction temperatures are produced by the heat energy from the core of the HTGR through forced convection of the primary or secondary helium circuit to the catalytic chemical reactor (steam reformer). This paper summarizes the design of a helium heated steam reformer utilized in conjunction with a 1170 MW(t) intermediate loop, 850/sup 0/C reactor outlet temperature, HTGR process heat plant concept. This paper also discusses various design considerations leading to the mechanical design features, the thermochemical performance, materials selection and the structural design analysis.

Impellezzeri, J.R.; Drendel, D.B.; Odegaard, T.K.

1981-01-20T23:59:59.000Z

113

Design Aspects of Hybrid Adsorbent?Membrane Reactors for Hydrogen Production  

Science Journals Connector (OSTI)

Design Aspects of Hybrid Adsorbent?Membrane Reactors for Hydrogen Production ... For hydrogen to replace fossil fuels as the fuel of choice for mobile applications, it will require the creation of a production and delivery infrastructure equivalent to those that currently exist for fossil fuels. ...

Babak Fayyaz; Aadesh Harale; Byoung-Gi Park; Paul K. T. Liu; Muhammad Sahimi; Theodore T. Tsotsis

2005-05-14T23:59:59.000Z

114

Spring design for use in the core of a nuclear reactor  

DOE Patents [OSTI]

A spring design particularly suitable for use in the core of a nuclear reactor includes one surface having a first material oriented in a longitudinal direction, and another surface having a second material oriented in a transverse direction. The respective surfaces exhibit different amounts of irraditation induced strain.

Willard, Jr., H. James (Bethel Park, PA)

1993-01-01T23:59:59.000Z

115

Plasma engineering design of a compact reversed-field pinch reactor (CRFPR)  

SciTech Connect (OSTI)

The rationale for and the characteristics of the high-power-density Compact Reversed-Field Pinch Reactor (CRFPR) are discussed. Particular emphasis is given to key plasma engineering aspects of the conceptual design, including plasma operations, current drive, and impurity/ash control by means of pumped limiters or magnetic divertors. A brief description of the Fusion-Power-Core integration is given.

Bathke, C.G.; Embrechts, M.J.; Hagenson, R.L.; Krakowski, R.A.; Miller, R.L.

1983-01-01T23:59:59.000Z

116

11/04/02 G. W. Rubloff AVS 2002 MS MoA5 1 Spatially Programmable Reactor Design  

E-Print Network [OSTI]

) reactor design · Process change impacts (often degrades) uniformity · Process optimization is constrained11/04/02 G. W. Rubloff ­ AVS 2002 ­ MS MoA5 1 Spatially Programmable Reactor Design: Toward a New recipe logic and timingProcess optimization requiresProcess optimization requires tradeoffs between

Rubloff, Gary W.

117

Compliance Certification Application  

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

40 CFR Part 191 40 CFR Part 191 Compliance Certification Application for the Waste Isolation Pilot Plant Appendix PIC United States Department of Energy Waste Isolation Pilot Plant Carlsbad Area Office Carlsbad, New Mexico Passive Institutional Controls Conceptual Design Report PASSIVE INSTITUTIONAL CONTROLS CONCEPTUAL DESIGN REPORT REVISION 0 MAY 14, 1996 1 C PASSIVE INSTITUTIONAL CONTROLS DESIGN REPORT REVISION 0 PASSIVE INSTITUTIONAL CONTROLS CONCEPTUAL DESIGN REPORT MAY 1 4 . 1 9 9 6 TABLE OF CONTENTS INTRODUCTION . . . . . . . . . . . . . . . . . . . . 1 A . Purpose . . . . . . . . . . . . . . . . . . . 1 B . Scope . . . . . . . . . . . . . . . . . . . . . 3 C . Background . . . . . . . . . . . . . . . . . . . 7 I1 . SITE DESCRIPTION . . . . . . . . . . . . . . . . . 11 I11 . DESIGN REQUIREMENTS/CRITERIA . . . . . . . . . . 17 IV . MESSAGES . . . . . . . . . . . . . . . . . .

118

Space power reactor in-core thermionic multicell evolutionary (S-prime) design  

SciTech Connect (OSTI)

A 5- to 40-kWe moderated in-core thermionic space nuclear power system (TI-SNPS) concept was developed to address the TI-SNPS program requirements. The 40-kWe baseline design uses multicell Thermionic Fuel Elements (TFEs) in a zirconium hydride moderated reactor to achieve a specific mass of 18.2 We/kg and a net end-of-mission (EOM) efficiency of 8.2%. The reactor is cooled with a single NaK-78 pumped loop, which rejects the heat through a 24 m[sup 2] heat pipe space radiator.

Determan, W.R. (Rocketdyne Division, Rockwell International, 6633 Canoga Avenue, P.O. Box 7922, anoga Park, California 91309-7922 (United States)); Van Hagan, T.H. (General Atomics, P.O. Box 85608, San Diego, California 92186-9784 (United States))

1993-01-20T23:59:59.000Z

119

Secondary heat exchanger design and comparison for advanced high temperature reactor  

SciTech Connect (OSTI)

Next generation nuclear reactors such as the advanced high temperature reactor (AHTR) are designed to increase energy efficiency in the production of electricity and provide high temperature heat for industrial processes. The efficient transfer of energy for industrial applications depends on the ability to incorporate effective heat exchangers between the nuclear heat transport system and the industrial process heat transport system. This study considers two different types of heat exchangers - helical coiled heat exchanger and printed circuit heat exchanger - as possible options for the AHTR secondary heat exchangers with distributed load analysis and comparison. Comparison is provided for all different cases along with challenges and recommendations. (authors)

Sabharwall, P. [Idaho National Laboratory, Idaho Falls, ID 83415-3860 (United States); Kim, E. S. [Seoul National Univ., P.O. Box 1625, Idaho Falls, ID 83415-3860 (United States); Siahpush, A.; McKellar, M.; Patterson, M. [Idaho National Laboratory, Idaho Falls, ID 83415-3860 (United States)

2012-07-01T23:59:59.000Z

120

Fuel performance models for high-temperature gas-cooled reactor core design  

SciTech Connect (OSTI)

Mechanistic fuel performance models are used in high-temperature gas-cooled reactor core design and licensing to predict failure and fission product release. Fuel particles manufactured with defective or missing SiC, IPyC, or fuel dispersion in the buffer fail at a level of less than 5 x 10/sup -4/ fraction. These failed particles primarily release metallic fission products because the OPyC remains intact on 90% of the particles and retains gaseous isotopes. The predicted failure of particles using performance models appears to be conservative relative to operating reactor experience.

Stansfield, O.M.; Simon, W.A.; Baxter, A.M.

1983-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" from the National Library of EnergyBeta (NLEBeta).
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121

Thermal analysis and design of a passive reflux condenser for the simplified boiling water reactor  

SciTech Connect (OSTI)

At present, the advanced light water reactors (ALWRS) in the United States are being designed to remove reactor decay heat for a period of 72 h following a postulated loss-of-coolant accident (LOCA). The water in the pools external to the containment is evaporated or boiled off to remove the decay heat. It is presumed that the water in the pools can be replenished within 72 h through operator actions or outside assistance. Some countries in Europe require that the plant be designed to remove the reactor decay heat for a much longer duration than 72 h without external assistance. This paper presents an analysis and design of a passive heat exchanger called a reflux condenser (RC), which was considered for an ALWR-the 600-MW(electric) simplified boiling water reactor. The RC is required to condense the steam formed when the water in the pool in which the passive containment cooling system (PCCS) is immersed boils following a LOCA. The RCs are nuclear non-safety related. This paper presents steady-state performance of an RC at various outdoor air dry-bulb temperatures under still air conditions.

Bijlani, C.; Patti, F. (Burns Roe Inc., Oradell, NJ (United States)); Prasad, V. (SUNY, Stony Brook, NY (United States))

1993-01-01T23:59:59.000Z

122

Presentation of NNSA Certificates to the Argonne RAP Team  

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

Presentation of NNSA Certificates to Argonne's RAP Team 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 Presentation of NNSA Certificates to Argonne's RAP Team Group photo taken during the presentation of the Letter of Appreciation Pictured in photo left to right: R. Klann (NE), F. Moore (NE), S.

123

SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts  

SciTech Connect (OSTI)

Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950's and 1960's in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with supercritical water (SCW) became attractive again as the ultimate development path for water-cooling. The main objectives of using SCW in nuclear reactors are 1) to increase the thermal efficiency of modern nuclear power plants (NPPs) from 33 -- 35% to about 40 -- 45%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs ({approx}$ 1000 US/kW). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625 deg. C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia. Design features related to both channels and fuel bundles are discussed in this paper. Also, Russian experience with operating supercritical steam heaters at NPP is presented. The main conclusion is that development of SCW pressure-channel nuclear reactors is feasible and significant benefits can be expected over other thermal energy systems. (authors)

Duffey, R.B.; Pioro, I.L. [Atomic Energy of Canada, Ltd. (Canada); Gabaraev, B.A.; Kuznetsov, Yu. N. [Research and Development Institute of Power Engineering, ul.M. Krasnoselskaya, 2/8 Moscow, Moscow 107140 (Russian Federation)

2006-07-01T23:59:59.000Z

124

ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs  

SciTech Connect (OSTI)

Cross-section libraries for the ORIGEN-ARP system were extended to include four non-U.S. reactor types: the Magnox reactor, the Advanced Gas-Cooled Reactor, the VVER-440, and the VVER-1000. Typical design and operational parameters for these four reactor types were determined by an examination of a variety of published information sources. Burnup simulation models of the reactors were then developed using the SAS2H sequence from the Oak Ridge National Laboratory SCALE code system. In turn, these models were used to prepare the burnup-dependent cross-section libraries suitable for use with ORIGEN-ARP. The reactor designs together with the development of the SAS2H models are described, and a small number of validation results using spent-fuel assay data are reported.

Murphy, BD

2004-03-10T23:59:59.000Z

125

Chapter 1 - Reactor configurations and design parameters for thermochemical conversion of biomass into fuels, energy, and chemicals  

Science Journals Connector (OSTI)

Abstract This chapter describes reactors for thermochemical conversion of lignocellulosic biomass into fuels, energy, and chemicals. The chapter covers basic definitions and concepts involved in biofuels and thermochemical conversion of biomass, and it also includes more advanced topics such as the main reactor configurations currently in use for thermochemical technologies, important parameters for reactor design, discussion of how parameters affect reactor performance, and several examples and case studies. The focus is on fast pyrolysis and gasification systems. The topics discussed include energy and carbon efficiencies, convenience of operation and scale-up, and several other parameters related to reactor design. After reading this chapter, the reader will understand the main characteristics of reactors for thermochemical conversion of biomass, their strengths, and their weaknesses for specific applications.

Fernando L.P. Resende

2014-01-01T23:59:59.000Z

126

Design and operation of a rotating drum radio frequency plasma reactor for the modification of free nanoparticles  

SciTech Connect (OSTI)

A rotating drum rf plasma reactor was designed to functionalize the surface of nanoparticles and other unusually shaped substrates through plasma polymerization and surface modification. This proof-of-concept reactor design utilizes plasma polymerized allyl alcohol to add OH functionality to Fe{sub 2}O{sub 3} nanoparticles. The reactor design is adaptable to current plasma hardware, eliminating the need for an independent reactor setup. Plasma polymerization performed on Si wafers, Fe{sub 2}O{sub 3} nanoparticles supported on Si wafers, and freely rotating Fe{sub 2}O{sub 3} nanoparticles demonstrated the utility of the reactor for a multitude of processes. X-ray photoelectron spectroscopy and Fourier transform infrared spectroscopy were used to characterize the surface of the substrates prior to and after plasma deposition, and scanning electron microscopy was used to verify that no extensive change in the size or shape of the nanoparticles occurred because of the rotating motion of the reactor. The reactor design was also extended to a non-depositing NH{sub 3} plasma modification system to demonstrate the reactor design is effective for multiple plasma processes.

Shearer, Jeffrey C.; Fisher, Ellen R. [Department of Chemistry, Colorado State University, Fort Collins, Colorado 80523-1872 (United States)

2013-06-15T23:59:59.000Z

127

DESIGN OF A TOKAMAK FUSION REACTOR FIRST WALL ARMOR AGAINST NEUTRAL BEAM IMPINGEMENT  

E-Print Network [OSTI]

Hoffman, et. a1. , "Fusion Reactor First Wall Cooling forTheir Signif- icance in Fusion Reactors," Fifth ConferenceProb- lems in Toroidal Fusion Reactors," Fifth Conference

Myers, Richard Allen

2011-01-01T23:59:59.000Z

128

High Temperature Gas-Cooled Reactor Program. Modular HTGR systems design and cost summary. [Methane reforming; steam cycle-cogeneration  

SciTech Connect (OSTI)

This report provides a summary description of the preconceptual design and energy product costs of the modular High Temperature Gas-Cooled Reactor (HTGR). The reactor system was studied for two applications: (1) reforming of methane to produce synthesis gas and (2) steam cycle/cogeneration to produce process steam and electricity.

Not Available

1983-09-01T23:59:59.000Z

129

Heat exchanger design considerations for high temperature gas-cooled reactor (HTGR) plants  

SciTech Connect (OSTI)

Various aspects of the high-temperature heat exchanger conceptual designs for the gas turbine (HTGR-GT) and process heat (HTGR-PH) plants are discussed. Topics include technology background, heat exchanger types, surface geometry, thermal sizing, performance, material selection, mechanical design, fabrication, and the systems-related impact of installation and integration of the units in the prestressed concrete reactor vessel. The impact of future technology developments, such as the utilization of nonmetallic materials and advanced heat exchanger surface geometries and methods of construction, is also discussed.

McDonald, C.F.; Vrable, D.L.; Van Hagan, T.H.; King, J.H.; Spring, A.H.

1980-02-01T23:59:59.000Z

130

A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design  

SciTech Connect (OSTI)

Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling and radiation damage in high burnup fuel. Such fuels use a manufacturing process in which fuel particles are encapsulated within a non-fuel matrix. Dispersion fuels have been studied since 1997 as part of an international effort to develop and test very high density fuel types for the Reduced Enrichment for Research and Test Reactors (RERTR) program.[1] The Idaho National Laboratory is performing research in the development of an innovative dispersion fuel concept that will meet the challenges of transuranic (TRU) transmutation by providing an integral fission gas plenum within the fuel itself, to eliminate the swelling that accompanies the irradiation of TRU. In this process, a metal TRU vector produced in a separations process is atomized into solid microspheres. The dispersion fuel process overcoats the microspheres with a mixture of resin and hollow carbon microspheres to create a TRUC. The foam may then be heated and mixed with a metal power (e.g., Zr, Ti, or Si) and resin to form a matrix metal carbide, that may be compacted and extruded into fuel elements. In this paper, we perform reactor physics calculations for a core loaded with the conceptual fuel design. We will assume a “typical” TRU vector and a reference matrix density. We will employ a fuel and core design based on the Advanced Burner Test Reactor (ABTR) design.[2] Using the CSAS6 and TRITON modules of the SCALE system [3] for preliminary scoping studies, we will demonstrate the feasibility of reactor operations. This paper will describe the results of these analyses.

Mark DeHart; Hongbin Zhang; Eric Shaber; Matthew Jesse

2010-11-01T23:59:59.000Z

131

Contract Management Certificate Program  

E-Print Network [OSTI]

Contract Management Certificate Program Accelerate Your Career BusinessandManagement extension bearing the UC seal signifies a well- known, uncompromising standard of academic excellence. #12;Contract Management Certificate Program UC Irvine Extension's Contract Management Certificate Program focuses on core

Rose, Michael R.

132

Analysis of Reference Design for Nuclear-Assisted Hydrogen Production at 750°C Reactor Outlet Temperature  

SciTech Connect (OSTI)

The use of High Temperature Electrolysis (HTE) for the efficient production of hydrogen without the greenhouse gas emissions associated with conventional fossil-fuel hydrogen production techniques has been under investigation at the Idaho National Engineering Laboratory (INL) for the last several years. The activities at the INL have included the development, testing and analysis of large numbers of solid oxide electrolysis cells, and the analyses of potential plant designs for large scale production of hydrogen using a high-temperature gas-cooled reactor (HTGR) to provide the process heat and electricity to drive the electrolysis process. The results of this research led to the selection in 2009 of HTE as the preferred concept in the U.S. Department of Energy (DOE) hydrogen technology down-selection process. However, the down-selection process, along with continued technical assessments at the INL, has resulted in a number of proposed modifications and refinements to improve the original INL reference HTE design. These modifications include changes in plant configuration, operating conditions and individual component designs. This report describes the resulting new INL reference design coupled to two alternative HTGR power conversion systems, a Steam Rankine Cycle and a Combined Cycle (a Helium Brayton Cycle with a Steam Rankine Bottoming Cycle). Results of system analyses performed to optimize the design and to determine required plant performance and operating conditions when coupled to the two different power cycles are also presented. A 600 MWt high temperature gas reactor coupled with a Rankine steam power cycle at a thermal efficiency of 44.4% can produce 1.85 kg/s of hydrogen and 14.6 kg/s of oxygen. The same capacity reactor coupled with a combined cycle at a thermal efficiency of 42.5% can produce 1.78 kg/s of hydrogen and 14.0 kg/s of oxygen.

Michael G. McKellar; Edwin A. Harvego

2010-05-01T23:59:59.000Z

133

The Treatment of Renewable Energy Certificates, Emissions Allowances, and Green Power Programs in State Renewables Portfolio Standards  

E-Print Network [OSTI]

Holt. 2004. “Design Guide for Renewable Energy Certificate2005. “Emerging Markets for Renewable Energy Certificates:Golden, CO: National Renewable Energy Laboratory. http://

Holt, Edward A.; Wiser, Ryan H.

2007-01-01T23:59:59.000Z

134

Advanced Core Design And Fuel Management For Pebble-Bed Reactors  

SciTech Connect (OSTI)

A method for designing and optimizing recirculating pebble-bed reactor cores is presented. At the heart of the method is a new reactor physics computer code, PEBBED, which accurately and efficiently computes the neutronic and material properties of the asymptotic (equilibrium) fuel cycle. This core state is shown to be unique for a given core geometry, power level, discharge burnup, and fuel circulation policy. Fuel circulation in the pebble-bed can be described in terms of a few well?defined parameters and expressed as a recirculation matrix. The implementation of a few heat?transfer relations suitable for high-temperature gas-cooled reactors allows for the rapid estimation of thermal properties critical for safe operation. Thus, modeling and design optimization of a given pebble-bed core can be performed quickly and efficiently via the manipulation of a limited number key parameters. Automation of the optimization process is achieved by manipulation of these parameters using a genetic algorithm. The end result is an economical, passively safe, proliferation-resistant nuclear power plant.

Hans D. Gougar; Abderrafi M. Ougouag; William K. Terry

2004-10-01T23:59:59.000Z

135

Design and analysis of megawatt-class heat-pipe reactor concepts  

SciTech Connect (OSTI)

There is growing interest in finding an alternative to diesel-powered systems at locations removed from a reliable electrical grid. One promising option is a 1- to 10-MW mobile reactor system, that could provide robust, self-contained, and long-term ({>=} 5 years) power in any environment. The reactor and required infrastructure could be transported to any location within one or a few standard transport containers. Heat pipe reactors, using alkali metal heat pipes, are perfectly suited for mobile applications because their nature is inherently simpler, smaller, and more reliable than 'traditional' reactors that rely on pumped coolant through the core. This paper examines a heat pipe reactor that is fabricated and shipped as six identical core segments. Each core segment includes a heat-pipe-to-gas heat exchanger that is coupled to the condenser end of the heat pipes. The reference power conversion system is a CO{sub 2}-Brayton system. The segments by themselves are deeply subcritical during transport, and they would be locked into an operating configuration (with control inserted) at the final destination. Two design options are considered: a near-term option and an advanced option. The near-term option is a 5-MWt concept that uses uranium-dioxide fuel, a stainless-steel structure, and potassium as the heat-pipe working fluid. The advanced option is a 15-MWt concept that uses uranium-nitride fuel, a molybdenum/TZM structure, and sodium as the heat-pipe working fluid. The materials used in the advanced option allow for higher temperatures and power densities, and enhanced power throughput in the heat pipes. Higher powers can be obtained from both concepts by increasing the core size and the number of heat pipes. (authors)

Poston, D.; Kapernick, R. [Los Alamos National Laboratory, MS C921, Los Alamos, NM 87545 (United States)

2012-07-01T23:59:59.000Z

136

Conceptual design of fast-ignition laser fusion reactor FALCON-D  

Science Journals Connector (OSTI)

A new conceptual design of the laser fusion power plant FALCON-D (Fast-ignition Advanced Laser fusion reactor CONcept with a Dry wall chamber) has been proposed. The fast-ignition method can achieve sufficient fusion gain for a commercial operation (~100) with about 10 times smaller fusion yield than the conventional central ignition method. FALCON-D makes full use of this property and aims at designing with a compact dry wall chamber (5–6?m radius). 1D/2D simulations by hydrodynamic codes showed a possibility of achieving sufficient gain with a laser energy of 400?kJ, i.e. a 40?MJ target yield. The design feasibility of the compact dry wall chamber and the solid breeder blanket system was shown through thermomechanical analysis of the dry wall and neutronics analysis of the blanket system. Moderate electric output (~400?MWe) can be achieved with a high repetition (30?Hz) laser. This dry wall reactor concept not only reduces several difficulties associated with a liquid wall system but also enables a simple cask maintenance method for the replacement of the blanket system, which can shorten the maintenance period. The basic idea of the maintenance method for the final optics system has also been proposed. Some critical R&D issues required for this design are also discussed.

T. Goto; Y. Someya; Y. Ogawa; R. Hiwatari; Y. Asaoka; K Okano; A. Sunahara; T. Johzaki

2009-01-01T23:59:59.000Z

137

Westinghouse Small Modular Reactor balance of plant and supporting systems design  

SciTech Connect (OSTI)

The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the second in a series of four papers which describe the design and functionality of the Westinghouse SMR. It focuses, in particular, upon the supporting systems and the balance of plant (BOP) designs of the Westinghouse SMR. Several Westinghouse SMR systems are classified as safety, and are critical to the safe operation of the Westinghouse SMR. These include the protection and monitoring system (PMS), the passive core cooling system (PXS), and the spent fuel cooling system (SFS) including pools, valves, and piping. The Westinghouse SMR safety related systems include the instrumentation and controls (I and C) as well as redundant and physically separated safety trains with batteries, electrical systems, and switch gears. Several other incorporated systems are non-safety related, but provide functions for plant operations including defense-in-depth functions. These include the chemical volume control system (CVS), heating, ventilation and cooling (HVAC) systems, component cooling water system (CCS), normal residual heat removal system (RNS) and service water system (SWS). The integrated performance of the safety-related and non-safety related systems ensures the safe and efficient operation of the Westinghouse SMR through various conditions and transients. The turbine island consists of the turbine, electric generator, feedwater and steam systems, moisture separation systems, and the condensers. The BOP is designed to minimize assembly time, shipping challenges, and on-site testing requirements for all structures, systems, and components. (authors)

Memmott, M. J.; Stansbury, C.; Taylor, C. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

2012-07-01T23:59:59.000Z

138

Core and System Design of Reduced-Moderation Water Reactor with Passive Safety Features  

SciTech Connect (OSTI)

In order to ensure the sustainable energy supply in Japan, research and developments of reduced-moderation water reactor (RMWR) have been performed. The RMWR can attain the favorable characteristics such as high burn-up, long operation cycle, multiple recycling of plutonium and effective utilization of uranium resources, based on the matured LWR technologies. MOX fuel assemblies in the tight-lattice fuel rod arrangement are used to reduce the moderation of neutron, and hence, to increase the conversion ratio. The conceptual design has been accomplished for the small 330 MWe RMWR core with the discharge burn-up of 60 GWd/t and the operation cycle of 24 months, under the natural circulation cooling of the core. A breeding ratio of 1.01 and the negative void reactivity coefficient are simultaneously realized in the design. In the plant system design, the passive safety features are intended to be utilized mainly to improve the economy. At present, a hybrid one under the combination of the passive and the active components, and a fully passive one are proposed. The former has been evaluated to reduce the cost for the reactor components. (authors)

Iwamura, Takamichi; Okubo, Tsutomu; Yonomoto, Taisuke [Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195 (Japan); Takeda, Renzo; Moriya, Kumiaki [Hitachi, Ltd. (Japan); Kanno, Minoru [The Japan Atomic Power Company (Japan)

2002-07-01T23:59:59.000Z

139

Ultracold neutron source at the PULSTAR reactor: Engineering design and cryogenic testing  

Science Journals Connector (OSTI)

Abstract Construction is completed and commissioning is in progress for an ultracold neutron (UCN) source at the PULSTAR reactor on the campus of North Carolina State University. The source utilizes two stages of neutron moderation, one in heavy water at room temperature and the other in solid methane at ~ 40 K , followed by a converter stage, solid deuterium at 5 K, that allows a single down scattering of cold neutrons to provide UCN. The UCN source rolls into the thermal column enclosure of the PULSTAR reactor, where neutrons will be delivered from a bare face of the reactor core by streaming through a graphite-lined assembly. The source infrastructure, i.e., graphite-lined assembly, heavy-water system, gas handling system, and helium liquefier cooling system, has been tested and all systems operate as predicted. The research program being considered for the PULSTAR UCN source includes the physics of UCN production, fundamental particle physics, and material surface studies of nanolayers containing hydrogen. In the present paper we report details of the engineering and cryogenic design of the facility as well as results of critical commissioning tests without neutrons.

E. Korobkina; G. Medlin; B. Wehring; A.I. Hawari; P.R. Huffman; A.R. Young; B. Beaumont; G. Palmquist

2014-01-01T23:59:59.000Z

140

Steady state temperature profiles in two simulated liquid metal reactor fuel assemblies with identical design specifications  

SciTech Connect (OSTI)

Temperature data from steady state tests in two parallel, simulated liquid metal reactor fuel assemblies with identical design specifications have been compared to determine the extent to which they agree. In general, good agreement was found in data at low flows and in bundle-center data at higher flows. Discrepancies in the data wre noted near the bundle edges at higher flows. An analysis of bundle thermal boundary conditions showed that the possible eccentric placement of one bundle within the housing could account for these discrepancies.

Levin, A.E.; Carbajo, J.J.; Lloyd, D.B.; Montgomery, B.H.; Rose, S.D.; Wantland, J.L.

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Study of design parameters for minimizing the cost of electricity of tokamak fusion power reactors  

Science Journals Connector (OSTI)

The impact of the design parameters on the cost of electricity (COE) is studied through a parameter survey in order to minimize the COE. Three kinds of operating modes are considered; first stability (FS), second stability (SS) and reversed shear (RS). The COE is calculated by a coupled physics-engineering-cost computer system code. Deuterium-tritium type, 1000 MW(e) at electric bus bar, steady state tokamak reactors with aspect ratios A from 3 to 4.5 are assumed. Several criteria are used for the parameter survey; for example, (a) the thermal to electrical conversion efficiency is assumed to be 34.5% using water as a coolant; (b) the average neutron wall load must not exceed 5 MW/m2 for plasma major radius Rp > 5 m; (c) a 2 MeV neutral beam injector (NBI) is applied. It is found that the RS operating mode most minimizes the COE among the three operating modes by reducing the cost of the current drive and the coils and structures. The cost-minimized RS reactor can attain high fbs, high ?N and low q95 at the same time, which results in a short Rp of 5.1 m, a low Bmax of the maximum magnetic toroidal field (TF) of the TF coils of 13 T and a low A of 3.0. It can be concluded that this cost-minimized RS reactor is the most cost-minimized within the frameworks of this study. This cost-minimized RS reactor has two advantages: one is that a Bmax = 13 T TF coil can be made by use of ITER coil technology and the other is that the same cooling technology as that of ITER (water cooling) can be used.

K. Tokimatsu; K. Okano; T. Yoshida; K. Yamaji; M. Katsurai

1998-01-01T23:59:59.000Z

142

Research reactors - an overview  

SciTech Connect (OSTI)

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

West, C.D.

1997-03-01T23:59:59.000Z

143

Safety Design Strategy for the Advanced Test Reactor Primary Coolant Pump and Motor Replacement Project  

SciTech Connect (OSTI)

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

Noel Duckwitz

2011-06-01T23:59:59.000Z

144

Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project  

SciTech Connect (OSTI)

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

Noel Duckwitz

2011-06-01T23:59:59.000Z

145

Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project  

SciTech Connect (OSTI)

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

Noel Duckwitz

2011-06-01T23:59:59.000Z

146

NNSA National Security Campus Receives LEED® Gold Certification...  

National Nuclear Security Administration (NNSA)

NSC earned 41 out of 51 possible points for this certification." LEED, or Leadership in Energy & Environmental Design, is the recognized standard for measuring building...

147

Safeguards-by-Design: Guidance for High Temperature Gas Reactors (HTGRs) With Pebble Fuel  

SciTech Connect (OSTI)

The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on pebble fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC.

Philip Casey Durst; Mark Schanfein

2012-08-01T23:59:59.000Z

148

Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

An engineering design study of the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel is ongoing at Oak Ridge National Laboratory. The computational models developed during fiscal year 2010 to search for an LEU fuel design that would meet the requirements for the conversion and the results obtained with these models are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating HEU fuel core. The results obtained indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations under the assumption that the operating power for the reactor fueled with LEU can be increased from the current value of 85 MW to 100 MW.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2011-05-01T23:59:59.000Z

149

The effect of reactor design on the sustainability of grass biomethane  

Science Journals Connector (OSTI)

Grass biomethane is a sustainable transport biofuel. It can meet the 60% greenhouse gas saving requirements (as compared to the replaced fossil fuel) specified in the EU Renewable Energy Directive, if allowance is made for carbon sequestration, green electricity is used and the vehicle is optimized for gaseous biomethane. The issue in this paper is the effect of the digester type on the overall emissions savings. Examining three digestion configurations; dry continuous (DCAD), wet continuous (WCAD), and a two phase system (SLBR-UASB), it was found that the reactor type can result in a variation of 15% in emissions savings. The system that as modeled produced most biogas, and fuelled a vehicle most distance, the two phase system (SLBR-UASB), was the least sustainable due to biogas losses in the dry batch step. The system as modeled which produced the least biogas (DCAD) was the most sustainable as the parasitic demands on the system were least. Optimal reactor design for sustainability criteria should maximize biogas production, while minimizing biogas losses and parasitic demands.

Anoop Singh; Abdul-Sattar Nizami; Nicholas E. Korres; Jerry D. Murphy

2011-01-01T23:59:59.000Z

150

Design, development, and applications of a low-cost, dynamic neutron radiography system utilizing the TAMU NSC TRIGA reactor  

E-Print Network [OSTI]

partial fulfilment of the requirements for the degree of MASTER OF SC'IENCE May 1990 Major Subject: Nuclear Engineering DESIGN, DEVELOPMENT. AND APPLICATIONS OF A LOW ? COST, DYNAMIC NEUTRON RADIOGRAPHY SYSTEM UTILIZING THE TAMU NSC TRIGA REACTOR A...DESIGN, DEVELOPMENT. AND APPLICATIONS OF A LOW ? COST, DYNAMIC NEUTRON RADIOGRAPHY SYSTEM UTILIZING THE TAMU NSC TRIGA REACTOR A Thesis SC'OTT PATRIC'If ItIIDGETT Submitted to the Ofhce of Graduate Studies of Texas AklVI I!niversity rn...

Midgett, Scott Patrick

2012-06-07T23:59:59.000Z

151

ENERGY STAR certification | ENERGY STAR Buildings & Plants  

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

ENERGY STAR certification ENERGY STAR certification Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section How can we help you? Find out who's partnered with ENERGY STAR Become an ENERGY STAR partner Find ENERGY STAR certified buildings and plants ENERGY STAR certification Featured research and reports Facts and stats Climate change and buildings ENERGY STAR certification

152

ENERGY STAR certification for your building | ENERGY STAR Buildings &  

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

certification for your building certification for your building Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section Learn the benefits Get started Use Portfolio Manager Save energy Find financing Earn recognition 20-percent recognition ENERGY STAR certification How to apply for ENERGY STAR certification Tips for low-cost verifications Submit a profile of your building

153

Conceptual design of a passively safe thorium breeder Pebble Bed Reactor  

Science Journals Connector (OSTI)

Abstract More sustainable nuclear power generation might be achieved by combining the passive safety and high temperature applications of the Pebble Bed Reactor (PBR) design with the resource availability and favourable waste characteristics of the thorium fuel cycle. It has already been known that breeding can be achieved with the thorium fuel cycle inside a Pebble Bed Reactor if reprocessing is performed. This is also demonstrated in this work for a cylindrical core with a central driver zone, with 3 g heavy metal pebbles for enhanced fission, surrounded by a breeder zone containing 30 g thorium pebbles, for enhanced conversion. The main question of the present work is whether it is also possible to combine passive safety and breeding, within a practical operating regime, inside a thorium Pebble Bed Reactor. Therefore, the influence of several fuel design, core design and operational parameters upon the conversion ratio and passive safety is evaluated. A Depressurized Loss of Forced Cooling (DLOFC) is considered the worst safety scenario that can occur within a PBR. So, the response to a DLOFC with and without scram is evaluated for several breeder PBR designs using a coupled DALTON/THERMIX code scheme. With scram it is purely a heat transfer problem (THERMIX) demonstrating the decay heat removal capability of the design. In case control rods cannot be inserted, the temperature feedback of the core should also be able to counterbalance the reactivity insertion by the decaying xenon without fuel temperatures exceeding 1600 °C. Results show that high conversion ratios (CR  > 0.96) and passive safety can be combined in a thorium PBR within a practical operating regime, which means a thermal power of 100 MW or higher, 1000 days total residence time of the breeder pebbles and fuel pebble handling times longer than 14.5 s, like in the HTR-PM. With an increased U-233 content of the fresh driver pebbles (18 w%), breeding (CR = 1.0135) can already be achieved for a 220 cm core and 80 cm driver zone radius. While the decay heat removal is sufficient in this design, the temperature feedback of the undermoderated driver pebbles is too weak to compensate the reactivity insertion due to the xenon decay during a DLOFC without scram. With a lower U-233 content per driver pebble (10 w%) it was found possible to combine breeding (CR = 1.0036) and passive safety for a 300 cm core and 100 cm driver zone radius, but this does require more than a doubling of the pebble handling speed and a high reprocessing rate of the fuel pebbles. The maximum fuel temperature during a DLOFC without scram was simulated to be 1481 °C for this design, still quite a bit below the TRISO failure temperature. The maximum reactivity insertion due to an ingress of water vapour is also limited with a value of +1497 pcm.

F.J. Wols; J.L. Kloosterman; D. Lathouwers; T.H.J.J. van der Hagen

2015-01-01T23:59:59.000Z

154

A Comparison of the Performance of Compact Neutrino Detector Designs for Nuclear Reactor Safeguards and Monitoring  

E-Print Network [OSTI]

There has been an increasing interest in the monitoring of nuclear fuel for power reactors by detecting the anti-neutrinos produced during operation. Small liquid scintillator detectors have already demonstrated sensitivity to operational power levels, but more sensitive monitoring requires improvements in the efficiency and uniformity of these detectors. In this work, we use a montecarlo simulation to investigate the detector performance of four different detector configurations. Based on the analysis of neutron detection efficiency and positron energy response, we find that the optimal detector design will depend on the goals and restrictions of the specific installation or application. We have attempted to present the relevant information so that future detector development can proceed in a profitable direction.

McKeown, R W

2006-01-01T23:59:59.000Z

155

Stress Analysis of Coated Particle Fuel in the Deep-Burn Pebble Bed Reactor Design  

SciTech Connect (OSTI)

High fuel temperatures and resulting fuel particle coating stresses can be expected in a Pu and minor actinide fueled Pebble Bed Modular Reactor (400 MWth) design as compared to the ’standard’ UO2 fueled core. The high discharge burnup aimed for in this Deep-Burn design results in increased power and temperature peaking in the pebble bed near the inner and outer reflector. Furthermore, the pebble power in a multi-pass in-core pebble recycling scheme is relatively high for pebbles that make their first core pass. This might result in an increase of the mechanical failure of the coatings, which serve as the containment of radioactive fission products in the PBMR design. To investigate the integrity of the particle fuel coatings as a function of the irradiation time (i.e. burnup), core position and during a Loss Of Forced Cooling (LOFC) incident the PArticle STress Analysis code (PASTA) has been coupled to the PEBBED code for neutronics, thermal-hydraulics and depletion analysis of the core. Two deep burn fuel types (Pu with or without initial MA fuel content) have been investigated with the new code system for normal and transient conditions including the effect of the statistical variation of thickness of the coating layers.

B. Boer; A. M. Ougouag

2010-05-01T23:59:59.000Z

156

NERSC Grid Certificates  

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

Grid Grid Certificates Grid Certificates | Tags: Grid Grid certificates allow you to access NERSC (and other Grid enabled computing facilities) via grid interfaces. Grid certificates are credentials that must be initialized for use with grid tools. Once a certificate is initialized it is automatically used by the grid tools to authenticate the user to the grid resource. Getting a Short Lived NERSC CA Certificate The NERSC Online CA now offers a quick and painless way to obtain grid certificates. You can obtain a grid certificate with a single command using this method. If you are on a NERSC system, load the globus module to set up your environment: % module load globus or % module load osg On the client system (assuming you have the globus binaries in your path), simply run:

157

Design and optimization of a high thermal flux research reactor via Kriging-based algorithm  

E-Print Network [OSTI]

In response to increasing demands for the services of research reactors, a 5 MW LEU-fueled research reactor core is developed and optimized to provide high thermal flux within specified limits upon thermal hydraulic ...

Kempf, Stephanie Anne

2011-01-01T23:59:59.000Z

158

An autonomous long-term fast reactor system and the principal design limitations of the concept  

E-Print Network [OSTI]

Actinides MOX Mixed OXide MSR Molten-Salt Reactors NERI Nuclear Energy Research Initiative vii PWR Pressurized Water Reactor RGPu Reactor-Grade Plutonium SCNES Self-Consistent Nuclear Energy System STAR Secure Transportable Autonomous Reactor... of LWR?s, the drastic increase of Am and Cm inventories are observed after uranium fuel irradiation and the second recycling of MOX fuel.1 Therefore, partitioning and transmutation of the recovered MA?s could significantly reduce the long...

Tsvetkova, Galina Valeryevna

2004-09-30T23:59:59.000Z

159

Design and testing of a boron carbide capsule for spectral-tailoring in mixed-spectrum reactors  

SciTech Connect (OSTI)

A boron carbide capsule has been designed and used for spectral-tailoring experiments at the TRIGA reactor at Washington State Univ.. Irradiations were conducted in pulsed mode and in continuous operation for up to 4 h. A cadmium cover was used to reduce thermal heating. The neutron spectrum calculated with the Monte Carlo N-particle transport code was found to be in good agreement with reactor dosimetry measurements using the STAY'SL computer code. The neutron spectrum resembles that of a fast reactor. The design of a capsule using boron carbide fully enriched in {sup 10}B shows that it is possible to produce a neutron spectrum similar to that of {sup 235}U fission. (authors)

Greenwood, L.R.; Wittman, R. [Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Pierson, B.P. [Univ. of Michigan, Ann Arbor, MI 48109 (United States); Metz, L.A.; Payne, R.; Finn, E.C.; Friese, J.I. [Pacific Northwest National Laboratory, Richland, WA 99352 (United States)

2011-07-01T23:59:59.000Z

160

Challenge Home Certificate Examples  

Broader source: Energy.gov [DOE]

These certificates are printed from RESNET Accredited Software, examples from REM/Rate and from EnergyGauge.

Note: This page contains sample records for the topic "reactor design certification" 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

Safeguards-by-Design:Guidance for High Temperature Gas Reactors (HTGRs) With Prismatic Fuel  

SciTech Connect (OSTI)

Introduction and Purpose The following is a guidance document from a series prepared for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), under the Next Generation Safeguards Initiative (NGSI), to assist facility designers and operators in implementing international Safeguards-by-Design (SBD). SBD has two main objectives: (1) to avoid costly and time consuming redesign work or retrofits of new nuclear fuel cycle facilities and (2) to make the implementation of international safeguards more effective and efficient at such facilities. In the long term, the attainment of these goals would save industry and the International Atomic Energy Agency (IAEA) time, money, and resources and be mutually beneficial. This particular safeguards guidance document focuses on prismatic fuel high temperature gas reactors (HTGR). The purpose of the IAEA safeguards system is to provide credible assurance to the international community that nuclear material and other specified items are not diverted from peaceful nuclear uses. The safeguards system consists of the IAEA’s statutory authority to establish safeguards; safeguards rights and obligations in safeguards agreements and additional protocols; and technical measures implemented pursuant to those agreements. Of foremost importance is the international safeguards agreement between the country and the IAEA, concluded pursuant to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). According to a 1992 IAEA Board of Governors decision, countries must: notify the IAEA of a decision to construct a new nuclear facility as soon as such decision is taken; provide design information on such facilities as the designs develop; and provide detailed design information based on construction plans at least 180 days prior to the start of construction, and on "as-built" designs at least 180 days before the first receipt of nuclear material. Ultimately, the design information will be captured in an IAEA Design Information Questionnaire (DIQ), prepared by the facility operator, typically with the support of the facility designer. The IAEA will verify design information over the life of the project. This design information is an important IAEA safeguards tool. Since the main interlocutor with the IAEA in each country is the State Regulatory Authority/SSAC (or Regional Regulatory Authority, e.g. EURATOM), the responsibility for conveying this design information to the IAEA falls to the State Regulatory Authority/SSAC. For the nuclear industry to reap the benefits of SBD (i.e. avoid cost overruns and construction schedule slippages), nuclear facility designers and operators should work closely with the State Regulatory Authority and IAEA as soon as a decision is taken to build a new nuclear facility. Ideally, this interaction should begin during the conceptual design phase and continue throughout construction and start-up of a nuclear facility. Such early coordination and planning could influence decisions on the design of the nuclear material processing flow-sheet, material storage and handling arrangements, and facility layout (including safeguards equipment), etc.

Mark Schanfein; Casey Durst

2012-11-01T23:59:59.000Z

162

Preliminary neutronics design of china lead-alloy cooled demonstration reactor (CLEAR-III) for nuclear waste transmutation  

SciTech Connect (OSTI)

China Lead-Alloy cooled Demonstration Reactor (CLEAR-III), which is the concept of lead-bismuth cooled accelerator driven sub-critical reactor for nuclear waste transmutation, was proposed and designed by FDS team in China. In this study, preliminary neutronics design studies have primarily focused on three important performance parameters including Transmutation Support Ratio (TSR), effective multiplication factor and blanket thermal power. The constraint parameters, such as power peaking factor and initial TRU loading, were also considered. In the specific design, uranium-free metallic dispersion fuel of (TRU-Zr)-Zr was used as one of the CLEAR-III fuel types and the ratio between MA and Pu was adjusted to maximize transmutation ratio. In addition, three different fuel zones differing in the TRU fraction of the fuel were respectively employed for this subcritical reactor, and the zone sizes and TRU fractions were determined such that the linear powers of these zones were close to each other. The neutronics calculations and analyses were performed by using Multi-Functional 4D Neutronics Simulation System named VisualBUS and nuclear data library HENDL (Hybrid Evaluated Nuclear Data Library). In the preliminary design, the maximum TSRLLMA was {approx}11 and the blanket thermal power was {approx}1000 MW when the effective multiplication factor was 0.98. The results showed that good performance of transmutation could be achieved based on the subcritical reactor loaded with uranium-free fuel. (authors)

Chen, Z. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); Southwest Science and Technology Univ., No.350 Shushanhu Road, Shushan District, Hefei, Anhui, 230031 (China); Chen, Y.; Bai, Y.; Wang, W.; Chen, Z.; Hu, L.; Long, P. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, Hefei, Anhui, 230031 (China)

2012-07-01T23:59:59.000Z

163

TOKOPS: Tokamak Reactor Operations Study: The influence of reactor operations on the design and performance of tokamaks with solid-breeder blankets: Final report  

SciTech Connect (OSTI)

Reactor system operation and procedures have a profound impact on the conception and design of power plants. These issues are studied here using a model tokamak system employing a solid-breeder blanket. The model blanket is one which has evolved from the STARFIRE and BCSS studies. The reactor parameters are similar to those characterizing near-term fusion engineering reactors such as INTOR or NET (Next European Tokamak). Plasma startup, burn analysis, and methods for operation at various levels of output power are studied. A critical, and complicating, element is found to be the self-consistent electromagnetic response of the system, including the presence of the blanket and the resulting forces and loadings. Fractional power operation, and the strategy for burn control, is found to vary depending on the scaling law for energy confinement, and an extensive study is reported. Full-power reactor operation is at a neutron wall loading pf 5 MW/m/sup 2/ and a surface heat flux of 1 MW/m/sup 2/. The blanket is a pressurized steel module with bare beryllium rods and low-activation HT-9-(9-C-) clad LiAlO/sub 2/ rods. The helium coolant pressure is 5 MPa, entering the module at 297/sup 0/C and exiting at 550/sup 0/C. The system power output is rated at 1000 MW(e). In this report, we present our findings on various operational scenarios and their impact on system design. We first start with the salient aspects of operational physics. Time-dependent analyses of the blanket and balance of plant are then presented. Separate abstracts are included for each chapter.

Conn, R.W.; Ghoniem, N.M.; Firestone, M.A. (eds.)

1986-09-01T23:59:59.000Z

164

Conceptual design of the bimodal nuclear power system based on the ‘‘Romashka’’ type reactor with thermionic energy conversion system  

Science Journals Connector (OSTI)

The paper presents conceptual design of the bimodal space nuclear power system (NPS) based on the high?temperature reactor of ROMASHKA type with thermoninic energy conversion system. At the heart of the design is an employment of close?spaced thermionic diodes operating in a quasi?vacuum mode. The paper gives preliminary estimates of the NPS neutron?physical electric thermophysical and mass?dimensional parameters for the reactor electric power of 25 kW and propulsive thrust of about 80 N. Discussed are peculiarities of the combined mode wherein electric power is generated along with propulsive thrust. The paper contains results of the design studies performed by the Small Business ‘‘NP Energotech’’ under the Agreement with Rockwell International/Rocketdyne Division and according to the Rocketdyne Division provided Design Requirements. Involved in the work was the team of specialists of RRC ‘‘Kurchatov Institute’’ ‘‘Red Star’’ State Enterprise and Research Institute of SPA ‘‘Luch’’

Nikolai N. Ponmarev?Stepnoi; Veniamin A. Usov; Yuri V. Nikolaev; Stanislav A. Yeriemin; Yevgeny Ye. Zhabotinski; Anatoly Ya. Galkin; Yevgeny D. Avdoshyn

1995-01-01T23:59:59.000Z

165

Energy Department Issues Green Building Certification System Final Rule to Support Increased Energy Measurement and Efficient Building Design  

Office of Energy Efficiency and Renewable Energy (EERE)

Supporting the Obama Administration’s goal to reduce carbon emissions and protect the environment, the Energy Department is pursuing a suite of initiatives to strengthen federal energy management through increased focus on measurement of energy use in federal buildings and energy efficient building design.

166

Computer analyses for the design, operation and safety of new isotope production reactors: A technology status review  

SciTech Connect (OSTI)

A review is presented on the currently available technologies for nuclear reactor analyses by computer. The important distinction is made between traditional computer calculation and advanced computer simulation. Simulation needs are defined to support the design, operation, maintenance and safety of isotope production reactors. Existing methods of computer analyses are categorized in accordance with the type of computer involved in their execution: micro, mini, mainframe and supercomputers. Both general and special-purpose computers are discussed. Major computer codes are described, with regard for their use in analyzing isotope production reactors. It has been determined in this review that conventional systems codes (TRAC, RELAP5, RETRAN, etc.) cannot meet four essential conditions for viable reactor simulation: simulation fidelity, on-line interactive operation with convenient graphics, high simulation speed, and at low cost. These conditions can be met by special-purpose computers (such as the AD100 of ADI), which are specifically designed for high-speed simulation of complex systems. The greatest shortcoming of existing systems codes (TRAC, RELAP5) is their mismatch between very high computational efforts and low simulation fidelity. The drift flux formulation (HIPA) is the viable alternative to the complicated two-fluid model. No existing computer code has the capability of accommodating all important processes in the core geometry of isotope production reactors. Experiments are needed (heat transfer measurements) to provide necessary correlations. It is important for the nuclear community, both in government, industry and universities, to begin to take advantage of modern simulation technologies and equipment. 41 refs.

Wulff, W.

1990-01-01T23:59:59.000Z

167

Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

This study presents the neutronic analysis of an advanced fuel design concept for the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) that could significantly extend the current fuel cycle length under the existing design and safety criteria. A key advantage of the fuel design herein proposed is that it would not require structural changes to the present HFIR core, in other words, maintaining the same rated power and fuel geometry (i.e., fuel plate thickness and coolant channel dimensions). Of particular practical importance, as well, is the fact that the proposed change could be justified within the bounds of the existing nuclear safety basis. The simulations herein reported employed transport theory-based and exposure-dependent eigenvalue characterization to help improve the prediction of key fuel cycle parameters. These parameters were estimated by coupling a benchmarked three-dimensional MCNP5 model of the HFIR core to the depletion code ORIGEN via the MONTEBURNS interface. The design of an advanced HFIR core with an improved fuel loading is an idea that evolved from early studies by R. D. Cheverton, formerly of ORNL. This study contrasts a modified and increased core loading of 12 kg of 235U against the current core loading of 9.4 kg. The simulations performed predict a cycle length of 39 days for the proposed fuel design, which represents a 50% increase in the cycle length in response to a 25% increase in fissile loading, with an average fuel burnup increase of {approx}23%. The results suggest that the excess reactivity can be controlled with the present design and arrangement of control elements throughout the core's life. Also, the new power distribution is comparable or even improved relative to the current power distribution, displaying lower peak to average fission rate densities across the inner fuel element's centerline and bottom cells. In fact, the fission rate density in the outer fuel element also decreased at these key locations for the proposed design. Overall, it is estimated that the advanced core design could increase the availability of the HFIR facility by {approx}50% and generate {approx}33% more neutrons annually, which is expected to yield sizeable savings during the remaining life of HFIR, currently expected to operate through 2014. This study emphasizes the neutronics evaluation of a new fuel design. Although a number of other performance parameters of the proposed design check favorably against the current design, and most of the core design features remain identical to the reference, it is acknowledged that additional evaluations would be required to fully justify the thermal-hydraulic and thermal-mechanical performance of a new fuel design, including checks for cladding corrosion performance as well as for industrial and economic feasibility.

Xoubi, Ned [ORNL; Primm, Trent [ORNL; Maldonado, G. Ivan [University of Tennessee, Knoxville (UTK)

2009-01-01T23:59:59.000Z

168

Design of a boiling water reactor equilibrium core using thorium-uranium fuel  

SciTech Connect (OSTI)

In this paper the design of a Boiling Water Reactor (BWR) equilibrium core using thorium is presented; a heterogeneous blanket-seed core arrangement concept was adopted. The design was developed in three steps: in the first step two different assemblies were designed based on the integrated blanket-seed concept, they are the blanket-dummy assembly and the blanket-seed assembly. The integrated blanketseed concept comes from the fact that the blanket and the seed rods are located in the same assembly, and are burned-out in a once-through cycle. In the second step, a core design was developed to achieve an equilibrium cycle of 365 effective full power days in a standard BWR with a reload of 104 fuel assemblies designed with an average 235U enrichment of 7.5 w/o in the seed sub-lattice. The main operating parameters, like power, linear heat generation rate and void distributions were obtained as well as the shutdown margin. It was observed that the analyzed parameters behave like those obtained in a standard BWR. The shutdown margin design criterion was fulfilled by addition of a burnable poison region in the assembly. In the third step an in-house code was developed to evaluate the thorium equilibrium core under transient conditions. A stability analysis was also performed. Regarding the stability analysis, five operational states were analyzed; four of them define the traditional instability region corner of the power-flow map and the fifth one is the operational state for the full power condition. The frequency and the boiling length were calculated for each operational state. The frequency of the analyzed operational states was similar to that reported for BWRs; these are close to the unstable region that occurs due to the density wave oscillation phenomena in some nuclear power plants. Four transient analyses were also performed: manual SCRAM, recirculation pumps trip, main steam isolation valves closure and loss of feed water. The results of these transients are similar to those obtained with the traditional UO2 nuclear fuel.

Francois, J-L.; Nunez-Carrera, A.; Espinosa-Paredes, G.; Martin-del-Campo, C.

2004-10-06T23:59:59.000Z

169

Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

An engineering design study that would enable the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel is ongoing at Oak Ridge National Laboratory. The computational models used to search for a low-enriched uranium (LEU) fuel design that would meet the requirements for the conversion study, and the recent results obtained with these models during FY 2009, are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating high-enriched uranium fuel core. These studies indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations.

Ilas, Germina [ORNL; Primm, Trent [ORNL

2009-11-01T23:59:59.000Z

170

Nuclear Regulatory Commission Handling of Beyond Design Basis Events for Nuclear Power Reactors  

Broader source: Energy.gov [DOE]

Presenter: Bill Reckley, Chief, Policy and Support Branch, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission US Nuclear Regulatory Commission

171

Design and development of a special purpose SAFT system for nondestructive evaluation of nuclear reactor vessels and piping components  

SciTech Connect (OSTI)

This report describes the design details of a special purpose system for real-time nondestructive evaluation of reactor vessels and piping components. The system consists of several components and the report presents the results of the research aimed at the design of each component and recommendations based on the results. One major component of the NDE system, namely the real-time SAFT processor, was designed with sufficient details to enable the fabrications of a prototype by GARD Inc. under a subcontract from The University of Michigan and the report includes their results and conclusions.

Ganapathy, S.; Schmult, B.; Wu, W.S.; Dennehy, T.G.; Moayeri, N.; Kelly, P.

1985-08-01T23:59:59.000Z

172

Obama Administration Announces $450 Million to Design and Commercialize  

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

$450 Million to Design and $450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors Obama Administration Announces $450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors March 22, 2012 - 2:15pm Addthis Today, as President Obama went to Ohio State University to discuss the all-out, all-of-the-above strategy for American energy, the White House announced new funding to advance the development of American-made small modular reactors (SMRs), an important element of the President's energy strategy. A total of $450 million will be made available to support first-of-its-kind engineering, design certification and licensing for up to two SMR designs over five years, subject to congressional appropriations. Manufacturing these reactors domestically will offer the United States

173

Obama Administration Announces $450 Million to Design and Commercialize  

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

450 Million to Design and 450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors Obama Administration Announces $450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors March 22, 2012 - 2:28pm Addthis COLUMBUS, Ohio - Today, as President Obama went to Ohio State University to discuss the all-out, all-of-the-above strategy for American energy, the White House announced new funding to advance the development of American-made small modular reactors (SMRs), an important element of the President's energy strategy. A total of $450 million will be made available to support first-of-its-kind engineering, design certification and licensing for up to two SMR designs over five years, subject to congressional appropriations. Manufacturing these reactors domestically

174

Status of axial heterogeneous liquid-metal fast breeder reactor core design studies and research and development  

SciTech Connect (OSTI)

The current status of axial heterogeneous core (AHC) design development in Japan, which consists of an AHC core design in a pool-type demonstration fast breeder reactor (DFBR) and research and development activities supporting AHC core design, is presented. The DFBR core design objectives developed by The Japan Atomic Power Company include (a) favorable core seismic response, (b) core compactness, (c) high availability, and (d) lower fuel cycle cost. The AHC concept was selected as a reference pool-type DFBR core because it met these objectives more suitably than the homogeneous core (HOC). The AHC core layouts were optimized emphasizing the reduction of the burnup reactivity swing, peak fast fluence, and power peaking. The key performance parameters resulting from the AHC, such as flat axial power/flux distribution, lower peak fast fluence, lower burnup reactivity swing, etc., were evaluated in comparison with the HOC. The critical experiments at the Japan Atomic Energy Research Institute's Fast Critical Assembly facility demonstrate the key AHC performance characteristics. The large AHC engineering benchmark experiments using the zero-power plutonium reactor and the AHC fuel pin irradiation test program using the JOYO reactor are also presented.

Nakagawa, H.; Inagaki, T.; Yoshimi, H.; Shirakata, K.; Watari, Y.; Suzuki, M.; Inoue, K.

1988-11-01T23:59:59.000Z

175

Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management  

SciTech Connect (OSTI)

The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzed in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility.1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety basis. The need for a design basis reconstitution program for the ATR has been identified along with the use of sound configuration management principles in order to support safe and efficient facility operation.

G. L. Sharp; R. T. McCracken

2004-05-01T23:59:59.000Z

176

Design of a continuous-flow reactor for in situ x-ray absorption spectroscopy of solids in supercritical fluids  

SciTech Connect (OSTI)

This paper presents the design and performance of a novel high-temperature and high-pressure continuous-flow reactor, which allows for x-ray absorption spectroscopy or diffraction in supercritical water and other fluids under high pressure and temperature. The in situ cell consists of a tube of sintered, polycrystalline aluminum nitride, which is tolerant to corrosive chemical media, and was designed to be stable at temperatures up to 500 deg. C and pressures up to 30 MPa. The performance of the reactor is demonstrated by the measurement of extended x-ray absorption fine structure spectra of a carbon-supported ruthenium catalyst during the continuous hydrothermal gasification of ethanol in supercritical water at 400 deg. C and 24 MPa.

Dreher, M.; De Boni, E.; Nachtegaal, M.; Wambach, J.; Vogel, F. [Paul Scherrer Institut, 5232 Villigen PSI (Switzerland)

2012-05-15T23:59:59.000Z

177

Training, Certification, and Mentoring  

Broader source: Energy.gov [DOE]

The Project Management Coordination Office (PMCO) is working to support programs in ensuring that team members have the necessary training and certifications to enable meaningful stewardship of...

178

Design, construction, commissioning and use of a new cadmium-lined in-core irradiation tube for the Oregon State University TRIGA Reactor  

SciTech Connect (OSTI)

As a result of several requests from reactor users, it was recently decided to install a new cadmium-lined in-core irradiation tube (CLICIT) in the Oregon State University TRIGA Reactor (OSTR). As the title implies, this paper will describe the complete sequence of this process, from the design, and design constraints through manufacture to the actual use of the tube. The design is such that it offers a significant degree of flexibility in use, while still strictly adhering to ALARA concepts. In order to keep costs down, the facility was designed, installed and commissioned by the Oregon State University TRIGA Reactor (OSTR) staff and fabricated locally. As this facility is relatively cheap (about $2,000), and will fit all non-conversion TRIGAs other reactor owners may be interested in copying the OSTR tube design. (author)

Dodd, B.; Anderson, T.V

1990-07-01T23:59:59.000Z

179

Degree Information 37 Transcripted Graduate Certificate Programs  

E-Print Network [OSTI]

program Energy Sustainability Engineering Certificate Program Graduate Certificate in Advanced's and Gender Studies Certificate Program in Tree Improvement Ocean Observing Systems Certificate Program the student's career goals. Energy Sustainability Engineering Certificate. The graduate level Energy

180

Optimal control of xenon concentration by observer design under reactor model uncertainty  

SciTech Connect (OSTI)

The state feedback in control theory enjoys many advantages, such as stabilization and improved transient response, which could be beneficially used for control of the xenon oscillation in a power reactor. It is, however, not possible in nuclear reactors to measure the state variables, such as xenon and iodine concentrations. For implementation of the optimal state feedback control law, it is thus necessary to estimate the unmeasurable state variables. This paper uses the Luenberger observer to estimate the xenon and iodine concentrations to be used in a linear quadratic problem with state feedback. To overcome the stiffness problem in reactor kinetics, a singular perturbation method is used.

Cho, Nam Z.; Yang, Chae Y.; Woo, Hae S.

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Optimized core design of a supercritical carbon dioxide-cooled fast reactor  

E-Print Network [OSTI]

Spurred by the renewed interest in nuclear power, Gas-cooled Fast Reactors (GFRs) have received increasing attention in the past decade. Motivated by the goals of the Generation-IV International Forum (GIF), a GFR cooled ...

Handwerk, Christopher S. (Christopher Stanley), 1974-

2007-01-01T23:59:59.000Z

182

Stability analysis of the boiling water reactor : methods and advanced designs  

E-Print Network [OSTI]

Density Wave Oscillations (DWOs) are known to be possible when a coolant undergoes considerable density reduction while passing through a heated channel. In the development of boiling water reactors (BWRs), there has been ...

Hu, Rui, Ph. D. Massachusetts Institute of Technology

2010-01-01T23:59:59.000Z

183

IoT-Based Maintenance Process Design for Fusion Reactor Remote Handling System  

Science Journals Connector (OSTI)

Nuclear fusion is one of the most important ways ... to risk of ionizing radiation, the nuclear fusion reactor will relay on remote handling maintenance to ... the maintenance efficiency. The basic structure of fusion

Ruonan Zhang; Xinbao Liu

2014-12-01T23:59:59.000Z

184

An inverted pressurized water reactor design with twisted-tape swirl promoters  

E-Print Network [OSTI]

An Inverted Fuel Pressurized Water Reactor (IPWR) concept was previously investigated and developed by Paolo Ferroni at MIT with the effort to improve the power density and capacity of current PWRs by modifying the core ...

Nguyen, Nghia T. (Nghia Tat)

2014-01-01T23:59:59.000Z

185

Design and optimization of the heat rejection system for a liquid cooled thermionic space nuclear reactor power system  

SciTech Connect (OSTI)

The heat transport subsystem for a liquid metal cooled thermionic space nuclear power system was modelled using algorithms developed in support of previous nuclear power system study programs, which date back to the SNAP-10A flight system. The model was used to define the optimum dimensions of the various components in the heat transport subsystem subjected to the constraints of minimizing mass and achieving a launchable package that did not require radiator deployment. The resulting design provides for the safe and reliable cooling of the nuclear reactor in a proven lightweight design.

Moriarty, M.P. (Rocketdyne Division, Rockwell International Corporation, 6633 Canoga Avenue, P.O. Box 7922, Canoga Park, California 91309-7922 (United States))

1993-01-15T23:59:59.000Z

186

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

SciTech Connect (OSTI)

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

187

Granular Dynamics in Pebble Bed Reactor Cores  

E-Print Network [OSTI]

pebble bed reactor,” Nuclear Engineering and Design, vol.the AVR reactor,” Nuclear Engineering and Design, vol. 121,Operating Experience,” Nuclear Engineering and Design, vol.

Laufer, Michael Robert

2013-01-01T23:59:59.000Z

188

Graduate Certificate in Transportation  

E-Print Network [OSTI]

Graduate Certificate in Transportation Nohad A. Toulan School of Urban Studies and Planning of Engineering and Computer Science integrated transportation systems. The Graduate Certificate in Transportation their capabilities. Students in the program can choose among a wide range of relevant courses in transportation

Bertini, Robert L.

189

Certification | Department of Energy  

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

Certification Certification Certification THE CERTIFICATION PROCESS You Are Sponsored and Associated With the PMCDP Program. How Do You Proceed? Start by taking an inventory of your past project management training, developmental assignments, and experience. Organize the information by the applicable knowledge, skill, and ability as shown in the Certification and Equivalency Guide (CEG), as well as the training curriculum requirements set forth in the Requirements at a Glance Table, or the PMCDP Curriculum Map. Profile Data Entry Log onto ESS. Click on PMCDP at the top of the screen. A drop down menu will appear. Choose "Instructions" and read through the applicable Tutorial chapters before you begin entering data. Once you are comfortable with the data requirements, begin entering your profile information into

190

Design change management in regulation of nuclear fleets: World nuclear association's working groups on Cooperation in Reactor Design Evaluation and Licensing (CORDEL)  

SciTech Connect (OSTI)

The 60 year life of a reactor means that a plant will undergo change during its life. To ensure continuing safety, changes must be made with a full understanding of the design intent. With this aim, regulators require that each operating organisation should have a formally designated entity responsible for complete design knowledge in regard to plant safety. INSAG-19 calls such an entity 'Design Authority'. This requirement is difficult to achieve, especially as the number of countries and utilities operating plants increases. Some of these operating organisations will be new, and some will be small. For Gen III plants sold on a turnkey basis, it is even more challenging for the operating company to develop and retain the full knowledge needed for this role. CORDEL's Task Force entitled 'Design Change Management' is investigating options for effective design change management with the aim to support design standardization throughout a fleet's lifetime by means of enhanced international cooperation within industry and regulators. This paper starts with considering the causes of design change and identifies reasons for the increased beneficial involvement of the plant's original vendor in the design change process. A key central theme running through the paper is the definition of responsibilities for design change. Various existing mechanisms of vendor-operator interfaces over design change and how they are managed in different organisational and regulatory environments around the world are considered, with the functionality of Owners Groups and Design Authority being central. The roles played in the design change process by vendors, utilities, regulators, owners' groups and other organisations such as WANO are considered The aerospace industry approach to Design Authority has been assessed to consider what lessons might be learned. (authors)

Swinburn, R. [CORDEL DCM Task Force, Rolls-Royce Plc (United Kingdom); Borysova, I. [CORDEL, WNA, 22a St.James Sq., London SW1Y 4JH (United Kingdom); Waddington, J. [CORDEL Group (United Kingdom); Head, J. G. [CORDEL Group, GE-Hitachi Nuclear Energy (United Kingdom); Raidis, Z. [CORDEL Group, Candu Energy (United Kingdom)

2012-07-01T23:59:59.000Z

191

Design of an Actinide-Burning, Lead or Lead-Bismuth Cooled Reactor that Produces Low-Cost Electricity  

SciTech Connect (OSTI)

The purpose of this Idaho National Engineering and Environmental Laboratory (INEEL) and Massachusetts Institute of Technology (MIT) University Research Consortium (URC) project is to investigate the suitability of lead or lead-bismuth cooled fast reactors for producing low-cost electricity as well as for actinide burning. The goal is to identify and analyze the key technical issues in core neutronics, materials, thermal-hydraulics, fuels, and economics associated with the development of this reactor concept. Work has been accomplished in four major areas of research: core neutronic design, material compatibility, plant engineering, and coolant activation. In the area of core neutronic design, the reactivity vs. burnup and discharge isotopics of both non-fertile and fertile fuels were evaluated. An innovative core for pure actinide burning that uses streaming, fertile-free fuel assemblies was studied in depth. This particular core exhibits excellent reactivity performance upon coolant voiding, even for voids that occur in the core center, and has a transuranic (TRU) destruction rate that is comparable to the proposed accelerator transmutation of waste (ATW) facility. These studies suggest that a core can be designed to achieve a long life while maintaining safety and minimizing waste. In the area of material compatibility studies, an experimental apparatus for the investigation of the flow-assisted dissolution and precipitation (corrosion) of potential fuel cladding and structural materials has been designed and built at the INEEL. The INEEL forced-convection corrosion cell consists of a small heated vessel with a shroud and gas flow system. The corrosion cell is being used to test steel that is commercially available in the United States to temperatures above 650°C. Progress in plant engineering was made for two reactor concepts, one utilizing an indirect cycle with heat exchangers and the other utilizing a direct-contact steam cycle. The evaluation of the indirect cycle designs has investigated the effects of various parameters to increase electric production at full power. For the direct-contact reactor, major issues related to the direct-contact heat transfer rate and entrainment and carryover of liquid lead-bismuth to the turbine have been identified and analyzed. An economic analysis approach was also developed to determine the cost of electricity production in the lead-bismuth reactor. The approach will be formulated into a model and applied to develop scientific cost estimates for the different reactor designs and thus aid in the selection of the most economic option. In the area of lead-bismuth coolant activation, the radiological hazard was evaluated with particular emphasis on the direct-contact reactor. In this system, the lack of a physical barrier between the primary and secondary coolant favors the release of the alpha-emitter Po?210 and its transport throughout the plant. Modeling undertaken on the basis of the scarce information available in the literature confirmed the importance of this issue, as well as the need for experimental work to reduce the uncertainties on the basic characteristics of volatile polonium chemical forms.

Mac Donald, Philip Elsworth; Weaver, Kevan Dean; Davis, Cliff Bybee; MIT folks

2000-07-01T23:59:59.000Z

192

Implementation of the SAM-CE Monte Carlo benchmark analysis capability for validating nuclear data and reactor design codes  

SciTech Connect (OSTI)

The National Nuclear Data Center is continuing its program to improve the nuclear data base used as input for commercial reactor analysis and design. In the most recent phase of this project the Monte Carlo program SAM-CE, developed by the Mathematical Applications Group, Inc. (MAGI), was made operational at BNL. This program was implemented on the BNL-CDC-7600 Computer, and also on the PDP-10 in-house computer. The NNDC made operational and developed techniques for processing ENDF/B-V cross sections for SAM-CE. A limited ENDF/B-V based library was produced. Use of the SAM-CE program in thermal reactor problems was validated using detailed comparisons of results with other Monte Carlo codes such as RECAP, RCP01 and VIM as well as with experimental data.

Beer, M.; Rose, P.

1981-04-01T23:59:59.000Z

193

Compiled reports on the applicability of selected codes and standards to advanced reactors  

SciTech Connect (OSTI)

The following papers were prepared for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission under contract DE-AC06-76RLO-1830 NRC FIN L2207. This project, Applicability of Codes and Standards to Advance Reactors, reviewed selected mechanical and electrical codes and standards to determine their applicability to the construction, qualification, and testing of advanced reactors and to develop recommendations as to where it might be useful and practical to revise them to suit the (design certification) needs of the NRC.

Benjamin, E.L.; Hoopingarner, K.R.; Markowski, F.J.; Mitts, T.M.; Nickolaus, J.R.; Vo, T.V.

1994-08-01T23:59:59.000Z

194

Newest Los Alamos facility receives LEED® Gold certification  

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

Newest facility receives LEED® Gold certification Newest facility receives LEED® Gold certification Newest Los Alamos facility receives LEED® Gold certification The Radiological Laboratory Utility Office Building is first to achieve both the Leadership in Energy and Environmental Design status and LEED Gold certification. June 13, 2012 Radiological Laboratory Utility Office Building Radiological Laboratory Utility Office Building Contact Kim Powell Communications Office (505) 695-6159 Email LOS ALAMOS, New Mexico, June 13, 2012-Los Alamos National Laboratory's newest facility, the Radiological Laboratory Utility Office Building (RLUOB), is also its first to achieve both the Leadership in Energy and Environmental Design (LEED) status and LEED Gold certification from the U.S. Green Building Council (USGBC).

195

Reliable-linac design for accelerator-driven subcritical reactor systems.  

SciTech Connect (OSTI)

Accelerator reliability corresponding to a very low frequency of beam interrupts is an important new accelerator requirement for accelerator-driven subcritical reactor systems. In this paper we review typical accelerator-reliability requirements and discuss possible methods for meeting these goals with superconducting proton-linac technology.

Wangler, Thomas P.,

2002-01-01T23:59:59.000Z

196

Analyses in support of the Laboratory Microfusion Facility and ICF commercial reactor designs  

SciTech Connect (OSTI)

Our work on this contract was divided into two major categories; two thirds of the total effort was in support of the Laboratory Microfusion Facility (LMF), and one third of the effort was in support of Inertial Confinement Fusion (ICF) commercial reactors. This final report includes copies of the formal reports, memoranda, and viewgraph presentations that were completed under this contract.

Meier, W.R.; Monsler, M.J.

1988-12-28T23:59:59.000Z

197

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

198

Conceptual design of thorium-fuelled Mitrailleuse accelerator-driven subcritical reactor using D-Be neutron source  

SciTech Connect (OSTI)

A distributed accelerator is a charged-particle accelerator that uses a new acceleration method based on repeated electrostatic acceleration. This method offers outstanding benefits not possible with the conventional radio-frequency acceleration method, including: (1) high acceleration efficiency, (2) large acceleration current, and (3) lower failure rate made possible by a fully solid-state acceleration field generation circuit. A 'Mitrailleuse Accelerator' is a product we have conceived to optimize this distributed accelerator technology for use with a high-strength neutron source. We have completed the conceptual design of a Mitrailleuse Accelerator and of a thorium-fuelled subcritical reactor driven by a Mitrailleuse Accelerator. This paper presents the conceptual design details and approach to implementing the subcritical reactor core. We will spend the next year or so on detailed design work, and then will start work on developing a prototype for demonstration. If there are no obstacles in setting up a development organization, we expect to finish verifying the prototype's performance by the third quarter of 2015. (authors)

Kokubo, Y. [Quan Japan Company Limited, 3-9-15 Sannomiya-cho, Chuo-ku, Kobe, Hyogo, 650-0021 (Japan); Kamei, T. [Research Inst. for Applied Sciences, 49 Tanaka Ohicho, Sakyo-ku, Kyoto-shi, Kyoto, 606-8202 (Japan)

2012-07-01T23:59:59.000Z

199

Design and Testing of a 10B4C Capsule for Spectral-Tailoring in Mixed-Spectrum Reactors  

SciTech Connect (OSTI)

A boron carbide capsule highly enriched in 10B has been designed and used for spectral-tailoring experiments at the TRIGA reactor at Washington State University. New experiments show that enriching the boron to 96% B-10 results in additional absorption of neutrons in the resonance region thereby producing a neutron spectrum that is much closer to a pure 235U fission spectrum. A cadmium outer cover was used to reduce thermal heating. The neutron spectrum calculated with MCNP was found to be in very good agreement with measured activation rates from neutron fluence monitors.

Greenwood, Lawrence R.; Wittman, Richard S.; Metz, Lori A.; Finn, Erin C.; Friese, Judah I.

2014-04-11T23:59:59.000Z

200

Conceptual design analysis of an MHD power conversion system for droplet-vapor core reactors. Final report  

SciTech Connect (OSTI)

A nuclear driven magnetohydrodynamic (MHD) generator system is proposed for the space nuclear applications of few hundreds of megawatts. The MHD generator is coupled to a vapor-droplet core reactor that delivers partially ionized fissioning plasma at temperatures in range of 3,000 to 4,000 K. A detailed MHD model is developed to analyze the basic electrodynamics phenomena and to perform the design analysis of the nuclear driven MHD generator. An incompressible quasi one dimensional model is also developed to perform parametric analyses.

Anghaie, S.; Saraph, G.

1995-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Forensic Toxicology Certificate  

E-Print Network [OSTI]

Forensic Toxicology Certificate What is Forensic Toxicology? Forensic toxicology is a discipline of forensic science that is concerned with the study of toxic substances or poisons. Toxicology encompasses. Students of forensic toxicology obtain knowledge about the absorption, distribution, and elimination

Saldin, Dilano

202

ENERGY STAR Industrial Plant Certification: Instructions for applying |  

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

Industrial Plant Certification: Instructions for Industrial Plant Certification: Instructions for applying Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In This Section Campaigns Commercial building design Communications resources Energy management guidance Financial resources Portfolio Manager Products and purchasing Recognition Research and reports Service and product provider (SPP) resources

203

ENERGY STAR Industrial Plant Certification: Professional Engineers' Guide  

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

Industrial Plant Certification: Professional Industrial Plant Certification: Professional Engineers' Guide Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In This Section Campaigns Commercial building design Communications resources Energy management guidance Financial resources Portfolio Manager Products and purchasing Recognition Research and reports Service and product provider (SPP) resources

204

Fuel element design for the enhanced destruction of plutonium in a nuclear reactor  

DOE Patents [OSTI]

A uranium-free fuel for a fast nuclear reactor comprising an alloy of Pu, Zr and Hf, wherein Hf is present in an amount less than about 10% by weight of the alloy. The fuel may be in the form of a Pu alloy surrounded by a Zr--Hf alloy or an alloy of Pu--Zr--Hf or a combination of both. 7 figs.

Crawford, D.C.; Porter, D.L.; Hayes, S.L.; Hill, R.N.

1999-03-23T23:59:59.000Z

205

Fuel element design for the enhanced destruction of plutonium in a nuclear reactor  

DOE Patents [OSTI]

A uranium-free fuel for a fast nuclear reactor comprising an alloy of Pu, Zr and Hf, wherein Hf is present in an amount less than about 10% by weight of the alloy. The fuel may be in the form of a Pu alloy surrounded by a Zr--Hf alloy or an alloy of Pu--Zr--Hf or a combination of both.

Crawford, Douglas C. (Idaho Falls, ID); Porter, Douglas L. (Idaho Falls, ID); Hayes, Steven L. (Idaho Falls, ID); Hill, Robert N. (Bolingbrook, IL)

1999-01-01T23:59:59.000Z

206

Nuclear design of the burst power ultrahigh temperature UF4 vapor core reactor system  

Science Journals Connector (OSTI)

Static and dynamic neutronic analyses are being performed as part of an integrated series of studies on an innovative burst power UF4 Ultrahigh Temperature Vapor Core Reactor (UTVR)/Disk Magnetohydrodynamic (MHD) generator for space nuclear power applications. This novel reactor concept operates on a direct closed Rankine cycle in the burst power mode (hundreds of MWe for thousands of seconds). The fuel/working fluid is a mixture of UF4 and metal fluoride. Preliminary calculations indicate high overall system efficiencies (?20%) small radiator size (?5 m2/MWe) and high specific power (?5 kWe/kg). Neutronic analysis has revealed a number of attractive features for this novel reactor concept. These include some unique and very effective inherent negative reactivity control mechanisms such as the vapor?fuel density power coefficient of reactivity the direct neutronic coupling among the multiple fissioning core regions (the central vapor core and the surrounding boiler columns) and the mass flow coupling feedback between the fissioning cores.

Samer D. Kahook; Edward T. Dugan

1991-01-01T23:59:59.000Z

207

Design of a Receding Horizon Control System for Nuclear Reactor Power Distribution  

SciTech Connect (OSTI)

A receding horizon control method is applied to the axial power distribution control in a pressurized water reactor. The basic concept of receding horizon control is to solve on-line, at each sampling instant, an optimization problem for a finite future and to implement the first optimal control input as the current control input. Thus, it is a suitable control strategy for time-varying systems. The reactor model used for computer simulations is a two-point xenon oscillation model based on the nonlinear xenon and iodine balance equations and a one-group, one-dimensional, neutron diffusion equation with nonlinear power reactivity feedback that adequately describes axial oscillations and treats the nonlinearities explicitly. The reactor core is axially divided into two regions, and each region has one input and one output and is coupled with the other region. Through numerical simulations, it is shown that the proposed control algorithm exhibits very fast tracking responses due to the step and ramp changes of axial target shape and also works well in a time-varying parameter condition.

Na, Man Gyun [Chosun University (Korea, Republic of)

2001-07-15T23:59:59.000Z

208

EA-1991: 10 CFR 433 and 10 CFR 435: Green Building Certification...  

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

Standards for the Design and Construction of New Federal Low-Rise Residential Buildings" (Green Building Certification Program) October 14, 2014 EA-1991: Final Environmental...

209

Design data needs modular high-temperature gas-cooled reactor. Revision 2  

SciTech Connect (OSTI)

The Design Data Needs (DDNs) provide summary statements for program management, of the designer`s need for experimental data to confirm or validate assumptions made in the design. These assumptions were developed using the Integrated Approach and are tabulated in the Functional Analysis Report. These assumptions were also necessary in the analyses or trade studies (A/TS) to develop selections of hardware design or design requirements. Each DDN includes statements providing traceability to the function and the associated assumption that requires the need.

NONE

1987-03-01T23:59:59.000Z

210

Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design  

SciTech Connect (OSTI)

The idea of developing fast spectrum reactors with molten lead (or lead alloy) as a coolant is not a new one. Although initially considered in the West in the 1950s, such technology was not pursued to completion because of anticipated difficulties associated with the corrosive nature of these coolant materials. However, in the Soviet Union, such technology was actively pursued during the same time frame (1950s through the 1980s) for the specialized role of submarine propulsion. More recently, there has been a renewal of interest in the West for such technology, both for critical systems as well as for Accelerator Driven Subcritical (ADS) systems. Meanwhile, interest in the former Soviet Union, primarily Russia, has remained strong and has expanded well beyond the original limited mission of submarine propulsion. This section reviews the past and current status of LFR development.

Smith, C

2010-02-22T23:59:59.000Z

211

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels -- Final Report under the International Nuclear Energy Research Initiative (I-NERI)  

SciTech Connect (OSTI)

The objective of this INERI project was to develop improved fuel behavior models for gas reactor coated-particle fuels and to explore improved coated-particle fuel designs that could be used reliably at very high burnups and potentially in gas-cooled fast reactors. Project participants included the Idaho National Engineering Laboratory (INEEL), Centre Étude Atomique (CEA), and the Massachusetts Institute of Technology (MIT). To accomplish the project objectives, work was organized into five tasks.

David Petti; Philippe Martin; Mayeul Phélip; Ronald Ballinger; Petti does not have NT account

2004-12-01T23:59:59.000Z

212

ACMP Handbook Change 2011-01 - Revised Financial Assistance Certification  

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

1-01 - Revised Financial Assistance Certification 1-01 - Revised Financial Assistance Certification 1 Chapter 4 Financial Assistance Certification Financial Assistance Qualification Standards Financial assistance award and administration within DOE is performed by both GS-1102 contracting personnel and non-GS1102 contracting personnel. In order to ensure that personnel in the financial assistance area possess the requisite skill set the Financial Assistance Program (FAP), certification is required. The Financial Assistance Certification Program (FACP) curriculum is designed to provide members with the necessary financial assistance skills and with experience in a wide range of thinking, approaches, and practices. Level IV is for only those individuals involved in the award and administration of Technology

213

Design of central irradiation facilities for the MITR-II research reactor  

E-Print Network [OSTI]

Design analysis studies have been made for various in-core irradiation facility designs which are presently used, or proposed for future use in the MITR-II. The information obtained includes reactivity effects, core flux ...

Meagher, Paul Christopher

1976-01-01T23:59:59.000Z

214

Portfolio for fast reactor collaboration  

SciTech Connect (OSTI)

The development of the LMFBR type reactor in the United Kingdom is reviewed. Design characteristics of a commercial demonstration fast reactor are presented and compared with the Super Phenix reactor.

Rippon, S.

1981-12-01T23:59:59.000Z

215

Secondary Heat Exchanger Design and Comparison for Advanced High Temperature Reactor  

SciTech Connect (OSTI)

The goals of next generation nuclear reactors, such as the high temperature gas-cooled reactor and advance high temperature reactor (AHTR), are to increase energy efficiency in the production of electricity and provide high temperature heat for industrial processes. The efficient transfer of energy for industrial applications depends on the ability to incorporate effective heat exchangers between the nuclear heat transport system and the industrial process heat transport system. The need for efficiency, compactness, and safety challenge the boundaries of existing heat exchanger technology, giving rise to the following study. Various studies have been performed in attempts to update the secondary heat exchanger that is downstream of the primary heat exchanger, mostly because its performance is strongly tied to the ability to employ more efficient conversion cycles, such as the Rankine super critical and subcritical cycles. This study considers two different types of heat exchangers—helical coiled heat exchanger and printed circuit heat exchanger—as possible options for the AHTR secondary heat exchangers with the following three different options: (1) A single heat exchanger transfers all the heat (3,400 MW(t)) from the intermediate heat transfer loop to the power conversion system or process plants; (2) Two heat exchangers share heat to transfer total heat of 3,400 MW(t) from the intermediate heat transfer loop to the power conversion system or process plants, each exchanger transfers 1,700 MW(t) with a parallel configuration; and (3) Three heat exchangers share heat to transfer total heat of 3,400 MW(t) from the intermediate heat transfer loop to the power conversion system or process plants. Each heat exchanger transfers 1,130 MW(t) with a parallel configuration. A preliminary cost comparison will be provided for all different cases along with challenges and recommendations.

Piyush Sabharwall; Ali Siahpush; Michael McKellar; Michael Patterson; Eung Soo Kim

2012-06-01T23:59:59.000Z

216

Reactor design for uniform chemical vapor deposition-grown films without substrate rotation  

DOE Patents [OSTI]

A quartz reactor vessel for growth of uniform semiconductor films includes a vertical, cylindrical reaction chamber in which a substrate-supporting pedestal provides a horizontal substrate-supporting surface spaced on its perimeter from the chamber wall. A cylindrical confinement chamber of smaller diameter is disposed coaxially above the reaction chamber and receives reaction gas injected at a tangent to the inside chamber wall, forming a helical gas stream that descends into the reaction chamber. In the reaction chamber, the edge of the substrate-supporting pedestal is a separation point for the helical flow, diverting part of the flow over the horizontal surface of the substrate in an inwardly spiraling vortex.

Wanlass, Mark (Golden, CO)

1987-01-01T23:59:59.000Z

217

Reactor design for uniform chemical vapor deposition-grown films without substrate rotation  

DOE Patents [OSTI]

A quartz reactor vessel for growth of uniform semiconductor films includes a vertical, cylindrical reaction chamber in which a substrate-supporting pedestal provides a horizontal substrate-supporting surface spaced on its perimeter from the chamber wall. A cylindrical confinement chamber of smaller diameter is disposed coaxially above the reaction chamber and receives reaction gas injected at a tangent to the inside chamber wall, forming a helical gas stream that descends into the reaction chamber. In the reaction chamber, the edge of the substrate-supporting pedestal is a separation point for the helical flow, diverting part of the flow over the horizontal surface of the substrate in an inwardly spiraling vortex.

Wanlass, M.

1985-02-19T23:59:59.000Z

218

ACQUISITION CERTIFICATION - FINANCIAL ASSISTANCE LEVEL I APPLICATION FOR CERTIFICATION  

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

ACQUISITION CERTIFICATION - FINANCIAL ASSISTANCE ACQUISITION CERTIFICATION - FINANCIAL ASSISTANCE LEVEL I APPLICATION FOR CERTIFICATION TECHNICAL PROJECT OFFICER LEVEL I PART A - EMPLOYEE INFORMATION Name (Last, First, Middle initial)_____________________________________________ Email Address____________________________________________________________ Phone __________________________________________________________________ Agency Name____________________________________________________________ Agency Address__________________________________________________________ Title, Series, Grade________________________________________________________ Education: Please specify degree and major: a. Degree: Associates: __; Bachelors __; Masters: __; Doctorate: __

219

Who Owns Renewable Energy Certificates?  

E-Print Network [OSTI]

Who Owns Renewable Energy Certificates? Edward Holt, RyanME 04079 edholt@igc.org Renewable energy certificates (RECs)convey the attributes of a renewable energy generator and

Holt, Edward; Wiser, Ryan; Bolinger, Mark

2006-01-01T23:59:59.000Z

220

Superior Energy Performance Certification Protocol  

Broader source: Energy.gov [DOE]

The Superior Energy Performance® (SEP™) Certification Protocol describes the purpose of the SEP program and defines the steps required for participation—from initial application through certification by an ANSI-ANAB accredited Verification Body.

Note: This page contains sample records for the topic "reactor design certification" 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

Incorporating reliability analysis into the design of passive cooling systems with an application to a gas-cooled reactor  

Science Journals Connector (OSTI)

A time-dependent reliability evaluation of a two-loop passive decay heat removal (DHR) system was performed as part of the iterative design process for a helium-cooled fast reactor. The system was modeled using RELAP5-3D. The uncertainties in input parameters were assessed and were propagated through the model using Latin hypercube sampling. An important finding was the discovery that the smaller pressure loss through the DHR heat exchanger than through the core would make the flow to bypass the core through one DHR loop, if two loops operated in parallel. This finding is a warning against modeling only one lumped DHR loop and assuming that n of them will remove n times the decay power. Sensitivity analyses revealed that there are values of some input parameters for which failures are very unlikely. The calculated conditional (i.e., given the LOCA) failure probability was deemed to be too high leading to the identification of several design changes to improve system reliability. This study is an example of the kinds of insights that can be obtained by including a reliability assessment in the design process. It is different from the usual use of PSA in design, which compares different system configurations, because it focuses on the thermal–hydraulic performance of a safety function.

Francisco J. Mackay; George E. Apostolakis; Pavel Hejzlar

2008-01-01T23:59:59.000Z

222

Design of an annular microchannel reactor (AMR) for hydrogen and/or syngas production via methane steam reforming  

Science Journals Connector (OSTI)

Abstract A bench-scale annular microchannel reactor (AMR) prototype with microchannel width of 0.3 mm and total catalyst length of 9.53 × 10?2 m active for the endothermic steam reforming of methane is presented. Experimental results at a steam to methane feed molar ratio of 3.3:1, reactor temperature of 1023 K, and pressure of 11 bar confirm catalyst power densities upwards of 1380 W per cm3 of catalyst at hydrogen yields >98% of thermodynamic equilibrium. A two-dimensional steady-state computational fluid dynamic model of the AMR prototype was validated using experimental data and subsequently employed to identify suitable operating conditions for an envisioned mass-production AMR design with 0.3 mm annular channel width and a single catalyst length of 254 mm. Thermal efficiencies, defined based upon methane and product hydrogen higher heating values (HHVs), of 72.7–57.7% were obtained from simulations for methane capacities of 0.5–2S LPM (space velocities of 195,000–782,000 h?1) at hydrogen yields corresponding to 99%–75% of equilibrium values. Under these conditions, analysis of local composition, temperature and pressure indicated that catalyst deactivation via coke formation or Nickel oxidation is not thermodynamically favorable. Lastly, initial analysis of an envisioned 10 kW autothermal reformer combining 19 parallel \\{AMRs\\} within a single methane-air combustion chamber, based upon existing manufacturing capabilities within Power & Energy, Inc., is presented.

Holly Butcher; Casey J.E. Quenzel; Luis Breziner; Jacques Mettes; Benjamin A. Wilhite; Peter Bossard

2014-01-01T23:59:59.000Z

223

certification_poststandardchange.pdf  

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

Certification Following a Change Certification Following a Change in the Applicable Energy or Water Conservation Standard The Energy Policy and Conservation Act of 1975, as amended, (EPCA or the ''Act'') authorizes the U. S. Department of Energy (DOE or the ''Department'') to enforce compliance with the energy conservation standards established for certain consumer products and commercial equipment. 42 U.S.C. §§ 6299-6305 (consumer products), 6316 (commercial and industrial equipment). To ensure that all covered products distributed in the United States comply with DOE's energy conservation standards, the Department has promulgated enforcement regulations, which include specific certification and compliance requirements. See Title 10 of the Code of Federal Regulations (10 CFR) part 430, subpart F; 10 CFR part 431,

224

STATE OF CALIFORNIA INSTALLATION CERTIFICATE  

E-Print Network [OSTI]

ENERGY COMMISSION INSTALLATION CERTIFICATE CF-6R-MECH-25-HERS Refrigerant Charge Verification ­ Standard to refrigerant charge verification for compliance, a MECH-24 Certificate (instead of this MECH-25 Certificate) should be used to demonstrate compliance with the refrigerant charge verification requirement. TMAH

225

Renewing Board Certification  

Science Journals Connector (OSTI)

Many persons argue that certification of a specialist indicates that he is up-to-date and competent at the time of examination but this does not prove that he continues indefinitely thereafter to be competent and aware of all important new knowledge in his field. This is obviously true and, as the certifying... Like gross anatomy class and the first night on call as an intern, the medical specialty board examination is a rite of passage for physicians. Dr. Robert Steinbrook reports that in 2005, board certification is in the midst of two fundamental changes.

Steinbrook R.

2005-11-10T23:59:59.000Z

226

ENERGY STAR plant certification | ENERGY STAR Buildings & Plants  

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

» ENERGY STAR plant certification » ENERGY STAR plant certification Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section Get started with ENERGY STAR Make the business case Build an energy management program Measure, track, and benchmark Improve energy performance Industrial service and product providers Earn recognition ENERGY STAR Partner of the Year Award

227

Contribution of Clinch River Breeder Reactor plant design and development to the LMFBR fuel cycle  

SciTech Connect (OSTI)

This paper describes how the CRBRP development and CRBRP focus of the LMFBR base technology program have led to advances in the state of the art in physics, thermal-hydraulics, structural analysis, core restraint, seismic analysis, and analysis of hypothetical core-disruptive accident energetics, all of which have been incorporated through disciplined engineering into the final CRBRP design. The total development in the US of fuels and materials, the analytical advances made on CRBRP design, and the incorporation of the latest experimental results into that design have put the US technology in general and the CRBRP design in particular at the forefront of technology. This has placed the US in a position to develop the most favorable LMFBR fuel cycle.

Riley, D.R.; Dickson, P.W.

1981-01-01T23:59:59.000Z

228

Preventing fuel failure for a beyond design basis accident in a fluoride salt cooled high temperature reactor  

E-Print Network [OSTI]

The fluoride salt-cooled high-temperature reactor (FHR) combines high-temperature coated-particle fuel with a high-temperature salt coolant for a reactor with unique market and safety characteristics. This combination can ...

Minck, Matthew J. (Matthew Joseph)

2013-01-01T23:59:59.000Z

229

Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input  

SciTech Connect (OSTI)

A conceptual design study of very small 350 MWth Gas-cooled Fast Reactors with Helium coolant has been performed. In this study Modified CANDLE burn-up scheme was implemented to create small and long life fast reactors with natural Uranium as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. The core with metallic fuel based was subdivided into 10 regions with the same volume. The fresh Natural Uranium is initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 is filled by fresh Natural Uranium fuel. This concept is basically applied to all axial regions. The reactor discharge burn-up is 31.8% HM. From the neutronic point of view, this design is in compliance with good performance.

Monado, Fiber, E-mail: fiber.monado@gmail.com [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung, Indonesia and Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Ariani, Menik [Dept. of Physics, Faculty of Mathematics and Natural Sciences, Sriwijaya University (Indonesia); Su'ud, Zaki; Waris, Abdul; Basar, Khairul; Permana, Sidik [Nuclear Physics and Biophysics Research Group, Dept. of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Bandung (Indonesia); Aziz, Ferhat [National Nuclear Energy Agency of Indonesia (BATAN) (Indonesia); Sekimoto, Hiroshi [CRINES, Tokyo Institute of Technology, O-okoyama, Meguro-ku, Tokyo 152-8550 (Japan)

2014-02-12T23:59:59.000Z

230

Reactor design for uniform chemical vapor deposition-grown films without substrate rotation  

SciTech Connect (OSTI)

A reactor vessel is described for chemical vapor deposition of a uniform semiconductor film on a substrate, comprising: a generally cylindrical reaction chamber for receiving a substrate and a flow of reaction gas capable of depositing a film on the substrate under the conditions of the chamber, the chamber having upper and lower portion and being oriented about a vertical axis; a supporting means having a substrate support surface generally perpendicular to the vertical axis for carrying the substrate within the lower portion of the reaction chamber in a predetermined relative position with respect to the upper portion of the reaction chamber, the upper portion including a cylindrically shaped confinement chamber. The confinement chamber has a smaller diameter than the lower portion of the reaction chamber and is positioned above the substrate support surface; and a means for introducing a reaction gas into the confinement chamber in a nonaxial direction so as to direct the reaction gas into the lower portion of the reaction chamber with a non-axial flow having a rotational component with respect to the vertical axis. In this way the reaction gas defines an inward vortex flow pattern with respect to the substrate surface.

Wanlass, M.

1987-03-17T23:59:59.000Z

231

Forensic Science Certificate  

E-Print Network [OSTI]

Forensic Science Certificate What do Forensic Scientists Do? Forensic scientists apply scientific conclusions about a crime based on the evidence. Some forensic scientists work in laboratories, while others complete their work on site, at the scene of the crime. Forensic scientists need to explain and justify

Saldin, Dilano

232

Conceptual design for a fast neutron ionization chamber for fusion reactor plasma diagnostics  

SciTech Connect (OSTI)

A conceptual design for a radiation-hard ``pointing`` fast neutron ionization chamber that is capable of delivering a 1 MHz countrate of T(D,n) events at ITER is given. The detector will use a {approximately}1 cm{sup 3} volume of CO{sub 2} fill gas at 0.1 bar pressure in a 500 V/cm electric field. The pulse widths will be {approximately}10 ns, enabling it to operate in a flux of {approximately} 6 {times} 10{sup 13} DT n/cm{sup 2}/sec. A special collimator design is used, giving an estimated angular resolution of 4.5 degrees HWHM.

Sailor, W.C.; Barnes, C.W.

1994-06-01T23:59:59.000Z

233

Estimation of the recycled power associated with the cryogenic refrigeration power of a fusion reactor based on TORE SUPRA experiment and ITER design  

Science Journals Connector (OSTI)

The refrigeration power associated with the superconducting magnets and cryopumps of a steady-state fusion reactor is not negligible. The power has to be minimized because it plays a role in the power station global efficiency and in the required amplification factor Q. On the one hand, the long plasma discharges obtained in December 2003 on TORE SUPRA give an insight of the cryogenic losses that might be expected for a steady-state fusion reactor equipped with superconducting magnets. The superfluid bath of the windings in TORE SUPRA allows a simple calorimetric estimation of the cryogenic losses through the temperature evolution of the bath during the long discharge. The different kinds of losses in TORE SUPRA are estimated, discussed and explained. Not all of them will be present in a real reactor. On the other hand, in the framework of ITER preparation, the magnet system and the associated refrigerator have been dimensioned taking into account again all kinds of cold losses. This exercise is important because ITER, by its size, could be relevant to the steady-state reactor situation regarding refrigeration. Based on TORE SUPRA experiment and ITER design it is, therefore, possible to propose for the first time a preliminary figure for the cryoplant power of a steady-state reactor. The order of magnitude of the cryoplant power is ten times lower than that of the fusion reactor recycled power which can be considered acceptable.

J.L. Duchateau; J.Y. Journeaux; F. Millet

2006-01-01T23:59:59.000Z

234

Fusion reactor theory and conceptual design. January 1982-May 1990 (A Bibliography from the INSPEC: Information Services for the Physics and Engineering Communities data base). Report for January 1982-May 1990  

SciTech Connect (OSTI)

This bibliography contains citations concerning theoretical and conceptual aspects of fusion reactor physics and designs. Conceptual design studies for a wide variety of fusion reactors are covered. Some experimental and demonstrational results of studies are considered. (This updated bibliography contains 290 citations, 189 of which are new entries to the previous edition.)

Not Available

1990-06-01T23:59:59.000Z

235

Advanced Nuclear Research Reactor  

SciTech Connect (OSTI)

This report describes technical modifications implemented by INVAP to improve the safety of the Research Reactors the company designs and builds.

Lolich, J.V.

2004-10-06T23:59:59.000Z

236

Seismic design technology for breeder reactor structures. Volume 1. Special topics in earthquake ground motion  

SciTech Connect (OSTI)

This report is divided into twelve chapters: seismic hazard analysis procedures, statistical and probabilistic considerations, vertical ground motion characteristics, vertical ground response spectrum shapes, effects of inclined rock strata on site response, correlation of ground response spectra with intensity, intensity attenuation relationships, peak ground acceleration in the very mean field, statistical analysis of response spectral amplitudes, contributions of body and surface waves, evaluation of ground motion characteristics, and design earthquake motions. (DLC)

Reddy, D.P.

1983-04-01T23:59:59.000Z

237

Certification Memos - DOE Directives, Delegations, and Requirements  

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

Chg 1 Certification for DOE P 456.1 Certification for DOE G 440.1-7A Certification for DOE G 441.1-1C Certification for DOE G 414.1-4 Certification for DOE M 441.1-1 and DOE O...

238

First Step to Spur U.S. Manufacturing of Small Modular Nuclear Reactors |  

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

First Step to Spur U.S. Manufacturing of Small Modular Nuclear First Step to Spur U.S. Manufacturing of Small Modular Nuclear Reactors First Step to Spur U.S. Manufacturing of Small Modular Nuclear Reactors January 25, 2012 - 5:06pm Addthis Brenda DeGraffenreid The Energy Department recently announced the first step toward manufacturing small modular nuclear reactors (SMRs) in the United States, demonstrating the Administration's commitment to advancing U.S. manufacturing leadership in low-carbon, next generation energy technologies and restarting the nation's nuclear industry. The release of a draft Funding Opportunity Announcement (FOA) last week presents supply-chain procurement opportunities for our nation's small businesses down the line, as industry provides input in advance of a full FOA on engineering, design certification, and licensing through a

239

Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels (I-NERI Annual Report)  

SciTech Connect (OSTI)

The objective of this INERI project is to develop improved fuel behavior models for gas reactor coated particle fuels and to develop improved coated-particle fuel designs that can be used reliably at very high burnups and potentially in fast gas-cooled reactors. Thermomechanical, thermophysical, and physiochemical material properties data were compiled by both the US and the French and preliminary assessments conducted. Comparison between U.S. and European data revealed many similarities and a few important differences. In all cases, the data needed for accurate fuel performance modeling of coated particle fuel at high burnup were lacking. The development of the INEEL fuel performance model, PARFUME, continued from earlier efforts. The statistical model being used to simulate the detailed finite element calculations is being upgraded and improved to allow for changes in fuel design attributes (e.g. thickness of layers, dimensions of kernel) as well as changes in important material properties to increase the flexibility of the code. In addition, modeling of other potentially important failure modes such as debonding and asphericity was started. A paper on the status of the model was presented at the HTR-2002 meeting in Petten, Netherlands in April 2002, and a paper on the statistical method was submitted to the Journal of Nuclear Material in September 2002. Benchmarking of the model against Japanese and an older DRAGON irradiation are planned. Preliminary calculations of the stresses in a coated particle have been calculated by the CEA using the ATLAS finite element model. This model and the material properties and constitutive relationships will be incorporated into a more general software platform termed Pleiades. Pleiades will be able to analyze different fuel forms at different scales (from particle to fuel body) and also handle the statistical variability in coated particle fuel. Diffusion couple experiments to study Ag and Pd transport through SiC were conducted. Analysis and characterization of the samples continues. Two active transport mechanisms are proposed: diffusion in SiC and release through SiC cracks or another, as yet undetermined, path. Silver concentration profiles determined by XPS analysis suggest diffusion within the SiC layer, most likely dominated by grain boundary diffusion. However, diffusion coefficients calculated from mass loss measurements suggest a much faster release path, postulated as small cracks or flaws that provide open paths with little resistance to silver migration. Work is ongoing to identify and characterize this path. Work on Pd behavior has begun and will continue next year.

Petti, David Andrew; Maki, John Thomas; Languille, Alain; Martin, Philippe; Ballinger, Ronald

2002-11-01T23:59:59.000Z

240

Civil Penalty Actions For Certification Violations Resolved | Department of  

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

Civil Penalty Actions For Certification Violations Resolved Civil Penalty Actions For Certification Violations Resolved Civil Penalty Actions For Certification Violations Resolved May 6, 2010 - 12:39pm Addthis Today, the Department of Energy announced that it had resolved civil penalty actions against four showerhead manufacturers for having violated the Department's water conservation certification regulations. To resolve these actions Zoe Industries, Altmans Products LLC, EZ-FLO International, and Watermark Designs Ltd. have now certified that their showerheads meet federal water conservation standards and collectively will pay civil penalties of $165,104. DOE had initiated cases against the four manufacturers on January 25th, alleging that they had failed to submit required documents to DOE demonstrating compliance with federal

Note: This page contains sample records for the topic "reactor design certification" 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.


241

Civil Penalty Actions For Certification Violations Resolved | Department of  

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

Civil Penalty Actions For Certification Violations Resolved Civil Penalty Actions For Certification Violations Resolved Civil Penalty Actions For Certification Violations Resolved May 6, 2010 - 12:39pm Addthis Today, the Department of Energy announced that it had resolved civil penalty actions against four showerhead manufacturers for having violated the Department's water conservation certification regulations. To resolve these actions Zoe Industries, Altmans Products LLC, EZ-FLO International, and Watermark Designs Ltd. have now certified that their showerheads meet federal water conservation standards and collectively will pay civil penalties of $165,104. DOE had initiated cases against the four manufacturers on January 25th, alleging that they had failed to submit required documents to DOE demonstrating compliance with federal

242

CERTIFICATE OF AUTHENTICITY  

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

CERTIFICATE OF AUTHENTICITY CERTIFICATE OF AUTHENTICITY I hereby certify that this transcript constitutes an accurate record of the full Council meeting of the National Coal Council held on November 14,2008 at the Westin Grand Hotel, Washington, D.C. ~ i c h a e l G. Mueller, Chair National Coal Council I NATIONAL COAL COUNCIL 1 FULL COUNCIL MEETING FRIDAY NOVEMBER 14, 2 0 0 8 The Full Council meeting convened at 9 : 0 0 a.m. in the Washington Ballroom of the Westin Grand Hotel, 2 3 5 0 M Street, NW, Washington, DC, Chair Michael G. Mueller presiding. ATTENDEES: MIKE MUELLER, Arneren Energy Fuels & Services Company, Chair RICH EIMER, Dynegy Inc., Vice-Chair ROBERT BECK, National Coal Council, Executive Vice-President SY ALI, Clean Energy Consulting BARB ALTIZER, Eastern Coal Council

243

certification_samplingplan.pdf  

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

Applicable Sampling Plan Applicable Sampling Plan for Certification of Consumer Products The Energy Policy and Conservation Act of 1975, as amended, (EPCA or the ''Act'') authorizes the Department of Energy (DOE or the ''Department'') to enforce compliance with the energy conservation standards established for certain consumer products and commercial equipment. 42 U.S.C. §§ 6299-6305. To ensure that all covered products distributed in the United States comply with DOE's energy conservation standards, the Department has promulgated enforcement regulations, which include specific certification and compliance requirements. See 10 CFR part 430, subpart F. Each manufacturer must certify that each basic model meets the applicable energy conservation standard before distributing that model in commerce. 10 CFR 430.62(a). To

244

Certification/enforcement analysis  

SciTech Connect (OSTI)

Industry compliance with minimum energy efficiency standards will be assured through a two-part program approach of certification and enforcement activities. The technical support document (TSD) presents the analyses upon which the proposed rule for assuring that consumer product comply with applicable energy efficiency standards is based. Much of the TSD is based upon support provided DOE by Vitro Laboratories. The OAO Corporation provided additional support in the development of the sampling plan incorporated in the proposed rule. Vitro's recommended approach to appliance certification and enforcement, developed after consideration of various program options, benefits, and impacts, establishes the C/E program framework, general criteria, and procedures for assuring a specified level of energy efficiency performance of covered consumer products. The results of the OAO analysis are given in Volume II of the TSD.

None

1980-06-01T23:59:59.000Z

245

Certification reporting forms  

SciTech Connect (OSTI)

The required information and formats for the certification report including the cover sheet, compliance statement, and body of the report are given in this document. The body of the reports is different for each product. There are no product-to-product differences in the forms of the other parts of the reports. The products covered in this document include: furnaces, water heaters, refrigerator-freezers, central air conditioners, room air conditioners, and freezers.

Not Available

1981-02-18T23:59:59.000Z

246

Building Operator Certification  

E-Print Network [OSTI]

programmed settings review ? Verify damper settings ? Check static pressure sensor calibration ? Review occupant complaint records and remedies ? Review established temperature set points HVAC Controls Operational Review ESL-KT-13-12-49 CATEE 2013: Clean... Operator Certification Energy Efficiency through Operator Training BOC Has Two Levels • Level I: Building Systems Maintenance ? Two or more years experience (5 yrs avg) ? Outcome: Basic understanding of electrical, HVAC and lighting systems...

Lilley, D.

2013-01-01T23:59:59.000Z

247

Design of Complex Systems to Achieve Passive Safety: Natural Circulation Cooling of Liquid Salt Pebble Bed Reactors  

E-Print Network [OSTI]

Safety. The Accident at TEPCO’s Fukushima Nuclear Power2: Accident and Thermal Fluids Analysis PIRTs. (Nuclearmolten nuclear reactor core debris following accidents such

Scarlat, Raluca Olga

2012-01-01T23:59:59.000Z

248

Design Study of Pb-Bi-Cooled and NaK-Cooled Small Reactors: PBWFR and DSFR  

SciTech Connect (OSTI)

The liquid lead-bismuth eutectic (Pb-Bi) has good compatibility with water, which is different from sodium. It is expected that the Pb-Bi could be used as a coolant of the deep sea fast reactor (DSFR) and the Pb-Bi- cooled direct contact boiling water small fast reactor (PBWFR). Physics analysis of the Pb-Bi-cooled small reactor cores with and without inner control rods was performed using the computer program of General Purpose Neutronics Code System (SRAC95) developed by Japan Atomic Energy Research Institute (JAERI). The coolant of Pb-Bi seems to be good as well as NaK for small reactors. (authors)

Otsubo, Akira; Takahashi, Minoru [N1-18, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)

2004-07-01T23:59:59.000Z

249

Catalytic reactor  

DOE Patents [OSTI]

A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

2009-03-10T23:59:59.000Z

250

Equipment Certification | Open Energy Information  

Open Energy Info (EERE)

Equipment Certification Equipment Certification Jump to: navigation, search Policies requiring renewable energy equipment to meet certain standards serve to protect consumers from buying inferior equipment. These requirements not only benefit consumers; they also protect the renewable energy industry by making it more difficult for substandard systems to reach the market. [1] Equipment Certification Incentives CSV (rows 1 - 19) Incentive Incentive Type Place Applicable Sector Eligible Technologies Active Canada Oil and Gas Operations Act (Canada) Environmental Regulations Equipment Certification Fees Generating Facility Rate-Making Generation Disclosure Industry Recruitment/Support Safety and Operational Guidelines Siting and Permitting Canada Commercial Construction Developer

251

End Use and Fuel Certification  

Broader source: Energy.gov [DOE]

Breakout Session 2: Frontiers and Horizons Session 2–B: End Use and Fuel Certification John Eichberger, Vice President of Government Relations, National Association for Convenience Stores

252

Nuclear Reactor (atomic reactor)  

Science Journals Connector (OSTI)

A nuclear reactor splits Uranium or Plutonium nuclei, and the...235 is fissionable but more than 99% of the naturally occurring Uranium is U238 that makes enrichment mandatory. In some reactors U238 and Thorium23...

2008-01-01T23:59:59.000Z

253

The Fast-spectrum Transmutation Experimental Facility FASTEF: Main design achievements (part 2: Reactor building design and plant layout) within the FP7-CDT collaborative project of the European Commission  

SciTech Connect (OSTI)

MYRRHA (Multi-purpose hybrid Research Reactor for High-tech Applications) is the flexible experimental accelerator-driven system (ADS) in development at SCK-CEN in replacement of its material testing reactor BR2. SCK-CEN in association with 17 European partners from industry, research centres and academia, responded to the FP7 (Seventh Framework Programme) call from the European Commission to establish a Central Design Team (CDT) for the design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) able to demonstrate efficient transmutation and associated technology through a system working in subcritical and/or critical mode. The project has started on April 01, 2009 for a period of three years. In this paper, we present the latest concept of the reactor building and the plant layout. The FASTEF facility has evolved quite a lot since the intermediate reporting done at the ICAPP'10 and ICAPP'11 conferences 1,2. Many iterations have been performed to take into account the safety requirements. The present configuration enables an easy operation and maintenance of the facility, including the possibility to change large components of the reactor. In a companion paper 3, we present the latest configuration of the reactor core and primary system. (authors)

De Bruyn, D.; Engelen, J. [Belgian Nuclear Research Centre SCK CEN, Boeretang 200, 2400 Mol (Belgium); Ortega, A.; Aguado, M. P. [Empresarios Agrupados A.I.E., Magallanes 3, 28015 Madrid (Spain)

2012-07-01T23:59:59.000Z

254

Green Power Network: Renewable Energy Certificates (RECs)  

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

Table of Retail Products Table of Retail Products Table of Commercial Certificate Marketers List of REC Marketers REC Prices National Renewable Energy Certificate Tracking Systems Map Carbon Offsets State Policies Renewable Energy Certificates (RECs) Renewable energy certificates (RECs), also known as renewable energy credits, green certificates, green tags, or tradable renewable certificates, represent the environmental attributes of the power produced from renewable energy projects and are sold separate from commodity electricity. Customers can buy green certificates whether or not they have access to green power through their local utility or a competitive electricity marketer. And they can purchase green certificates without having to switch electricity suppliers. Table of Retail Products

255

Building Technologies Office: Implementation, Certification and Enforcement  

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

Implementation, Implementation, Certification and Enforcement to someone by E-mail Share Building Technologies Office: Implementation, Certification and Enforcement on Facebook Tweet about Building Technologies Office: Implementation, Certification and Enforcement on Twitter Bookmark Building Technologies Office: Implementation, Certification and Enforcement on Google Bookmark Building Technologies Office: Implementation, Certification and Enforcement on Delicious Rank Building Technologies Office: Implementation, Certification and Enforcement on Digg Find More places to share Building Technologies Office: Implementation, Certification and Enforcement on AddThis.com... About Standards & Test Procedures Implementation, Certification & Enforcement Standardized Templates for Reporting Test Results

256

Ecotourism and Certification: Setting Standards in Practice  

E-Print Network [OSTI]

Review: Ecotourism and Certification: Setting Standards inMartha Honey (Ed. ). Ecotourism and Certification: SettingAlkaline paper. Tourism and ecotourism are growing rapidly,

Hook, Robert D.

2004-01-01T23:59:59.000Z

257

FAQS Qualification Card - NNSA Package Certification Engineer...  

Office of Environmental Management (EM)

Qualification Card - NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification...

258

Designing an enzymatic oscillator: Bistability and feedback controlled oscillations with glucose oxidase in a continuous flow stirred tank reactor  

E-Print Network [OSTI]

oxidase in a continuous flow stirred tank reactor Vladimir K. Vanag,a David G. Míguez,b and Irving R as the flow rate is varied in a continuous flow stirred tank reactor. Oscillations in pH can be obtained

Epstein, Irving R.

259

Certificate in Transit Management and  

E-Print Network [OSTI]

Certificate in Transit Management and Operations UMass Transit, in partnership with the UMass Transportation Center and CTTransit, are pleased to offer "A Certificate in Transit Management and Operations Engineering and the School of Management - Internships with UMass Transit and CTTransit - A summer workshop

Massachusetts at Amherst, University of

260

Certificate in Transit Management and  

E-Print Network [OSTI]

Certificate in Transit Management and Operations UMass Transit, in partnership with the UMass Transportation Center and CTTransit, are pleased to offer "A Certificate in Transit Management and Operations contract to provide transit management services in Hartford and other cities in Connecticut. CTTRANSIT

Massachusetts at Amherst, University of

Note: This page contains sample records for the topic "reactor design certification" 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

Quantum Certificate Complexity Scott Aaronson  

E-Print Network [OSTI]

(f) R0 (f), and that QE (f) D (f). If f is partial (i.e. Dom (f) = {0, 1}n ), then Q2 (f) canQuantum Certificate Complexity Scott Aaronson Computer Science Division University of California for all i S then f (Y ) = f (X). Then CX (f) is the mini- mum size of a certificate for X, and C (f

Aaronson, Scott

262

Postgraduate Certificate in Geothermal Energy  

E-Print Network [OSTI]

Postgraduate Certificate in Geothermal Energy Technology The University of Auckland The University with this dynamic industry. Why this programme? The Postgraduate Certificate in Geothermal Energy Technology of developing geothermal energy fields. The course content draws on recent advances in technology and leading

Auckland, University of

263

Radiation Shielding Design and Orientation Considerations for a 1 kWe Heat Pipe Cooled Reactor Utilized to Bore Through the Ice Caps of Mars  

SciTech Connect (OSTI)

The goal in designing any space power system is to develop a system able to meet the mission requirements for success while minimizing the overall costs. The mission requirements for the this study was to develop a reactor (with Stirling engine power conversion) and shielding configuration able to fit, along with all the other necessary science equipment, in a Cryobot 3 m high with {approx}0.5 m diameter hull, produce 1 kWe for 5yrs, and not adversely affect the mission science by keeping the total integrated dose to the science equipment below 150 krad. Since in most space power missions the overall system mass dictates the mission cost, the shielding designs in this study incorporated Martian water extracted at the startup site in order to minimize the tungsten and LiH mass loading at launch. Different reliability and mass minimization concerns led to three design configuration evolutions. With the help of implementing Martian water and configuring the reactor as far from the science equipment as possible, the needed tungsten and LiH shield mass was minimized. This study further characterizes the startup dose and the necessary mission requirements in order to ensure integrity of the surface equipment during reactor startup phase.

Fensin, Michael L. [Department of Nuclear and Radiological Engineering, University of Florida, Gainesville, FL 32611 (United States); Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Elliott, John O. [Jet Propulsion Laboratories, California Institute of Technology, Pasedena, Ca 91109 (United States); Lipinski, Ronald J. [Sandia National Laboratory, Albuquerque, NM 87185 (United States); Poston, David I. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

2006-01-20T23:59:59.000Z

264

Thermal hydraulic design of a 2400 MW t?h? direct supercritical CO?-cooled fast reactor  

E-Print Network [OSTI]

The gas cooled fast reactor (GFR) has received new attention as one of the basic concepts selected by the Generation-IV International Forum (GIF) for further investigation. Currently, the reference GFR is a helium-cooled ...

Pope, Michael A. (Michael Alexander)

2006-01-01T23:59:59.000Z

265

Application of USNRC NUREG/CR-6661 and draft DG-1108 to evolutionary and advanced reactor designs  

SciTech Connect (OSTI)

For the seismic design of evolutionary and advanced nuclear reactor power plants, there are definite financial advantages in the application of USNRC NUREG/CR-6661 and draft Regulatory Guide DG-1108. NUREG/CR-6661, 'Benchmark Program for the Evaluation of Methods to Analyze Non-Classically Damped Coupled Systems', was by Brookhaven National Laboratory (BNL) for the USNRC, and Draft Regulatory Guide DG-1108 is the proposed revision to the current Regulatory Guide (RG) 1.92, Revision 1, 'Combining Modal Responses and Spatial Components in Seismic Response Analysis'. The draft Regulatory Guide DG-1108 is available at http://members.cox.net/apolloconsulting, which also provides a link to the USNRC ADAMS site to search for NUREG/CR-6661 in text file or image file. The draft Regulatory Guide DG-1108 removes unnecessary conservatism in the modal combinations for closely spaced modes in seismic response spectrum analysis. Its application will be very helpful in coupled seismic analysis for structures and heavy equipment to reduce seismic responses and in piping system seismic design. In the NUREG/CR-6661 benchmark program, which investigated coupled seismic analysis of structures and equipment or piping systems with different damping values, three of the four participants applied the complex mode solution method to handle different damping values for structures, equipment, and piping systems. The fourth participant applied the classical normal mode method with equivalent weighted damping values to handle differences in structural, equipment, and piping system damping values. Coupled analysis will reduce the equipment responses when equipment, or piping system and structure are in or close to resonance. However, this reduction in responses occurs only if the realistic DG-1108 modal response combination method is applied, because closely spaced modes will be produced when structure and equipment or piping systems are in or close to resonance. Otherwise, the conservatism in the current Regulatory Guide 1.92, Revision 1, will overshadow the advantage of coupled analysis. All four participants applied the realistic modal combination method of DG-1108. Consequently, more realistic and reduced responses were obtained. (authors)

Chang 'Apollo', Chen [Apollo Consulting, Inc., Surprise, AZ 85374-4605 (United States)

2006-07-01T23:59:59.000Z

266

The Graduate Certificate in African Diaspora  

E-Print Network [OSTI]

to their di- asporic conditions. A successful recipi- ent of a Graduate Certificate in African Diaspora

Massachusetts at Amherst, University of

267

Journey to Leadership Certificate Program Application  

Broader source: Energy.gov [DOE]

Application packet for Journey to Leadership Certificate Program Pilot course, includes description.

268

Utilization of Refractory Metals and Alloys in Fusion Reactor Structures  

Science Journals Connector (OSTI)

In design of fusion reactors, structural material selection is very crucial to improve reactor’s performance. Different types of materials have been proposed for use in fusion reactor structures. Among these mate...

Mustafa Übeyli; ?enay Yalç?n

2006-12-01T23:59:59.000Z

269

Solar Equipment Certification | Department of Energy  

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

Solar Equipment Certification Solar Equipment Certification Solar Equipment Certification < Back Eligibility Commercial Construction Installer/Contractor Residential Savings Category Heating & Cooling Commercial Heating & Cooling Solar Heating Water Heating Program Info State Minnesota Program Type Equipment Certification Provider Minnesota Department of Commerce Minnesota law requires that all active solar space-heating and water-heating systems, sold, offered for sale, or installed on residential and commercial buildings in the state meet Solar Rating and Certification Corporation (SRCC) standards. Specifically, the rule references SRCC's "Operating Guidelines" pertaining to collector certification and system certification: OG-100 and OG-300, respectively. Local building officials

270

EPA Redesigns Conversion Certification Policies  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

EPA Redesigns EPA Redesigns Conversion Certification Policies At a recent meeting held in Washington, DC, officials from the U.S. Environmental Protection Agency (EPA) opened dialogue about proposed changes to its emission certification policies that affect alternative fuel vehicles (AFVs). "We are trying to accommo- date the Energy Policy Act (EPAct) and Executive Order requirements while trying to change enforce- ment policies and guidance with respect to conversions," said Rich Ackerman of EPA's Enforcement Office. The meeting, attended by representatives of more than 60 organizations, was held to discuss actions addressing AFV emission certification. Specifically, topics included * Conversion emissions perfor- mance data * Status of environmental laws pertaining to alternative fuel

271

Power Reactor Progress  

Science Journals Connector (OSTI)

Argonne kicks off EBWR; Allis-Chalmers plans power reactor using both nuclear and conventional fuels ... NUCLEAR POWER took two giant steps last week. ... Just as the first nuclear power system in the U. S. designed and built solely for the generation of electric power went into full operation at Argonne, Allis-Chalmers came up with a new twist in power reactors—a controlled recirculation boiling reactor (CRBR) using both nuclear and conventional fuels (C&EN, Feb. 18, page 7). ...

1957-02-25T23:59:59.000Z

272

Renewable Energy Certificate Program  

SciTech Connect (OSTI)

This project was primarily to develop and implement a curriculum which will train undergraduate and graduate students at the University seeking a degree as well as training for enrollees in a special certification program to prepare individuals to be employed in a broad range of occupations in the field of renewable energy and energy conservation. Curriculum development was by teams of Saint Francis University Faculty in the Business Administration and Science Departments and industry experts. Students seeking undergraduate and graduate degrees are able to enroll in courses offered within these departments which will combine theory and hands-on training in the various elements of wind power development. For example, the business department curriculum areas include economic modeling, finance, contracting, etc. The science areas include meteorology, energy conversion and projection, species identification, habitat protection, field data collection and analysis, etc.

Gwendolyn S. Andersen

2012-07-17T23:59:59.000Z

273

B Reactor | Department of Energy  

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

Operational Management » History » Manhattan Project » Signature Operational Management » History » Manhattan Project » Signature Facilities » B Reactor B Reactor B Reactor Completed in September 1944, the B Reactor was the world's first large-scale plutonium production reactor. As at Oak Ridge, the need for labor turned Hanford into an atomic boomtown, with the population reaching 50,000 by summer 1944. Similar to the X-10 Graphite Reactor at Oak Ridge in terms of loading and unloading fuel, the B Reactor was built on a much larger scale and used water rather than air as a coolant. Whereas the X-10 had an initial design output of 1,000 kilowatts, the B Reactor was designed to operate at 250,000 kilowatts. Consisting of a 28- by 36-foot, 1,200-ton graphite cylinder lying on its side, the reactor was penetrated through its

274

Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2008  

SciTech Connect (OSTI)

This report documents progress made during FY 2008 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in reactor performance from the current level. Results of selected benchmark studies imply that calculations of LEU performance are accurate. Scoping experiments with various manufacturing methods for forming the LEU alloy profile are presented.

Primm, Trent [ORNL; Chandler, David [ORNL; Ilas, Germina [ORNL; Miller, James Henry [ORNL; Sease, John D [ORNL; Jolly, Brian C [ORNL

2009-03-01T23:59:59.000Z

275

CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues  

SciTech Connect (OSTI)

Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule ({section}50.62); (2) station blackout ({section}50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term ({section}50.34(f) and {section}100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements ({section}50.55a, etc); (6) ECCS acceptance criteria ({section}50.46)(b); (7) combustible gas control ({section}50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle ({section}51.51); and (11) (standards {section}50.55a).

Charak, I.; Kier, P.H. [Argonne National Lab., IL (United States)

1995-04-01T23:59:59.000Z

276

LEED Certification | Open Energy Information  

Open Energy Info (EERE)

Certification Certification Jump to: navigation, search Name LEED Certification/U.S. Green Building Council Address U.S. Green Building Council 2101 L Street, NW Suite 500 Place Washington, District of Columbia Zip 20037 Sector Buildings Product Certification system Website http://www.usgbc.org/DisplayPa Coordinates 38.889471°, -77.0578855° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.889471,"lon":-77.0578855,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

277

Summary Protocol: Identification, Characterization, Designation, Remedial  

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

Summary Protocol: Identification, Characterization, Designation, Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification (January 1986) Summary Protocol: Identification, Characterization, Designation, Remedial Action, Certification (January 1986) More Documents & Publications Supplement No. 1 to the FUSRAP Summary Protocol - Designation/Elimination Protocol Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at

278

DataTrends: ENERGY STAR Certification | ENERGY STAR Buildings & Plants  

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

ENERGY STAR Certification ENERGY STAR Certification Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In This Section Campaigns Commercial building design Communications resources Energy management guidance Financial resources Portfolio Manager Products and purchasing Recognition Research and reports Service and product provider (SPP) resources Success stories Target Finder

279

Earn ENERGY STAR certification | ENERGY STAR Buildings & Plants  

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

Earn ENERGY STAR certification Earn ENERGY STAR certification Secondary menu About us Press room Contact Us Portfolio Manager Login Facility owners and managers Existing buildings Commercial new construction Industrial energy management Small business Service providers Service and product providers Verify applications for ENERGY STAR certification Design commercial buildings Energy efficiency program administrators Commercial and industrial program sponsors Associations State and local governments Federal agencies Tools and resources Training In this section How can we help you? Build an energy program Improve building and plant performance Earn the ENERGY STAR and other recognition Benchmark energy use ENERGY STAR in action Communicate and educate ENERGY STAR communications toolkit Bring Your Green to Work with ENERGY STAR

280

Application of RCC-MR for the structural design of tube sheet of intermediate heat exchanger for a sodium cooled fast reactor  

Science Journals Connector (OSTI)

Abstract The structural mechanics behavior of tube sheets of a sodium to sodium heat exchanger for a fast reactor, with circular tube holes pattern, less addressed subject in the literature, is investigated in detail. The tube sheet design rules recommended in the French design code RCC-MR-2007 and the associated solid mechanics basis are explained. A finite element analysis of tube sheets of intermediate heat exchanger of a typical 500 MWe pool type fast reactor is presented to study the effects of some specific parameters viz., (i) small solid rim portion with connecting shell and (ii) grooves on rim area. For the analysis, the distribution of holes on the last row is assumed to be symmetric and axial stiffening of tubes on tube sheet is included toward realistic estimation of stresses in the tube sheets. The effects are studied on the primary and secondary stresses induced along the interface between solid to perforated region. The aspects covered include linearization of radial and circumferential stress components, thereby deriving primary membrane and bending stress intensities along the radial directions with particular focus at the interfaces between solid portions and perforated portions including the effect of filet radius at the junction of tube sheet and shell. These investigations thus help to optimize the design of IHX tube sheets with high confidence. The analysis has been carried out by CAST3M, a structure analysis software granted by CEA, France.

Suman Gupta; P. Chellapandi

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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.


281

UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY  

E-Print Network [OSTI]

UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY GREEN DEPARTMENT CERTIFICATION INSTRUCTIONS & FORMS PART II & III: GREEN DEPARTMENT CERTIFICATION #12; UAF Green Department of 30 awards a Green certification

Hartman, Chris

282

New fast-reactor approach. [LMFBR  

SciTech Connect (OSTI)

The design parameters for a 1000 MW LMFBR type reactor are presented. The design requires the multiple primary coolant pumps and heat exchangers to be located around the core within the reactor vessel.

Folkrod, J.R.; Kann, W.J.; Klocksieben, R.H.

1983-01-01T23:59:59.000Z

283

Grant County PUD - EnergyStar New Home Certification Program | Department  

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

EnergyStar New Home Certification Program EnergyStar New Home Certification Program Grant County PUD - EnergyStar New Home Certification Program < Back Eligibility Construction Residential Savings Category Appliances & Electronics Heating & Cooling Home Weatherization Construction Commercial Weatherization Commercial Heating & Cooling Design & Remodeling Heat Pumps Program Info State District of Columbia Program Type Utility Rebate Program Rebate Amount Energy Star Manufactured Homes: $500 Site-Built Energy Star NW Homes with Heat Pump: $2,100 Heat Pumps: $200/ton Clothes Washers: $70 Provider Grant County PUD Grant County PUD offers incentives to qualifying customers through the Energy Star Home Certification Program. The Energy Star certification is available for both new site-built homes and new manufactured homes.

284

New Year, New Certification Opportunities for Home Energy Workers...  

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

professional certifications. These new certifications cover the four most common home energy and weatherization job classifications: quality control inspectors, energy...

285

Design and Certification of Industrial Predictive Controllers  

E-Print Network [OSTI]

.g. a car moving over a terrain with changing slopes. Many others can be viewed as a composition of interacting subsystems like harvester machines, wind mills etc. Further in this thesis, practical solutions for controlling such nonlinear and distributed...

Dutta, Abhishek

2014-09-24T23:59:59.000Z

286

Ensuring Physicians' Competence — Is Maintenance of Certification the Answer?  

Science Journals Connector (OSTI)

Pressed by their leaders, external stakeholders, and a public troubled by lapses in the quality of care and unsustainable cost increases, physicians are facing stiffer challenges in initiatives designed to link more closely the goals of learning with the delivery of better care and measures of greater... Maintenance of certification programs sponsored by the American Board of Medical Specialties and its member boards were designed to improve and assess physicians' clinical competence. The authors discuss the history of MOC and current controversies.

Iglehart J.K.; Baron R.B.

2012-12-27T23:59:59.000Z

287

Reactor operation safety information document  

SciTech Connect (OSTI)

The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

Not Available

1990-01-01T23:59:59.000Z

288

Microsoft Word - CERTIFICATION LEVEL REQUIREMENTS.doc  

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

CERTIFICATION LEVEL CERTIFICATION LEVEL The CEG is intended to provide program secretarial officers and field element managers (including operations offices, site offices, area offices, project offices, and service centers) with the requirements and guidelines for evaluating PMCDP candidate competencies and requests for equivalencies at all four certification levels and continuing education. Persons planning to be certified under the PMCDP may attain certification levels with the following total project cost (TPC) limits: * Certification Level 4: TPC exceeding $400 million (M) * Certification Level 3: TPC greater than $100M and equal to or less than $400M * Certification Level 2: TPC greater than $20M and equal to or less than $100M * Certification Level 1: TPC greater than $5M and equal to or less than $20M

289

Political Science Departmental Distinction Certificate Program  

E-Print Network [OSTI]

Political Science Departmental Distinction Certificate Program Purpose: The goal of the Departmental Distinction Certificate Program is to challenge and recognize excellent Political Science students both for their academic and academic- related work. Eligibility: Students majoring in Political Science

Elsherbeni, Atef Z.

290

FINALCOMMISSIONDECISION Application For Certification (08-AFC-1)  

E-Print Network [OSTI]

FINALCOMMISSIONDECISION Application For Certification (08-AFC-1) Kings County CALIFORNIA ENERGY For Certification (08-AFC-1) Kings County CALIFORNIA ENERGY COMMISSION AVENAL ENERGY DECEMBER 2009 (08-AFC-1) CEC

291

WICF Certification, Compliance and Enforcement webinar | Department...  

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

DOE Certification, Compliance, and Enforcement Overview for Refrigerators, Refrigerator-Freezers, Freezers, Dehumidifiers, Room Air Conditioners, Clothes Washers, Clothes...

292

Optimization Online - Certificates of Optimality and Sensitivity ...  

E-Print Network [OSTI]

Dec 9, 2014 ... Certificates of Optimality and Sensitivity Analysis using Generalized Subadditive Generator Functions: A test study on Knapsack Problems.

Babak Moazzez

2014-12-09T23:59:59.000Z

293

Radiation physics and shielding codes and analyses applied to design-assist and safety analyses of CANDU{sup R} and ACR{sup TM} reactors  

SciTech Connect (OSTI)

This paper discusses the radiation physics and shielding codes and analyses applied in the design of CANDU and ACR reactors. The focus is on the types of analyses undertaken rather than the inputs supplied to the engineering disciplines. Nevertheless, the discussion does show how these analyses contribute to the engineering design. Analyses in radiation physics and shielding can be categorized as either design-assist or safety and licensing (accident) analyses. Many of the analyses undertaken are designated 'design-assist' where the analyses are used to generate recommendations that directly influence plant design. These recommendations are directed at mitigating or reducing the radiation hazard of the nuclear power plant with engineered systems and components. Thus the analyses serve a primary safety function by ensuring the plant can be operated with acceptable radiation hazards to the workers and public. In addition to this role of design assist, radiation physics and shielding codes are also deployed in safety and licensing assessments of the consequences of radioactive releases of gaseous and liquid effluents during normal operation and gaseous effluents following accidents. In the latter category, the final consequences of accident sequences, expressed in terms of radiation dose to members of the public, and inputs to accident analysis, e.g., decay heat in fuel following a loss-of-coolant accident, are also calculated. Another role of the analyses is to demonstrate that the design of the plant satisfies the principle of ALARA (as low as reasonably achievable) radiation doses. This principle is applied throughout the design process to minimize worker and public doses. The principle of ALARA is an inherent part of all design-assist recommendations and safety and licensing assessments. The main focus of an ALARA exercise at the design stage is to minimize the radiation hazards at the source. This exploits material selection and impurity specifications and relies heavily on experience and engineering judgement, consistent with the ALARA philosophy. Special care is taken to ensure that the best estimate dose rates are used to the extent possible when applying ALARA. Provisions for safeguards equipment are made throughout the fuel-handling route in CANDU and ACR reactors. For example, the fuel bundle counters rely on the decay gammas from the fission products in spent-fuel bundles to record the number of fuel movements. The International Atomic Energy Agency (IAEA) Safeguards system for CANDU and ACR reactors is based on item (fuel bundle) accounting. It involves a combination of IAEA inspection with containment and surveillance, and continuous unattended monitoring. The spent fuel bundle counter monitors spent fuel bundles as they are transferred from the fuelling machine to the spent fuel bay. The shielding and dose-rate analysis need to be carried out so that the bundle counter functions properly. This paper includes two codes used in criticality safety analyses. Criticality safety is a unique phenomenon and codes that address criticality issues will demand specific validations. However, it is recognised that some of the codes used in radiation physics will also be used in criticality safety assessments. (authors)

Aydogdu, K.; Boss, C. R. [Atomic Energy of Canada Limited, Sheridan Science and Technology Park, Mississauga, Ont. L5K 1B2 (Canada)

2006-07-01T23:59:59.000Z

294

Orion Registrar, Inc., USA Certificate of Registration  

E-Print Network [OSTI]

Orion Registrar, Inc., USA Certificate of Registration D'fus Js lo cerl!fy !he Occupalional Golden, Colorado 80401 USA J fas been assessedby Orion !l?egislrar and}Oundlobe 1i2 compliance mi-456-6681 To authenticate this certificate please visit www.orion4value.com #12;Orion Registrar, Inc., USA Certificate

295

Design Study for a Low-enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2007  

SciTech Connect (OSTI)

This report documents progress made during fiscal year 2007 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low enriched uranium fuel (LEU). Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. A high volume fraction U/Mo-in-Al fuel could attain the same neutron flux performance as with the current, HEU fuel but materials considerations appear to preclude production and irradiation of such a fuel. A diffusion barrier would be required if Al is to be retained as the interstitial medium and the additional volume required for this barrier would degrade performance. Attaining the high volume fraction (55 wt. %) of U/Mo assumed in the computational study while maintaining the current fuel plate acceptance level at the fuel manufacturer is unlikely, i.e. no increase in the percentage of plates rejected for non-compliance with the fuel specification. Substitution of a zirconium alloy for Al would significantly increase the weight of the fuel element, the cost of the fuel element, and introduce an as-yet untried manufacturing process. A monolithic U-10Mo foil is the choice of LEU fuel for HFIR. Preliminary calculations indicate that with a modest increase in reactor power, the flux performance of the reactor can be maintained at the current level. A linearly-graded, radial fuel thickness profile is preferred to the arched profile currently used in HEU fuel because the LEU fuel media is a metal alloy foil rather than a powder. Developments in analysis capability and nuclear data processing techniques are underway with the goal of verifying the preliminary calculations of LEU flux performance. A conceptual study of the operational cost of an LEU fuel fabrication facility yielded the conclusion that the annual fuel cost to the HFIR would increase significantly from the current, HEU fuel cycle. Though manufacturing can be accomplished with existing technology, several engineering proof-of-principle tests would be required. The RERTR program is currently conducting a series of generic fuel qualification tests at the Advanced Test Reactor. A review of these tests and a review of the safety basis for the current, HEU fuel cycle led to the identification of a set of HFIR-specific fuel qualification tests. Much additional study is required to formulate a HFIR-specific fuel qualification plan from this set. However, one such test - creating a graded fuel profile across a flat foil - has been initiated with promising results.

Primm, Trent [ORNL; Ellis, Ronald James [ORNL; Gehin, Jess C [ORNL; Ilas, Germina [ORNL; Miller, James Henry [ORNL; Sease, John D [ORNL

2007-11-01T23:59:59.000Z

296

Examples of the use of PSA in the design process and to support modifications at two research reactors  

SciTech Connect (OSTI)

Many, if not most, of the world`s commercial nuclear power plants have been the subject of plant-specific probabilistic safety assessments (PSA). A growing number of other nuclear facilities as well as other types of industrial installations have been the focus of plant-specific PSAs. Such studies have provided valuable information concerning the nature of the risk of the individual facility and have been used to identify opportunities to manage that risk. This paper explores the risk management activities associated with two research reactors in the United States as a demonstration of the versatility of the use of PSA to support risk-related decision making.

Johnson, D.H.; Bley, D.C.; Lin, J.C. [PLG, Inc., Newport Beach, CA (United States); Ramsey, C.T.; Linn, M.A. [Oak Ridge National Lab., TN (United States)

1994-03-01T23:59:59.000Z

297

DOE Certification Programs | Department of Energy  

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

DOE Certification Programs DOE Certification Programs DOE Certification Programs The following are certification programs offered at DOE: Acquisition Career Management Program (ACMP) - is managed by the Office of Acquisition and Project Management's (OAPM) Professional Development Division (PDD). ACMP implements Federal Acquisition Certifications established by the Office of Federal Procurement Policy in accordance with the provisions of 41 USC 433 regarding professionalization of the non-DOD acquisition workforce. IT Project Management Qualification Process - is developed by the Office of the Chief Information Officer (OCIO) to provide a framework for certifying Federal IT Project Managers as having the qualifications necessary to manage IT projects. Per the Office of Management and Budget

298

Equipment Certification Requirements | Open Energy Information  

Open Energy Info (EERE)

Equipment Certification Requirements Equipment Certification Requirements Jump to: navigation, search Policies requiring renewable energy equipment to meet certain standards serve to protect consumers from buying inferior equipment. These requirements not only benefit consumers; they also protect the renewable energy industry by making it more difficult for substandard systems to reach the market. [1] Contents 1 Equipment Certification Incentives 2 References Equipment Certification Incentives CSV (rows 1 - 19) Incentive Incentive Type Place Applicable Sector Eligible Technologies Active Canada Oil and Gas Operations Act (Canada) Environmental Regulations Equipment Certification Fees Generating Facility Rate-Making Generation Disclosure Industry Recruitment/Support Safety and Operational Guidelines

299

FAQS Qualification Card - NNSA Package Certification Engineer |  

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

NNSA Package Certification Engineer NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NNSAPackageCertificationEngineer.docx Description NNSA Package Certification Engineer Qualification Card

300

Compliance Certification Enforcement | Department of Energy  

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

Compliance Certification Enforcement Compliance Certification Enforcement Compliance Certification Enforcement DOE enforces the energy and water conservation regulations established by the Office of Energy Efficiency and Renewable Energy, Appliance Standards Program to ensure that residential, commercial and industrial equipment deliver the energy and cost savings required by law. To ensure that all covered products comply with the energy and water conservation standards, the enforcement office reviews manufacturers' compliance with certification requirements. Products covered under the Energy Policy and Conservation Act of 1975, as amended, are required annually to ''certify by means of a certification report that each basic model(s) meets the applicable energy conservation standard." This program

Note: This page contains sample records for the topic "reactor design certification" 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

Review and Exams Limited Certification  

E-Print Network [OSTI]

__________________________________ Check which exam you will be taking: Commercial Landscape Maintenance Lawn & Ornamental CEU's ONLY 8 Limited Certification for Commercial Landscape Maintenance A license is necessary for each commercial landscape maintenance person who applies pesticides to ornamental plant beds. Application available at: http

Watson, Craig A.

302

Professional Certificate in Management Skills  

E-Print Network [OSTI]

.carleton.ca/ppd A well-balanced program for employees in transition from a union to a management environment. KudosProfessional Certificate in Management Skills 2010 Program 12 days over 6 months Jan. 24 ­ June 14, 2011 An essential program for managers of today ­ gain a portfolio of tools and learn how to integrate

Carleton University

303

Quantum Certificate Complexity Scott Aaronson #  

E-Print Network [OSTI]

, that Q 0 (f) # R 0 (f), and that Q E (f) # D (f). If f is partial (i.e. Dom (f) #= {0, 1} n ), then Q 2Quantum Certificate Complexity Scott Aaronson # Computer Science Division University of California . Then the deterministic query complexity D (f) is the minimum number of queries to the y i 's needed to evaluate f , if Y

Aaronson, Scott

304

STATE OF CALIFORNIA INSTALLATION CERTIFICATE  

E-Print Network [OSTI]

ENERGY COMMISSION INSTALLATION CERTIFICATE CF-6R-MECH-26-HERS Refrigerant Charge Verification ­ Alternate are specified in Reference Residential Appendix RA3.2. If refrigerant charge verification is requiredR-MECH-26-HERS Refrigerant Charge Verification ­ Alternate Measurement Procedure (Page 2 of 3) Site

305

Graduate Certificate in Clinical Practice  

E-Print Network [OSTI]

Systems: A Health Services Management Program? The Master of Science in Health Systems Program is a 30 between theoretical and practical approaches to the financial management of the health care institutionsChoiCes... Online Graduate Certificate in Clinical Practice Management Positioning Clinical

Garfunkel, Eric

306

Masters and Certificate Student Handbook  

E-Print Network [OSTI]

at RWJMS)! This student handbook is informational only and does not constitute a contract between Rutgers1 Masters and Certificate Student Handbook Graduate School of Biomedical Sciences at Robert Wood. This handbook represents a program of the current curricula, educational plans, offerings and requirements

Garfunkel, Eric

307

Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles  

E-Print Network [OSTI]

Cost of electricity is the key factor that determines competitiveness of a power plant. Thus the proper selection, design and optimization of the electric power generating cycle is of main importance. This report makes an ...

Dostal, Vaclav

308

Conceptual design study FY 1981: synfuels from fusion - using the tandem mirror reactor and a thermochemical cycle to produce hydrogen  

SciTech Connect (OSTI)

This report represents the second year's effort of a scoping and conceptual design study being conducted for the express purpose of evaluating the engineering potential of producing hydrogen by thermochemical cycles using a tandem mirror fusion driver. The hydrogen thus produced may then be used as a feedstock to produce fuels such as methane, methanol, or gasoline. The main objective of this second year's study has been to obtain some approximate cost figures for hydrogen production through a conceptual design study.

Krikorian, O.H. (ed.)

1982-02-09T23:59:59.000Z

309

Non-ferrous Metals Industry Energy Management System Certification  

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

ferrous Metals Industry ferrous Metals Industry Energy Management System Certification China Quality Certification Center Zhigang Wang 1. Importance Energy Management System 2. Pilot Programs of Energy Management System Certification Contents China Quality Certification Center A professional certification body under the General Administration of Quality Supervision, Inspection and Quarantine of the PRC. Member of the following international organizations: IECEE and IQNet. CQC provides the following services; System certification, Product certification and Training . Main Qualifications -State authorized administrator of the Energy Conservation Label -Provides compulsory product certification as outlined by the Certification and Accreditation Administration(CNCA) of the PRC

310

Spherical torus fusion reactor  

DOE Patents [OSTI]

The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

311

Physics design of a 100 keV acceleration grid system for the diagnostic neutral beam for international tokamak experimental reactor  

SciTech Connect (OSTI)

This paper describes the physics design of a 100 keV, 60 A H{sup -} accelerator for the diagnostic neutral beam (DNB) for international tokamak experimental reactor (ITER). The accelerator is a three grid system comprising of 1280 apertures, grouped in 16 groups with 80 apertures per beam group. Several computer codes have been used to optimize the design which follows the same philosophy as the ITER Design Description Document (DDD) 5.3 and the 1 MeV heating and current drive beam line [R. Hemsworth, H. Decamps, J. Graceffa, B. Schunke, M. Tanaka, M. Dremel, A. Tanga, H. P. L. De Esch, F. Geli, J. Milnes, T. Inoue, D. Marcuzzi, P. Sonato, and P. Zaccaria, Nucl. Fusion 49, 045006 (2009)]. The aperture shapes, intergrid distances, and the extractor voltage have been optimized to minimize the beamlet divergence. To suppress the acceleration of coextracted electrons, permanent magnets have been incorporated in the extraction grid, downstream of the cooling water channels. The electron power loads on the extractor and the grounded grids have been calculated assuming 1 coextracted electron per ion. The beamlet divergence is calculated to be 4 mrad. At present the design for the filter field of the RF based ion sources for ITER is not fixed, therefore a few configurations of the same have been considered. Their effect on the transmission of the electrons and beams through the accelerator has been studied. The OPERA-3D code has been used to estimate the aperture offset steering constant of the grounded grid and the extraction grid, the space charge interaction between the beamlets and the kerb design required to compensate for this interaction. All beamlets in the DNB must be focused to a single point in the duct, 20.665 m from the grounded grid, and the required geometrical aimings and aperture offsets have been calculated.

Singh, M. J. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, Gujarat 382428 (India); De Esch, H. P. L. [CEA-Cadarache, IRFM, F-13108 Saint-Paul-lez-Durance (France)

2010-01-15T23:59:59.000Z

312

Internet Explorer 7 on Windows Vista: Obtaining MIT Certificates  

E-Print Network [OSTI]

: A separate certificate password is not necessary for IE7 on Vista; the certificate is protected by your web services at MIT with IE7 on Windows Vista, three types of MIT web certificates are needed: · MIT servers · MIT Client Certificate, needed in IE7 on Vista to generate the personal certificate · MIT

Barton, Paul I.

313

Light Water Reactor Sustainability Program Operator Performance Metrics for Control Room Modernization: A Practical Guide for Early Design Evaluation  

SciTech Connect (OSTI)

As control rooms are modernized with new digital systems at nuclear power plants, it is necessary to evaluate the operator performance using these systems as part of a verification and validation process. There are no standard, predefined metrics available for assessing what is satisfactory operator interaction with new systems, especially during the early design stages of a new system. This report identifies the process and metrics for evaluating human system interfaces as part of control room modernization. The report includes background information on design and evaluation, a thorough discussion of human performance measures, and a practical example of how the process and metrics have been used as part of a turbine control system upgrade during the formative stages of design. The process and metrics are geared toward generalizability to other applications and serve as a template for utilities undertaking their own control room modernization activities.

Ronald Boring; Roger Lew; Thomas Ulrich; Jeffrey Joe

2014-03-01T23:59:59.000Z

314

Simulated Performance of the Integrated PNAR and SINRD Detector Designed for Spent Fuel Measurements at the Fugen Reactor in Japan  

SciTech Connect (OSTI)

Objective is to investigate the use of Passive Neutron Albedo Reactivity (PNAR) and Self-Interrogation Neutron Resonance Densitometry (SINRD) to quantify fissile content in FUGEN spent fuel assemblies (FAs). Methodology used is: (1) Detector was designed using fission chambers (FCs); (2) Optimized design via MCNPX simulations; and (3) Plan to build and field test instrument in FY13. Significance was to improve safeguards verification of spent fuel assemblies in water and increase sensitivity to partial defects. MCNPX simulations were performed to optimize the design of the SINRD+PNAR detector. PNAR ratio was less sensitive to FA positioning than SINRD and SINRD ratio was more sensitive to Pu fissile mass than PNAR. Significance was that the integration of these techniques can be used to improve verification of spent fuel assemblies in water.

Lafleur, Adrienne M. [Los Alamos National Laboratory; Ulrich, Timothy J. II [Los Alamos National Laboratory; Menlove, Howard O. [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory; Tobin, Stephen J. [Los Alamos National Laboratory; Seya, Michio [Japan Atomic Energy Agency; Bolind, Alan M. [Japan Atomic Energy Agency

2012-07-13T23:59:59.000Z

315

Do teachers differ by certification route? novice teachers' sense of self-efficacy, commitment to teaching, and preparedness to teach  

E-Print Network [OSTI]

their impact on the teaching pool (Darling-Hammond, Berry, & Thoreson, 2001; Darling-Hammond, Chung, & Frelow, 2002; Goldhaber, 2000; Ingersoll, 1999; Shen, 1997, 1999). The present study was designed to explore differences by certification type and program...

Zientek, Linda Reichwein

2007-09-17T23:59:59.000Z

316

Self Certifications | Department of Energy  

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

Electricity Policy Coordination and Implementation » Electricity Policy Coordination and Implementation » International Electricity Regulation » Self Certifications Self Certifications Title II of the Powerplant and Industrial Fuel Use Act of 1978 (FUA), as amended (42 U.S.C. 8301 et seq.), provides that no new baseload electric powerplant may be constructed or operated without the capability to use coal or another alternate fuel as a primary energy source. In order to meet the requirement of coal capability, the owner or operator of such facilities proposing to use natural gas or petroleum as its primary energy source shall certify, pursuant to FUA section 201(d), and Section 501.60(a)(2) of DOE's regulations to the Secretary of Energy prior to construction, or prior to operation as a base load powerplant, that such

317

Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2006  

SciTech Connect (OSTI)

Neutronics and thermal-hydraulics studies show that, for equivalent operating power [85 MW(t)], a low-enriched uranium (LEU) fuel cycle based on uranium-10 wt % molybdenum (U-10Mo) metal foil with radially, “continuously graded” fuel meat thickness results in a 15% reduction in peak thermal flux in the beryllium reflector of the High Flux Isotope Reactor (HFIR) as compared to the current highly enriched uranium (HEU) cycle. The uranium-235 content of the LEU core is almost twice the amount of the HEU core when the length of the fuel cycle is kept the same for both fuels. Because the uranium-238 content of an LEU core is a factor of 4 greater than the uranium-235 content, the LEU HFIR core would weigh 30% more than the HEU core. A minimum U-10Mo foil thickness of 84 ?m is required to compensate for power peaking in the LEU core although this value could be increased significantly without much penalty. The maximum U-10Mo foil thickness is 457?m. Annual plutonium production from fueling the HFIR with LEU is predicted to be 2 kg. For dispersion fuels, the operating power for HFIR would be reduced considerably below 85 MW due to thermal considerations and due to the requirement of a 26-d fuel cycle. If an acceptable fuel can be developed, it is estimated that $140 M would be required to implement the conversion of the HFIR site at Oak Ridge National Laboratory from an HEU fuel cycle to an LEU fuel cycle. To complete the conversion by fiscal year 2014 would require that all fuel development and qualification be completed by the end of fiscal year 2009. Technological development areas that could increase the operating power of HFIR are identified as areas for study in the future.

Primm, R. T. [ORNL] [ORNL; Ellis, R. J. [ORNL] [ORNL; Gehin, J. C. [ORNL] [ORNL; Clarno, K. T. [ORNL] [ORNL; Williams, K. A. [ORNL] [ORNL; Moses, D. L. [ORNL] [ORNL

2006-11-01T23:59:59.000Z

318

Quantum Certificate Complexity Scott Aaronson  

E-Print Network [OSTI]

2 (f) R 2 (f) R 0 (f) D (f) n, that QE (f) D (f), and that Q0 (f) R0 (f).1 If f is partial (i.eQuantum Certificate Complexity Scott Aaronson Abstract Given a Boolean function f, we study two/2, and otherwise outputs "I don't know" (it can never output an incorrect value). If we require the algorithm

Aaronson, Scott

319

Quantum Certificate Complexity Scott Aaronson #  

E-Print Network [OSTI]

(f) # D (f ), and that Q 0 (f) # R 0 (f). 1 If f is partial (i.e. S #= {0, 1} n ), then Q 2 (f) canQuantum Certificate Complexity Scott Aaronson # Abstract Given a Boolean function f , we study two . Then the deterministic query complexity D (f) is the minimum number of queries to the y i 's needed to evaluate f , if Y

Aaronson, Scott

320

Application for COR Certification-Recertification  

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

MEMORANDUM FOR SITE ACQUISITION CAREER MANAGER FROM: SUBJECT: Application for COR Certification- In accordance with DOE Order 361.1B, paragraph 4.B, the following application for COR certification is submitted, based on completion of the required minimum experience and training and my existing and/or pending COR appointment. E-mail address: _____________________ Program Office: Phone: ____________________________ Duty Station (city/state): I am COR to a or ________________________ under Contract/Solicitation number _________________________ 1. Previous certification (attached): Date last issued or renewed:____________

Note: This page contains sample records for the topic "reactor design certification" 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

UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY  

E-Print Network [OSTI]

/Documentation: Computers are set to energy saving modes. Description/Documentation: GREEN DEPARTMENT PLEDGE UAF Green Department Certification UAF OFFICE OF SUSTAINABILITY GREEN DEPARTMENT CERTIFICATION INSTRUCTIONS & FORMS PART I: GETTING STARTED & REQUIRED ACTIONS #12; UAF Green Department Certification

Hartman, Chris

322

JAPAN GOING TOWARD FOREST CERTIFICATION September 24, 2004  

E-Print Network [OSTI]

JAPAN GOING TOWARD FOREST CERTIFICATION September 24, 2004 Toshiaki Owari #12;TABLE OF CONTENTS JAPAN: GROWING INTEREST IN FOREST CERTIFICATION................................ 2 FOREST, FORESTRY AND FOREST INDUSTRY IN JAPAN ................................... 2 DIFFERENT FOREST CERTIFICATION SCHEMES

323

Validation of nuclear design method by measured data obtained in the physics test at a small fast reactor  

SciTech Connect (OSTI)

The present paper discusses applicability of the measured data of Joyo cores from a view point of integral validation for the 4S nuclear design methodology. Through the evaluation of isothermal reactivity coefficients and reactivity losses due to burnup, the results confirm that those MK-I and MK-II database are effective in order to increase the dataset for uncertainty estimation for the prediction. Discussions on the 4S design method validation are also done through the analyses of criticality, power distributions and reactivity loss due to burn-up. The C/E values for criticality and reaction rate distributions are confirmed to be consistent with those obtained from the physics benchmark experiments. Through an analysis of burnup coefficient of the MK-I core by the detailed Monte Carlo calculations, the C/E value is 1.1, which is close to 1.06 obtained by the deterministic transport analysis. (authors)

Nagata, A.; Tsuboi, Y. [Advanced Energy Design and Engineering Dep., Toshiba Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Moriki, Y. [Power and Industrial Systems Research and Development Center, Toshiba Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Kawashima, M. [Nuclear Technology Application Dept., Toshiba Nuclear Engineering Services Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)

2012-07-01T23:59:59.000Z

324

Financial Assistance Certification Financial Assistance Qualification Standards  

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

Financial Assistance Certification Financial Assistance Certification Financial Assistance Qualification Standards Financial assistance award and administration in DOE is performed primarily by contract specialists. The Office of Personnel Management qualification standards for GS- 1 102 contract specialists are relevant but not fully sufficient for performing financial assistance duties. Contract specialists performing financial assistance in addition to, or in place of, acquisition duties must also meet the certification requirements established by the Financial Assistance Career Development (FACD) program. The FACD Program is built upon the skills acquired by the contract specialists in the performance of their acquisition duties and the training provided under the Contracting/Purchasing certification program.

325

DOE Plan for 2302(c) Certification  

Broader source: Energy.gov [DOE]

OSC's 2302(c) Certification Program allows federal agencies to meet the statutory obligation to inform their workforces about the rights and remedies available to them under the prohibited...

326

Verifying the ENERGY STAR® Certification Application  

Broader source: Energy.gov [DOE]

Do you verify commercial building applications for ENERGY STAR certification? This webinar, based on the ENERGY STAR Guide for Licensed Professionals, covers the role of the licensed professional,...

327

IT Project Management Certification | Department of Energy  

Office of Environmental Management (EM)

and research project management certification initiatives and services provided by NASA, USDA, DOJ, HUD, GSA (STAR program), OPM, Federal CIO Council, Project Management...

328

FAQS Reference Guide – NNSA Package Certification Engineer  

Broader source: Energy.gov [DOE]

This reference guide addresses the competency statements in the February 2009 edition of DOE-STD-1026-2009, NNSA Package Certification Engineer Functional Area Qualification Standard.

329

CERTIFICATE OF AUTHENTICITY | Department of Energy  

Energy Savers [EERE]

D.C. Tran001.pdf CERTIFICATE OF AUTHENTICITY More Documents & Publications U.S. Offshore Wind Advanced Technology Demonstration Projects Public Meeting Transcript for...

330

Home Energy Professional Certifications (Fact Sheet), Guidelines...  

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

professionals, the four new certifications focus on the most common jobs in the industry: energy auditor, retrofit installer technician, crew leader, and quality control inspector....

331

Home Energy Professional Certifications Fact Sheet | Department...  

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

professionals, the four new certifications focus on the most common jobs in the industry: energy auditor, retrofit installer technician, crew leader, and quality control inspector....

332

FEMA - National Flood Insurance Program Elevation Certificate...  

Open Energy Info (EERE)

and Instructions Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: FEMA - National Flood Insurance Program Elevation Certificate and Instructions...

333

Colorado Water Quality Certification General Information | Open...  

Open Energy Info (EERE)

search OpenEI Reference LibraryAdd to library Legal Document- OtherOther: Colorado Water Quality Certification General InformationLegal Abstract The Colorado Department of...

334

REC Tracking Systems Design Guide  

SciTech Connect (OSTI)

OAK-B135 The Design Guide is presented in three parts. Section II describes the need for REC tracking, the two principal tracking methods available, and, in simple terms, the operation of certificate-based systems. Section III presents the major issues in the design of certificate-based tracking systems and discusses the advantages and disadvantages of alternative solutions. Finally, Section IV offers design principles or recommendations for most of these issues.

Meredith Wingate

2004-02-03T23:59:59.000Z

335

Reactor hot spot analysis  

SciTech Connect (OSTI)

The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

Vilim, R.B.

1985-08-01T23:59:59.000Z

336

T-724: Microsoft Security Advisory: Fraudulent digital certificates...  

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

24: Microsoft Security Advisory: Fraudulent digital certificates could allow spoofing T-724: Microsoft Security Advisory: Fraudulent digital certificates could allow spoofing...

337

2014-04-17 DOE Certification, Compliance, and Enforcement Overview...  

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

04-17 DOE Certification, Compliance, and Enforcement Overview for Plumbing Products 2014-04-17 DOE Certification, Compliance, and Enforcement Overview for Plumbing Products This...

338

File:07TXBRECGeneratorCertification.pdf | Open Energy Information  

Open Energy Info (EERE)

TXBRECGeneratorCertification.pdf Jump to: navigation, search File File history File usage Metadata File:07TXBRECGeneratorCertification.pdf Size of this preview: 463 599 pixels....

339

Iowa Water and Wastewater Operators Seek SEP Certification in...  

Energy Savers [EERE]

Iowa Water and Wastewater Operators Seek SEP Certification in New Pilot Program Iowa Water and Wastewater Operators Seek SEP Certification in New Pilot Program September 18, 2014 -...

340

Green Building Certification Systems Requirement for New Federal...  

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

Green Building Certification Systems Requirement for New Federal Buildings and Major Renovations of Federal Buildings Final Rule Green Building Certification Systems Requirement...

Note: This page contains sample records for the topic "reactor design certification" 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

Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality...  

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

Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Vehicle Certification Test Fuel and Ethanol Flex Fuel Quality Breakout Session 2: Frontiers and Horizons Session 2-B:...

342

accuracy certificates for computational problems with convex structure  

E-Print Network [OSTI]

guarantees without building the certificates explicitly. Finally, the ... tionally cheap rules for on-line building of explicit accuracy certificates justifying the standard.

2008-11-26T23:59:59.000Z

343

DOE Convening Report on Certification of Commercial HVAC and...  

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

Convening Report on Certification of Commercial HVAC and CRE Products DOE Convening Report on Certification of Commercial HVAC and CRE Products This document is the convening...

344

FAQS Job Task Analyses - NNSA Package Certification Engineer...  

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

NNSA Package Certification Engineer FAQS Job Task Analyses - NNSA Package Certification Engineer FAQS Job Task Analyses are performed on the Function Area Qualification Standards....

345

National Certification Standard for Ground Source Heat Pump Personnel  

SciTech Connect (OSTI)

The National Certification Standard for the Geothermal Heat Pump Industry adds to the understanding of the barriers to rapid growth of the geothermal heat pump (GHP) industry by bringing together for the first time an analysis of the roles and responsibilities of each of the individual job tasks involved in the design and installation of GHP systems. The standard addresses applicable qualifications for all primary personnel involved in the design, installation, commissioning, operation and maintenance of GHP systems, including their knowledge, skills and abilities. The resulting standard serves as a foundation for subsequent development of curriculum, training and certification programs, which are not included in the scope of this project, but are briefly addressed in the standard to describe ways in which the standard developed in this project may form a foundation to support further progress in accomplishing those other efforts. Follow-on efforts may use the standard developed in this project to improve the technical effectiveness and economic feasibility of curriculum development and training programs for GHP industry personnel, by providing a more complete and objective assessment of the individual job tasks necessary for successful implementation of GHP systems. When incorporated into future certification programs for GHP personnel, the standard will facilitate increased consumer confidence in GHP technology, reduce the potential for improperly installed GHP systems, and assure GHP system quality and performance, all of which benefit the public through improved energy efficiency and mitigated environmental impacts of the heating and cooling of homes and businesses.

Kelly, John [Geothermal Heat Pump Consortium] [Geothermal Heat Pump Consortium

2013-07-31T23:59:59.000Z

346

Novel, fiber optic, hybrid pressure and temperature sensor designed for high-temperature gen-IV reactor applications  

SciTech Connect (OSTI)

A novel, fiber optic, hybrid pressure-temperature sensor is presented. The sensor is designed for reliable operation up to 1050 C, and is based on the high-temperature fiber optic sensors already demonstrated during previous work. The novelty of the sensors presented here lies in the fact that pressure and temperature are measured simultaneously with a single fiber and a single transducer. This hybrid approach will enable highly accurate active temperature compensation and sensor self-diagnostics not possible with other platforms. Hybrid pressure and temperature sensors were calibrated by varying both pressure and temperature. Implementing active temperature compensation resulted in a ten-fold reduction in the temperature-dependence of the pressure measurement. Sensors were also tested for operability in a relatively high neutron radiation environment up to 6.9x10{sup 17} n/cm{sup 2}. In addition to harsh environment survivability, fiber optic sensors offer a number of intrinsic advantages for nuclear power applications including small size, immunity to electromagnetic interference, self diagnostics / prognostics, and smart sensor capability. Deploying fiber optic sensors on future nuclear power plant designs would provide a substantial improvement in system health monitoring and safety instrumentation. Additional development is needed, however, before these advantages can be realized. This paper will highlight recent demonstrations of fiber optic sensors in environments relevant to emerging nuclear power plants. Successes and lessons learned will be highlighted. (authors)

Palmer, M. E.; Fielder, R. S.; Davis, M. A. [Luna Innovations, Incorporated, 2851 Commerce St., Blacksburg, VA 24060 (United States)

2006-07-01T23:59:59.000Z

347

NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS TOWARDS THE FULL INTEGRATION OF REACTOR  

E-Print Network [OSTI]

NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS ­ TOWARDS THE FULL INTEGRATION solutions. However, it does not provide optimal reactor design from both economical and environmental and methods for reactor design. It also explores the possibilities for actuation improvement for the optimal

Van den Hof, Paul

348

T-586: Microsoft Advisory about fraudulent SSL Certificates | Department of  

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

586: Microsoft Advisory about fraudulent SSL Certificates 586: Microsoft Advisory about fraudulent SSL Certificates T-586: Microsoft Advisory about fraudulent SSL Certificates March 23, 2011 - 3:05pm Addthis PROBLEM: Microsoft just released an advisory alerting its customers that a total of 9 certificates were issued using the leaked/stolen CA certificated from Comodo. PLATFORM: These certificates affect the following Web properties: login.live.com mail.google.com www.google.com login.yahoo.com (3 certificates) login.skype.com addons.mozilla.org "Global Trustee" ABSTRACT: Microsoft Advisory about fraudulent SSL Certificates. reference LINKS: Microsoft Security Advisory: 2524375 ISC 2011-03-23 Security updates IMPACT ASSESSMENT: High Discussion: Microsoft is aware of nine fraudulent digital certificates issued by Comodo, a certification authority present in the Trusted Root Certification

349

Advanced Safeguards Approaches for New Fast Reactors  

SciTech Connect (OSTI)

This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

2007-12-15T23:59:59.000Z

350

SECTION 1 -CERTIFICATION BY AUTHORISED DEPARTMENTAL OFFICER  

E-Print Network [OSTI]

SECTION 1 - CERTIFICATION BY AUTHORISED DEPARTMENTAL OFFICER Earnings Code Description Rate No Ext. Employee ID Surname Given Names Title Date of Birth (dd/mm/yy) Sex (tick one) male female Home Phone No. Postal Address (for group certificates, etc) Postcode Is an Employment Declaration Form

Tobar, Michael

351

Birth Certificate Citizen Petrovich, Petr Ivanovich  

E-Print Network [OSTI]

REISSUE Birth Certificate Citizen Petrovich, Petr Ivanovich last name, first name, patronymic of English and Russian languages, and certify the above translation of the Birth Certificate from Russian was born on 02.02.1977 (the Second of February, Year Nineteen Seventy Seven) Place of birth: the City

Comech, Andrew

352

Small Wind Turbine Certifications Signal Maturing Industry  

Broader source: Energy.gov [DOE]

More than a dozen small wind turbine models have received certification to the U.S. industry standard from accredited certification bodies. This progress signals a maturing industry and that the DOE Wind Program is on track to reach its goal of certifying 40 turbine models by 2020.

353

Renewal Credit Matrix CERTIFICATE RENEWAL PLAN  

E-Print Network [OSTI]

Renewal Credit Matrix CERTIFICATE RENEWAL PLAN PROFESSIONAL DEVELOPMENT OPTIONS FOR SOUTH CAROLINA are restricted to Options 1 and 2 in the matrix. CERTIFICATE RENEWAL OPTION ELIGIBILITY CRITERIA RENEWAL CREDITS to 120 renewal credits may be earned via this option during the five-year validity period

Kunkle, Tom

354

Roundtable on Sustainable Biofuels Certification Readiness Study  

E-Print Network [OSTI]

Roundtable on Sustainable Biofuels Certification Readiness Study: Hawai`i Biofuel Projects Prepared 12.1 Deliverable Bioenergy Analyses Prepared by Hawai`i Biofuel Foundation And NCSI Americas Inc agency thereof. #12;1 RSB Certification Readiness Study: Hawaii Biofuel Projects Prepared For Hawaii

355

INFORMATION SESSION Graduate Certificate Program in  

E-Print Network [OSTI]

INFORMATION SESSION Graduate Certificate Program in TRANSPORTATION STUDIES TUESDAY, OCTOBER 4, 2005 a certificate in transportation studies are encouraged to attend this information session. The session will also arrival at Mn/DOT, please check in at the first floor information counter. (Directions: www

Minnesota, University of

356

The Graduate Certificate in Management of Technology  

E-Print Network [OSTI]

The Graduate Certificate in Management of Technology Entirely Online and In Class New Jersey Institute of Technology School of Management THE EDGE IN KNOWLEDGE May 2012 Rev Use your smartphone to scan://www.njit.edu/continuing/ #12;WHY PURSUE A GRADUATE CERTIFICATE IN MANAGEMENT OF TECHNOLOGY? Developments in science

Bieber, Michael

357

THE GRADUATE CERTIFICATE IN ENVIRONMENTAL HAZARD MANAGEMENT  

E-Print Network [OSTI]

THE GRADUATE CERTIFICATE IN ENVIRONMENTAL HAZARD MANAGEMENT Offered by The College of Architecture and The Hazard Reduction and Recovery Center Texas A&M University #12;2 THE GRADUATE CERTIFICATE IN ENVIRONMENTAL..................................................................................3 C. Approved Courses in the College of Architecture .............................4 D. Approved

358

Insulin Pump Software Certification Yihai Chen1,  

E-Print Network [OSTI]

Insulin Pump Software Certification Yihai Chen1, , Mark Lawford2, , Hao Wang2, , and Alan Wassyng2 for Software Certification McMaster University, Hamilton, Ontario, Canada Abstract. The insulin pump. Malfunction of the insulin pump will endanger the user's life. All countries impose some regula- tion

Lawford, Mark

359

NUCLEAR REACTORS.  

E-Print Network [OSTI]

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain… (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

360

Ssessment methodology for proliferation resistant fast breeder reactor  

E-Print Network [OSTI]

Due to perceived proliferation risks, current US fast reactor designs have avoided the use of uranium blankets. While reducing the amount of plutonium produced, this omission also restrains the reactor design space and has ...

Singh, Mohit, S.M. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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

Renewable Energy Certificates | Department of Energy  

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

Renewable Energy Certificates Renewable Energy Certificates Renewable Energy Certificates October 16, 2013 - 5:15pm Addthis Image of a red balloon reading 'Electricity' plus a green balloon reading 'REC' equals a purple balloon reading 'Renewable Power' Components of a Renewable Energy Certificate Two separate products exist from electricity produced by renewable energy projects that can be sold together or treated separately. One is the actual electrons produced, which can either be transferred through the power grid to provide power to utility customers or used off-grid or at a customer site. Although they are not common in the market, Federal renewable energy policy recognizes renewable energy certificates (RECs) from thermal renewable energy projects. For thermal RECs the energy product is British

362

Solar Equipment Certification | Department of Energy  

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

Solar Equipment Certification Solar Equipment Certification Solar Equipment Certification < Back Eligibility Construction General Public/Consumer Savings Category Solar Buying & Making Electricity Heating & Cooling Water Heating Program Info State Florida Program Type Equipment Certification Provider Florida Solar Energy Center Under the Solar Energy Standards Act of 1976, the Florida Solar Energy Center (FSEC) is responsible for certifying all solar equipment sold in Florida. A manufacturer who wishes to have their solar equipment certified first contacts FSEC for an application and requests that FSEC test samples of the product at random. Equipment is then subjected to a series of tests in order to be approved or denied certification. Standards and applications procedures for specific technologies are available on the FSEC web site.

363

National Certification Methodology for the Nuclear Weapons Stockpile  

SciTech Connect (OSTI)

Lawrence Livermore and Los Alamos National Laboratories have developed a common framework and key elements of a national certification methodology called Quantification of Margins and Uncertainties (QMU). A spectrum from senior managers to weapons designers has been engaged in this activity at the two laboratories for on the order of a year to codify this methodology in an overarching and integrated paper. Following is the certification paper that has evolved. In the process of writing this paper, an important outcome has been the realization that a joint Livermore/Los Alamos workshop on QMU, focusing on clearly identifying and quantifying differences between approaches between the two labs plus developing an even stronger technical foundation on methodology, will be valuable. Later in FY03, such a joint laboratory workshop will be held. One of the outcomes of this workshop will be a new version of this certification paper. A comprehensive approach to certification must include specification of problem scope, development of system baseline models, formulation of standards of performance assessment, and effective procedures for peer review and documentation. This document concentrates on the assessment and peer review aspects of the problem. In addressing these points, a central role is played by a 'watch list' for weapons derived from credible failure modes and performance gate analyses. The watch list must reflect our best assessment of factors that are critical to weapons performance. High fidelity experiments and calculations as well as full exploitation of archival test data are essential to this process. Peer review, advisory groups and red teams play an important role in confirming the validity of the watch list. The framework for certification developed by the Laboratories has many basic features in common, but some significant differences in the detailed technical implementation of the overall methodology remain. Joint certification workshops held in June and December of 2001 and continued in 2002 have proven useful in developing the methodology, and future workshops should prove useful in further refining this framework. Each laboratory developed an approach to certification with some differences in detailed implementation. The general methodology introduces specific quantitative indicators for assessing confidence in our nuclear weapon stockpile. The quantitative indicators are based upon performance margins for key operating characteristics and components of the system, and these are compared to uncertainties in these factors. These criteria can be summarized in a quantitative metric (for each such characteristic) expressed as: (i.e., confidence in warhead performance depends upon CR significantly exceeding unity for all these characteristics). These Confidence Ratios are proposed as a basis for guiding technical and programmatic decisions on stockpile actions. This methodology already has been deployed in certifying weapons undergoing current life extension programs or component remanufacture. The overall approach is an adaptation of standard engineering practice and lends itself to rigorous, quantitative, and explicit criteria for judging the robustness of weapon system and component performance at a detailed level. There are, of course, a number of approaches for assessing these Confidence Ratios. The general certification methodology was publicly presented for the first time to a meeting of Strategic Command SAG in January 2002 and met with general approval. At that meeting, the Laboratories committed to further refine and develop the methodology through the implementation process. This paper reflects the refinement and additional development to date. There will be even further refinement at a joint laboratory workshop later in FY03. A common certification methodology enables us to engage in peer reviews and evaluate nuclear weapon systems on the basis of explicit and objective metrics. The clarity provided by such metrics enables each laboratory and our common customers to understand the meaning and logic

Goodwin, B T; Juzaitis, R J

2006-08-07T23:59:59.000Z

364

Interfacial effects in fast reactors  

E-Print Network [OSTI]

The problem of increased resonance capture rates near zone interfaces in fast reactor media has been examined both theoretically and experimentally. An interface traversing assembly was designed, constructed and employed ...

Saidi, Mohammad Said

1979-01-01T23:59:59.000Z

365

Design, performance, and grounding aspects of the International Thermonuclear Experimental Reactor ion cyclotron range of frequencies antenna  

SciTech Connect (OSTI)

ITER's Ion Cyclotron Range of Frequencies (ICRF) system [Lamalle et al., Fusion Eng. Des. 88, 517–520 (2013)] comprises two antenna launchers designed by CYCLE (a consortium of European associations listed in the author affiliations above) on behalf of ITER Organisation (IO), each inserted as a Port Plug (PP) into one of ITER's Vacuum Vessel (VV) ports. Each launcher is an array of 4 toroidal by 6 poloidal RF current straps specified to couple up to 20?MW in total to the plasma in the frequency range of 40 to 55 MHz but limited to a maximum system voltage of 45?kV and limits on RF electric fields depending on their location and direction with respect to, respectively, the torus vacuum and the toroidal magnetic field. A crucial aspect of coupling ICRF power to plasmas is the knowledge of the plasma density profiles in the Scrape-Off Layer (SOL) and the location of the RF current straps with respect to the SOL. The launcher layout and details were optimized and its performance estimated for a worst case SOL provided by the IO. The paper summarizes the estimated performance obtained within the operational parameter space specified by IO. Aspects of the RF grounding of the whole antenna PP to the VV port and the effect of the voids between the PP and the Blanket Shielding Modules (BSM) surrounding the antenna front are discussed. These blanket modules, whose dimensions are of the order of the ICRF wavelengths, together with the clearance gaps between them will constitute a corrugated structure which will interact with the electromagnetic waves launched by ICRF antennas. The conditions in which the grooves constituted by the clearance gaps between the blanket modules can become resonant are studied. Simple analytical models and numerical simulations show that mushroom type structures (with larger gaps at the back than at the front) can bring down the resonance frequencies, which could lead to large voltages in the gaps between the blanket modules and perturb the RF properties of the antenna if they are in the ICRF operating range. The effect on the wave propagation along the wall structure, which is acting as a spatially periodic (toroidally and poloidally) corrugated structure, and hence constitutes a slow wave structure modifying the wall boundary condition, is examined.

Durodié, F., E-mail: frederic.durodie@rma.ac.be; Dumortier, P.; Vrancken, M.; Messiaen, A.; Huygen, S.; Louche, F.; Van Schoor, M.; Vervier, M. [LPP-ERM/KMS, Association EURATOM-Belgian State, Brussels (Belgium); Bamber, R.; Hancock, D.; Lockley, D.; Nightingale, M. P. S.; Shannon, M.; Tigwell, P.; Wilson, D. [EURATOM/CCFE Assoc., Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Maggiora, R.; Milanesio, D. [Associazione EURATOM-ENEA, Politechnico di Torino (Italy); Winkler, K. [IPP-MPI, EURATOM-Assoziation, Garching (Germany)

2014-06-15T23:59:59.000Z

366

Certification of a weld produced by friction stir welding  

DOE Patents [OSTI]

Methods, devices, and systems for providing certification of friction stir welds are disclosed. A sensor is used to collect information related to a friction stir weld. Data from the sensor is compared to threshold values provided by an extrinsic standard setting organizations using a certification engine. The certification engine subsequently produces a report on the certification status of the weld.

Obaditch, Chris; Grant, Glenn J

2013-10-01T23:59:59.000Z

367

Quick Guide: Renewable Energy Certificates (RECs) (Fact Sheet)  

SciTech Connect (OSTI)

Guide for Federal agencies considering renewable energy certificate (REC) purchases to fulfill Federal renewable energy requirements.

Not Available

2011-07-01T23:59:59.000Z

368

Use of Nested Certificates for Efficient, Dynamic and Trust Preserving Public Key Infrastructure  

E-Print Network [OSTI]

Use of Nested Certificates for Efficient, Dynamic and Trust Preserving Public Key Infrastructure), and verify the certificates on this path recursively. This is the classical methodology. Nested certification certificates ­ called nested certificates ­ for other certificates. Nested certificates can be used together

369

Light Water Reactor Sustainability Program Status of Silicon Carbide Joining Technology Development  

SciTech Connect (OSTI)

Advanced, accident tolerant nuclear fuel systems are currently being investigated for potential application in currently operating light water reactors (LWR) or in reactors that have attained design certification. Evaluation of potential options for accident tolerant nuclear fuel systems point to the potential benefits of silicon carbide (SiC) relative to Zr-based alloys, including increased corrosion resistance, reduced oxidation and heat of oxidation, and reduced hydrogen generation under steam attack (off-normal conditions). If demonstrated to be applicable in the intended LWR environment, SiC could be used in nuclear fuel cladding or other in-core structural components. Achieving a SiC-SiC joint that resists corrosion with hot, flowing water, is stable under irradiation and retains hermeticity is a significant challenge. This report summarizes the current status of SiC-SiC joint development work supported by the Department of Energy Light Water Reactor Sustainability Program. Significant progress has been made toward SiC-SiC joint development for nuclear service, but additional development and testing work (including irradiation testing) is still required to present a candidate joint for use in nuclear fuel cladding.

Shannon M. Bragg-Sitton

2013-09-01T23:59:59.000Z

370

Energy Performance Certification of Buildings: A Policy Tool to Improve  

Open Energy Info (EERE)

Energy Performance Certification of Buildings: A Policy Tool to Improve Energy Performance Certification of Buildings: A Policy Tool to Improve Energy Efficiency Jump to: navigation, search Tool Summary Name: Energy Performance Certification of Buildings: A Policy Tool to Improve Energy Efficiency Agency/Company /Organization: International Energy Agency Sector: Energy Focus Area: Energy Efficiency, Buildings Topics: Policies/deployment programs Resource Type: Guide/manual, Lessons learned/best practices Website: www.iea.org/papers/pathways/buildings_certification.pdf Energy Performance Certification of Buildings: A Policy Tool to Improve Energy Efficiency Screenshot References: nergy Performance Certification of Buildings[1] Logo: Energy Performance Certification of Buildings: A Policy Tool to Improve Energy Efficiency

371

Certificate of Current Cost and Pricing Data  

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

CERTIFICATE OF CURRENT COST AND PRICING DATA (OCT 1997) CERTIFICATE OF CURRENT COST AND PRICING DATA (OCT 1997) This is to certify that, to the best of my knowledge and belief, the cost or pricing data (as defined in section 15.401 of the Federal Acquisition Regulation (FAR) and required under FAR subsection 15.403-4) submitted, either actually or by specific identification in writing, to the Contracting Officer or to the Contracting Officer's representative in support of * are accurate, complete, and current as of **. This certification includes the cost or pricing data supporting any advance agreements and forward pricing rate agreements between the offeror and the Government that are

372

Baseline Concept Description of a Small Modular High Temperature Reactor  

SciTech Connect (OSTI)

The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNP were all both ‘small’ or medium-sized and ‘modular’ by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOE’s ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the Generation IV program and its specific R&D needs will be included in this report when appropriate for comparison. The distinguishing features of the HTGR are the refractory (TRISO) coated particle fuel, the low-power density, graphite-moderated core, and the high outlet temperature of the inert helium coolant. The low power density and fuel form effectively eliminate the possibility of core melt, even upon a complete loss of coolant pressure and flow. The graphite, which constitutes the bulk of the core volume and mass, provides a large thermal buffer that absorbs fission heat such that thermal transients occur over a timespan of hours or even days. As chemically-inert helium is already a gas, there is no coolant temperature or void feedback on the neutronics and no phase change or corrosion product that could degrade heat transfer. Furthermore, the particle coatings and interstitial graphite retain fission products such that the source terms at the plant boundary remain well below actionable levels under all anticipated nominal and off-normal operating conditions. These attributes enable the reactor to supply process heat to a collocated industrial plant with negligible risk of contamination and minimal dynamic coupling of the facilities (Figure 1). The exceptional retentive properties of coated particle fuel in a graphite matrix were first demonstrated in the DRAGON reactor, a European research facility that began operation in 1964.

Hans Gougar

2014-05-01T23:59:59.000Z

373

Strategic Need for Multi-Purpose Thermal Hydraulic Loop for Support of Advanced Reactor Technologies  

SciTech Connect (OSTI)

This report presents a conceptual design for a new high-temperature multi fluid, multi loop test facility for the INL to support thermal hydraulic, materials, and thermal energy storage research for nuclear and nuclear-hybrid applications. In its initial configuration, the facility will include a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed with this facility include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs) at prototypical operating conditions, flow and heat transfer issues related to core thermal hydraulics in advanced helium-cooled and salt-cooled reactors, and evaluation of corrosion behavior of new cladding materials and accident-tolerant fuels for LWRs at prototypical conditions. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. Research performed in this facility will advance the state of the art and technology readiness level of high temperature intermediate heat exchangers (IHXs) for nuclear applications while establishing the INL as a center of excellence for the development and certification of this technology. The thermal energy storage capability will support research and demonstration activities related to process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will assist in development of reliable predictive models for thermal hydraulic design and safety codes over the range of expected advanced reactor operating conditions. Proposed/existing IHX heat transfer and friction correlations and criteria will be assessed with information on materials compatibility and instrumentation needs. The experimental database will guide development of appropriate predictive methods and be available for code verification and validation (V&V) related to these systems.

James E. O'Brien; Piyush Sabharwall; Su-Jong Yoon; Gregory K. Housley

2014-09-01T23:59:59.000Z

374

naval reactors  

National Nuclear Security Administration (NNSA)

After operating for 34 years and training over 14,000 sailors, the Department of Energy S1C Prototype Reactor Site in Windsor, Connecticut, was returned to "green field"...

375

Implementation, Certification and Enforcement | Department of Energy  

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

Implementation, Certification Implementation, Certification and Enforcement Implementation, Certification and Enforcement The U.S. Department of Energy (DOE) is authorized by the Energy Policy and Conservation Act of 1975 (as amended) to enforce compliance with the energy and water conservation standards established for certain consumer products and commercial and industrial equipment. To ensure the implementation of the current standards for covered appliances and equipment, DOE has published certification, compliance, and enforcement regulations for these products and equipment in the Code of Federal Regulations (CFR) at 10 CFR part 429. Please note that the previous link is to the Electronic Code of Federal Regulations (e-CFR), which is a version of the CFR updated daily. It is not an official legal edition of

376

Training, Certification, and Mentoring | Department of Energy  

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

Training, Certification, and Mentoring Training, Certification, and Mentoring Training, Certification, and Mentoring The Project Management Coordination Office (PMCO) is working to support programs in ensuring that team members have the necessary training and certifications to enable meaningful stewardship of their projects and programs. Greater awareness of the process and understanding of the full assistance/acquisition project lifecycle will help each program meet its objectives. Project Managers help ensure awards and acquisitions are put in place in a timely manner, are aligned with the technology's road-map and receive adequate, effective oversight and management. In order to improve program and project management, the Office of Energy Efficiency and Renewable Energy (EERE) will ensure all projects are managed by appropriately trained

377

Certificate of Current Cost and Pricing Data  

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

CERTIFICATE OF CURRENT COST AND PRICING DATA (OCT 1997) This is to certify that, to the best of my knowledge and belief, the cost or pricing data (as defined in section 15.401 of...

378

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-09-09T23:59:59.000Z

379

CERTIFICATION REQUIREMENTS IN THE CALIFORNIA ENERGY COMMISSION'S  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION CERTIFICATION REQUIREMENTS IN THE CALIFORNIA ENERGY COMMISSION'S APPLIANCE REGULATIONS: A Summary Guide, Including Forms for Manufacturers, Trade Associations, and Other ...............................................................................................................1 III. Where to Find the Energy Commission Appliance Efficiency Regulations .....2 IV. Where to Get

380

Secondary Mathematics Teacher Certification Requirements Mathematics  

E-Print Network [OSTI]

Secondary Mathematics Teacher Certification Requirements Mathematics Undergraduate Program:______________ Date:______________ Date:______________ Date:______________ MATHEMATICS CORE REQUIREMENTS MATH 151 Introduction to Mathematical Analysis I CMSC 201 Computer Science I MATHEMATICS EDUCATION CONCENTRATION

Maryland, Baltimore County, University of

Note: This page contains sample records for the topic "reactor design certification" 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

PKIX Certificate Status in Hybrid MANETs  

Science Journals Connector (OSTI)

Certificate status validation is a hard problem in general but it is particularly complex in Mobile Ad-hoc Networks (MANETs) because we require solutions to manage both the lack of fixed infrastructure inside the...

Jose L. Muñoz; Oscar Esparza; Carlos Gañán…

2009-01-01T23:59:59.000Z

382

Applications for Certification (Contracting) | Department of...  

Office of Environmental Management (EM)

Contracting) Applications for Certification (Contracting) Application FAC-C Level I.pdf Application FAC-C Level II.pdf Application FAC-C Level III.pdf More Documents & Publications...

383

Managing certificates in a corporate environment  

Science Journals Connector (OSTI)

Many cryptographic security protocols make use of public key cryptography and corresponding public key certificates. In addition, it is possible and very likely that e-commerce applications will make heavy use...

Rolf Oppliger

384

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-12-14T23:59:59.000Z

385

Timber Products' Mississippi mill earns formaldehyde certification Tuesday, February 10, 2009 -Modern Woodworking  

E-Print Network [OSTI]

., have been certified to meet the California Air Resources Board (CARB) requirements. Timber Products of the California Air Resources Board (CARB). Corinth's designation means that all Timber Products hardwood plywoodTimber Products' Mississippi mill earns formaldehyde certification Tuesday, February 10, 2009

386

Lessons Learned From Gen I Carbon Dioxide Cooled Reactors  

SciTech Connect (OSTI)

This paper provides a review of early gas cooled reactors including the Magnox reactors originating in the United Kingdom and the subsequent development of the Advanced Gas-cooled Reactors (AGR). These early gas cooled reactors shared a common coolant medium, namely carbon dioxide (CO2). A framework of information is provided about these early reactors and identifies unique problems/opportunities associated with use of CO2 as a coolant. Reactor designers successfully rose to these challenges. After years of successful use of the CO2 gas cooled reactors in Europe, the succeeding generation of reactors, called the High Temperature Gas Reactors (HTGR), were designed with Helium gas as the coolant. Again, in the 21st century, with the latest reactor designs under investigation in Generation IV, there is a revived interest in developing Gas Cooled Fast Reactors that use CO2 as the reactor coolant. This paper provides a historical perspective on the 52 CO2 reactors and the reactor programs that developed them. The Magnox and AGR design features and safety characteristics were reviewed, as well as the technologies associated with fuel storage, reprocessing, and disposal. Lessons-learned from these programs are noted to benefit the designs of future generations of gas cooled nuclear reactors.

David E. Shropshire

2004-04-01T23:59:59.000Z

387

E-Print Network 3.0 - advanced fast reactor Sample Search Results  

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

ANNULAR FAST REACTOR (3000 MWth) Fuel... and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... Cooled, Fast, ... Source:...

388

E-Print Network 3.0 - advanced reactors coupled Sample Search...  

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

ANNULAR FAST REACTOR (3000 MWth) Fuel... and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... Cooled, Fast, Subcritical...

389

E-Print Network 3.0 - advanced reactor analyses Sample Search...  

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

ANNULAR FAST REACTOR (3000 MWth) Fuel... and NRE Design Class., "Advances in the Subcritical, Gas-Cooled Fast Transmutation Reactor Concept", Nucl... Cooled, Fast, Subcritical...

390

A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor.  

E-Print Network [OSTI]

?? The CANDU-900 reactor design is an improvement on the current CANDU-6 reactor in the areas of economics, safety of operation and fuel cycle flexibility.… (more)

Trudell, David A

2012-01-01T23:59:59.000Z

391

TAMU Online ESL Certification Prep Course  

E-Print Network [OSTI]

SSI) and Title III funds through the Texas Education Agency. Department of Educational Psychology College of Education & Human Development Texas A&M University Presentation Overview ? Online ESL Certification Course?Overview ? Course... ESL Certification Prep Course Department of Educational Psychology College of Education & Human Development Texas A&M University Funding Source This training is made possible by the Limited English Proficient, Student Success Initiative (LEP...

Lara-Alecio, Rafael; Treviño, Polly; Tong, Fuhui

2010-10-22T23:59:59.000Z

392

PROTEUS - Simulation Toolset for Reactor Physics and Fuel Cycle Analysis  

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

Simulation Toolset for Simulation Toolset for Reactor Physics and Fuel Cycle Analysis PROTEUS Faster and more accurate neutronics calculations enable optimum reactor design... Argonne National Laboratory's powerful reactor physics toolset, PROTEUS, empowers users to create optimal reactor designs quickly, reliably and accurately. ...Reducing costs for designers of fast spectrum reactors. PROTEUS' long history of validation provides confidence in predictive simulations Argonne's simulation tools have more than 30 years of validation history against numerous experiments and measurements. The tools within PROTEUS work together, using the same interface files for easier integration of calculations. Multi-group Fast Reactor Cross Section Processing: MC 2 -3 No other fast spectrum multigroup generation tool

393

T-587: Firefox Blocking Fraudulent Certificates | Department of Energy  

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

587: Firefox Blocking Fraudulent Certificates 587: Firefox Blocking Fraudulent Certificates T-587: Firefox Blocking Fraudulent Certificates March 24, 2011 - 3:05pm Addthis PROBLEM: Mozilla Security Advisory: Several invalid HTTPS certificates were placed on the certificate blacklist to prevent their misuse. PLATFORM: Firefox, Thunderbird, SeaMonkey ABSTRACT: Firefox Blocking Fraudulent Certificates. reference LINKS: MFSA 2011-11 Mozilla Bug 644012 Mozilla Security updates IMPACT ASSESSMENT: High Discussion: Firefox will crashes when trying to access a HTTPS website with a certificate that does not contain the fields issuerName. Mozilla has been informed about the issuance of several fraudulent SSL certificates for public websites. The certificates have been revoked by their issuer which should protect most users. This is not a

394

Transport reactor development status  

SciTech Connect (OSTI)

This project is part of METC`s Power Systems Development Facility (PSDF) located at Wilsonville, Alabama. The primary objective of the Advanced Gasifier module is to produce vitiated gases for intermediate-term testing of Particulate Control Devices (PCDs). The Transport reactor potentially allows particle size distribution, solids loading, and particulate characteristics in the off-gas stream to be varied in a number of ways. Particulates in the hot gases from the Transport reactor will be removed in the PCDs. Two PCDs will be initially installed in the module; one a ceramic candle filter, the other a granular bed filter. After testing of the initial PCDs they will be removed and replaced with PCDs supplied by other vendors. A secondary objective is to verify the performance of a Transport reactor for use in advanced Integrated Gasification Combined Cycle (IGCC), Integrated Gasification Fuel Cell (IG-FC), and Pressurized Combustion Combined Cycle (PCCC) power generation units. This paper discusses the development of the Transport reactor design from bench-scale testing through pilot-scale testing to design of the Process Development Unit (PDU-scale) facility at Wilsonville.

Rush, R.E.; Fankhanel, M.O.; Campbell, W.M.

1994-10-01T23:59:59.000Z

395

Radioisotope thermoelectric generator licensed hardware package and certification tests  

SciTech Connect (OSTI)

This paper presents the Licensed Hardware package and the Certification Test portions of the Radioisitope Themoelectric Generator Transportation System. This package has been designed to meet those portions of the {ital Code} {ital of} {ital Federal} {ital Regulations} (10 CFR 71) relating to ``Type B`` shipments of radioactive materials. The licensed hardware is now in the U. S. Department of Energy licensing process that certifies the packaging`s integrity under accident conditions. The detailed information for the anticipated license is presented in the safety analysis report for packaging, which is now in process and undergoing necessary reviews. As part of the licensing process, a full-size Certification Test Article unit, which has modifications slightly different than the Licensed Hardware or production shipping units, is used for testing. Dimensional checks of the Certification Test Article were made at the manufacturing facility. Leak testing and drop testing were done at the 300 Area of the U.S. Department of Energy`s Hanford Site near Richland, Washington. The hardware includes independent double containments to prevent the environmental spread of {sup 238}Pu, impact limiting devices to protect portions of the package from impacts, and thermal insulation to protect the seal areas from excess heat during accident conditions. The package also features electronic feed-throughs to monitor the Radioisotope Thermoelectric Generator`s temperature inside the containment during the shipment cycle. This package is designed to safely dissipate the typical 4,500 thermal watts produced in the largest Radioisotope Thermoelectric Generators. The package also contains provisions to ensure leak tightness when radioactive materials, such as a Radioisotope Thermoelectric Generator for the Cassini Mission, planned for 1997 by the National Aeronautics and Space Administration, are being prepared for shipment. (Abstract Truncated)

Goldmann, L.H.; Averette, H.S. [Westinghouse Hanford Company, P.O. Box 1970, M/S R3-86 or N1-32, Richland, Washington 99352 (United States)

1995-01-20T23:59:59.000Z

396

MANAGEMENT CERTIFICATE FOR WOMEN (MCW) A Professional Certificate in Management Fundamentals & Skills  

E-Print Network [OSTI]

-profitsectors Womenprofessionals(e.g.medical,legal,engineering)andscientificspecialists who wish to transition into managementMANAGEMENT CERTIFICATE FOR WOMEN (MCW) A Professional Certificate in Management Fundamentals & Skills This program recognizes that women have different learning and management styles than do

Dawson, Jeff W.

397

BIOTECHNOLOGY CERTIFICATE PROGRAM The Biotechnology Certificate Program is open to all FAU Biology and Chemistry Students  

E-Print Network [OSTI]

BIOTECHNOLOGY CERTIFICATE PROGRAM The Biotechnology Certificate Program is open to all FAU Biology in biotechnology. In addition to the requirements for the baccalaureate degree sought, students must complete credits) B- PCB 3063 Genetics (4 credits) C- BSCL4403 Biotechnology I laboratory (2 credits) B- BSCL4405

Fernandez, Eduardo

398

Light Water Reactor Sustainability  

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

4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

399

Certification of the Cessna 152 on 100% ethanol  

SciTech Connect (OSTI)

In June 1996, the Renewable Aviation Fuels Development Center (RAFDC) at Baylor University in Waco, Texas, received a Supplemental Type Certificate (STC) for the use of 100% ethanol as a fuel for the Cessna 152, the most popular training aircraft in the world. This is the first certification granted by the Federal Aviation Administration (FAA) for a non-petroleum fuel. Certification of an aircraft on a new fuel requires a certification of the engine followed by a certification of the airframe/engine combination. This paper will describe the FAA airframe certification procedure, the tests required and their outcome using ethanol as an aviation fuel in a Cessna 152.

Shauck, M.E.; Zanin, M.G.

1997-12-31T23:59:59.000Z

400

Renewable Energy Specifications, Testing and Certification Terms of  

Open Energy Info (EERE)

Renewable Energy Specifications, Testing and Certification Terms of Renewable Energy Specifications, Testing and Certification Terms of Reference Jump to: navigation, search Tool Summary Name: Renewable Energy Specifications, Testing and Certification Terms of Reference Agency/Company /Organization: World Bank Sector: Energy Focus Area: Solar, - Solar PV Topics: Market analysis, Co-benefits assessment Website: web.worldbank.org/WBSITE/EXTERNAL/TOPICS/EXTENERGY2/EXTRENENERGYTK/0,, References: Renewable Energy Specifications, Testing and Certification Terms of Reference[1] Resources Establishment of Local PV Systems Certification Capability Preparation of Small Private Power Producers Grid Connection Standards Establishment of Local PV System Battery Testing Procedure References ↑ "Renewable Energy Specifications, Testing and Certification

Note: This page contains sample records for the topic "reactor design certification" 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

Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II) ; Development of a core design optimization tool and analysis in support of the planned low enriched uranium conversion of the MIT Research Reactor (MITR-II) .  

E-Print Network [OSTI]

??The MIT Research Reactor (MITR-II) is currently undergoing analysis for the planned conversion from high enriched uranium (HEU) to low enriched uranium (LEU), as part… (more)

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

402

Unique features of space reactors  

SciTech Connect (OSTI)

Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K. 8 refs., 3 figs., 1 tab.

Buden, D.

1990-01-01T23:59:59.000Z

403

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

> Heavy Liquid Metal Reactor Development > Heavy Liquid Metal Reactor Development Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor (AFR) Heavy Liquid Metal Reactor Development Generation IV Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Advanced Reactor Development and Technology Heavy Liquid Metal Reactor Development Bookmark and Share STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge. Click on image to view larger image. Argonne has traditionally been the foremost institute in the US for

404

An Innovative Three-Dimensional Heterogeneous Coarse-Mesh Transport Method for Advanced and Generation IV Reactor Core Analysis and Design  

SciTech Connect (OSTI)

This project has resulted in a highly efficient method that has been shown to provide accurate solutions to a variety of 2D and 3D reactor problems. The goal of this project was to develop (1) an accurate and efficient three-dimensional whole-core neutronics method with the following features: based sollely on transport theory, does not require the use of cross-section homogenization, contains a highly accurate and self-consistent global flux reconstruction procedure, and is applicable to large, heterogeneous reactor models, and to (2) create new numerical benchmark problems for code cross-comparison.

Farzad Rahnema

2009-11-12T23:59:59.000Z

405

Overview of Sandia National Laboratories pulse nuclear reactors  

SciTech Connect (OSTI)

Sandia National Laboratories has designed, constructed and operated bare metal Godiva-type and pool-type pulse reactors since 1961. The reactor facilities were designed to support a wide spectrum of research, development, and testing activities associated with weapon and reactor systems.

Schmidt, T.R. [Sandia National Labs., Albuquerque, NM (United States); Reuscher, J.A. [Texas A& M Univ., College Station, TX (United States)

1994-10-01T23:59:59.000Z

406

Experimental and Computational Study of a Scaled Reactor Cavity Cooling System  

E-Print Network [OSTI]

The Very High Temperature Gas-Cooled Reactor (VHTR) is one of the next generation nuclear reactors designed to achieve high temperatures to support industrial applications and power generation. The Reactor Cavity Cooling System (RCCS) is a passive...

Vaghetto, Rodolfo

2013-11-25T23:59:59.000Z

407

ANALYSIS OF SEPCTRUM CHOICES FOR SMALL MODULAR REACTORS-PERFORMANCE AND DEVELOPMENT  

E-Print Network [OSTI]

. The research mainly focused on producing a small modular reactor (Pebble Bed Modular Reactor) design to analyze the fuel depletion and plutonium and minor actinide accumulation with varying power densities. The reactors running at low power densities were found...

Kafle, Nischal

2011-04-26T23:59:59.000Z

408

Design  

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

Design Design of a Multithreaded Barnes-Hut Algorithm for Multicore Clusters Technical Report Junchao Zhang and Babak Behzad Department of Computer Science, University of Illinois at Urbana-Champaign {jczhang, bbehza2}@illinois.edu Marc Snir Department of Computer Science, University of Illinois at Urbana-Champaign and MCS Division, Argonne National Laboratory snir@anl.gov Abstract We describe in this paper an implementation of the Barnes-Hut al- gorithm on multicore clusters. Based on a partitioned global ad- dress space (PGAS) library, the design integrates intranode mul- tithreading and internode one-sided communication, exemplifying a PGAS + X programming style. Within a node, the computation is decomposed into tasks (subtasks), and multitasking is used to hide network latency. We study the tradeoffs between locality in private caches and locality in shared caches

409

Use of Nested Certificates for Efficient, Dynamic and Trust Preserving Public Key Infrastructure  

E-Print Network [OSTI]

Use of Nested Certificates for Efficient, Dynamic and Trust Preserving Public Key Infrastructure the certificates on this path recursively. This is the classical methodology. Nested certification is a novel nested certificates ­ for other certificates. Nested certificates can be used together with classical

Levi, Albert

410

Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model  

Science Journals Connector (OSTI)

Abstract One of the important operations in nuclear power plants is load-following in which imbalance of axial power distribution induces xenon oscillations. These oscillations must be maintained within acceptable limits otherwise the nuclear power plant could become unstable. Therefore, bounded xenon oscillation considered to be a constraint for the load-following operation. In other hands, precursors produce delayed neutrons which are most important in control of nuclear reactor, but xenon concentration & precursor density cannot be measured directly. In this paper, non-linear sliding mode observer which has the robust characteristics facing the parameters uncertainties and disturbances is proposed based on the two point nuclear reactor model to estimate the xenon concentration & delayed neutron precursor density of the Pressurized-Water Nuclear Reactor (PWR) using reactor power measurement. The stability analysis is given by means Lyapunov approach, thus the system is guaranteed to be stable within a large range. The employed method is easy to implement in practical applications. This estimation is done taking into account the effects of reactivity feedback due to temperature and xenon concentration. Simulation results clearly show that the sliding mode observer follows the actual system variables accurately and is satisfactory in the presence of the parameters uncertainties & disturbances.

G.R. Ansarifar; M.H. Esteki; M. Arghand

2015-01-01T23:59:59.000Z

411

Observations of the boiling process from a downward-facing torispherical surface: Confirmatory testing of the heavy water new production reactor flooded cavity design  

SciTech Connect (OSTI)

Reactor-scale ex-vessel boiling experiments were performed in the CYBL facility at Sandia National Laboratories. The boiling flow pattern outside the RPV bottom head shows a center pulsating region and an outer steady two-phase boundary layer region. The local heat transfer data can be correlated in terms of a modified Rohsenow correlation.

Chu, T.Y.; Bentz, J.H.; Simpson, R.B.

1995-06-01T23:59:59.000Z

412

T-724: Microsoft Security Advisory: Fraudulent digital certificates could  

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

724: Microsoft Security Advisory: Fraudulent digital certificates 724: Microsoft Security Advisory: Fraudulent digital certificates could allow spoofing T-724: Microsoft Security Advisory: Fraudulent digital certificates could allow spoofing September 22, 2011 - 12:45pm Addthis PROBLEM: Microsoft Security Advisory: Fraudulent digital certificates could allow spoofing. PLATFORM: Microsoft Untrusted Certificate Store: DigiNotar root certificates ABSTRACT: Microsoft has released a Microsoft security advisory about this issue for IT professionals. reference LINKS: MS Article ID: 2616676 Microsoft Security Advisory: 2607712 DOE-CIRC Tech Bulletin: T-706 IMPACT ASSESSMENT: Medium Discussion: The Microsoft update revokes the trust of the following DigiNotar root certificates by putting them in the Microsoft Untrusted Certificate Store:

413

Guidance Concerning Certification Following a Change in the Applicable  

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

Concerning Certification Following a Change in the Concerning Certification Following a Change in the Applicable Energy or Water Conservation Standard Guidance Concerning Certification Following a Change in the Applicable Energy or Water Conservation Standard Guidance regardling the applicability of changes in the EPCA standards. If any manufacturer's previous certification demonstrates that the basic model meets the NEW standard, no additional certification is necessary. If any manufacturer's previous certification does not demonstrate that the basic model meets the NEW standard, that model has not been certified. It may not be distributed once the new standard takes effect unless the manufacturer submits a new certification report demonstrating that the basic model meets the new standard. Guidance Concerning Certification Following a Change in the Applicable

414

T-711: Fraudulent Google Digital Certificates Could Allow Man...  

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

11: Fraudulent Google Digital Certificates Could Allow Man-in-the-Middle Attacks T-711: Fraudulent Google Digital Certificates Could Allow Man-in-the-Middle Attacks September 7,...

415

Paper achieves forest certification An Independent Paper plc product story  

E-Print Network [OSTI]

Paper achieves forest certification An Independent Paper plc product story Edited certification: News from Independent Paper plc http://www.printingtalk.com/news/inp/inp119.html 1 of 1 11

416

Failure Rates from Certification Testing to UL and IEC Standards...  

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

Failure Rates from Certification Testing to UL and IEC Standards for Flat Plate PV Modules Failure Rates from Certification Testing to UL and IEC Standards for Flat Plate PV...

417

Development of a system model for advanced small modular reactors.  

SciTech Connect (OSTI)

This report describes a system model that can be used to analyze three advance small modular reactor (SMR) designs through their lifetime. Neutronics of these reactor designs were evaluated using Monte Carlo N-Particle eXtended (MCNPX/6). The system models were developed in Matlab and Simulink. A major thrust of this research was the initial scoping analysis of Sandia's concept of a long-life fast reactor (LLFR). The inherent characteristic of this conceptual design is to minimize the change in reactivity over the lifetime of the reactor. This allows the reactor to operate substantially longer at full power than traditional light water reactors (LWRs) or other SMR designs (e.g. high temperature gas reactor (HTGR)). The system model has subroutines for lifetime reactor feedback and operation calculations, thermal hydraulic effects, load demand changes and a simplified SCO2 Brayton cycle for power conversion.

Lewis, Tom Goslee,; Holschuh, Thomas Vernon,

2014-01-01T23:59:59.000Z

418

Cross section generation strategy for high conversion light water reactors  

E-Print Network [OSTI]

High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to achieve a conversion ratio of ...

Herman, Bryan R. (Bryan Robert)

2011-01-01T23:59:59.000Z

419

High voltage dry-type air-core shunt reactors  

Science Journals Connector (OSTI)

Dry-type air-core shunt reactors are now being ... systems to limit overvoltages. Recently, high voltage dry-type air-core shunt reactors have been designed, ... transient overvoltages and electrical and magnetic...

Klaus Papp; Michael R. Sharp…

2014-11-01T23:59:59.000Z

420

Preparing for the Quality Control Inspector Certification Exam...  

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

Department of Commerce, identifies how individuals can better prepare for the Home Energy Professional Quality Control Inspector Certification Exam. preparingfortheqci...

Note: This page contains sample records for the topic "reactor design certification" 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

UCLA program in reactor studies: The ARIES tokamak reactor study  

SciTech Connect (OSTI)

The ARIES research program is a multi-institutional effort to develop several visions of tokamak reactors with enhanced economic, safety, and environmental features. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Four ARIES visions are currently planned for the ARIES program. The ARIES-1 design is a DT-burning reactor based on modest'' extrapolations from the present tokamak physics database and relies on either existing technology or technology for which trends are already in place, often in programs outside fusion. ARIES-2 and ARIES-4 are DT-burning reactors which will employ potential advances in physics. The ARIES-2 and ARIES-4 designs employ the same plasma core but have two distinct fusion power core designs; ARIES-2 utilize the lithium as the coolant and breeder and vanadium alloys as the structural material while ARIES-4 utilizes helium is the coolant, solid tritium breeders, and SiC composite as the structural material. Lastly, the ARIES-3 is a conceptual D-{sup 3}He reactor. During the period Dec. 1, 1990 to Nov. 31, 1991, most of the ARIES activity has been directed toward completing the technical work for the ARIES-3 design and documenting the results and findings. We have also completed the documentation for the ARIES-1 design and presented the results in various meetings and conferences. During the last quarter, we have initiated the scoping phase for ARIES-2 and ARIES-4 designs.

Not Available

1991-01-01T23:59:59.000Z

422

Physics of nuclear reactor safety  

Science Journals Connector (OSTI)

Provides a concise review of the physical aspects of safety of nuclear fission reactors. It covers the developments of roughly the last decade. The introductory chapter contains an analysis of the changes in safety philosophy that are characteristic of the last decade and that have given rise to an increased importance of physical aspects because of the emphasis on passive or natural safety. The second chapter focuses on the basics of reactor safety, identifying the main risk sources and the main principles for a safe design. The third chapter concerns a systematic treatment of the physical processes that are fundamental for the properties of fission chain reacting processes and the control of those processes. Because of the rather specialized nature of the field of reactor physics, each paragraph contains a very concise description of the theory of the phenomenon under consideration, before presenting a review of the developments. Chapter 4 contains a short review of the thermal aspects of reactor safety, restricted to those aspects that are characteristic of the nuclear reactor field, because thermal hydraulics of fission reactors is not principally different from that of other physical systems. In chapter 5 the consequences of the physics treated in the preceding chapters for the dynamics and safety of actual reactors are reviewed. The systematics of the treatment is mainly based on a division of reactors into three categories according to the type of coolant, which to a large extent determines the safety properties of the reactors. The last chapter contains a physical analysis of the Chernobyl accident that occurred in 1986. The reason for an attempt to give a review of this accident, as complete as possible within the space limits set by the editors, is twofold: the Chernobyl accident is the most severe accident in history and physical properties of the reactor played a decisive role, thereby serving as an illustration of the material of the preceding chapters.

H van Dam

1992-01-01T23:59:59.000Z

423

The Drafting Technology Program offers a certificate or associate of applied science in drafting technology. The certificate program  

E-Print Network [OSTI]

DRAFTING TECHNOLOGY The Drafting Technology Program offers a certificate or associate of applied science in drafting technology. The certificate program offers a choice of six areas of emphasis: architectural drafting; civil drafting; information technology; mechanical and electrical drafting; process

Ickert-Bond, Steffi

424

Solar Renewable Energy Certificates | Department of Energy  

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

Solar Renewable Energy Certificates Solar Renewable Energy Certificates Solar Renewable Energy Certificates < Back Eligibility Agricultural Commercial Fed. Government Industrial Institutional Local Government Multi-Family Residential Nonprofit Residential Schools State Government Savings Category Solar Buying & Making Electricity Heating & Cooling Commercial Heating & Cooling Heating Water Heating Maximum Rebate $500/MWh (the Solar Alternative Compliance Payment, or SACP) or $0.50/kWh Program Info Start Date 01/01/2006 State District of Columbia Program Type Performance-Based Incentive Rebate Amount Varies based on market conditions. As of December 2012 the market price for D.C.-sourced SRECs was approximately $310/MWh ($0.31/kWh) although some individual trades have taken place at substantially lower and higher

425

SF-2050.11, Patent Certification  

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

1 1 OMB Control No. (2-87) 1910-0800 (Previous GC-792) Contractor Interim Certification Final Certification DOE Prime and/or Subcontract Nos. Contractor hereby certifies that: 1. All procedures for identifying and disclosing subject inventions as required by the patent clause of the con- tract have been followed throughout the reporting period. 2. There were no subcontracts or purchase orders involving research, development, and demonstration except as follows: [State none when applicable.] 3. No inventions or discoveries were made or conceived in the course of or under this contract other than the 4. The completion date of this contract is as follows: Month Day Year Contractor Address Month Day Year Signature Date of Certification

426

Application for Degree or Certificate Last Name: Date of Birth  

E-Print Network [OSTI]

Application for Degree or Certificate Last Name: Date of Birth: First Name: Email: Middle Name: UNI" section at http://registrar.columbia.edu. Degree or Certificate for Which You Are Applying School: Grad Year: Month: Select: Feb, May, June (HS only), or Oct Department: Degree or Certificate: Undergraduates

Adams, Mark

427

WICF Certification, Compliance and Enforcement webinar  

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

WICF Testing, Certification, WICF Testing, Certification, Compliance, and Enforcement Overview August 30, 2011 2 | Building Technologies Program & General Counsel's Office of Enforcement eere.energy.gov Agenda 2 Certified Ratings 3 1 Testing Basic Model Enforcement 4 5 Manufacturer How to Submit Questions 6 3 | Building Technologies Program & General Counsel's Office of Enforcement eere.energy.gov Manufacturer Explanation A Manufacturer of a WICF * Is a domestic manufacturer or an importer. * Produces a component of a walk-in cooler or walk-in freezer that affects energy consumption, including, but not limited to, refrigeration, doors, lights, windows, or walls.

428

CERTIFICATION DOCKET WESTINGHOUSE ATOMIC POWER DEVELOPMENT PLANT  

Office of Legacy Management (LM)

WESTINGHOUSE ATOMIC POWER DEVELOPMENT PLANT WESTINGHOUSE ATOMIC POWER DEVELOPMENT PLANT EAST PITTSBURGH PLANT FOREST HILLS PITTSBURGH, PENNSYLVANIA Department of Energy Office of Nuclear Energy Office of Terminal Waste Disposal and Remedial Action Division of Remedial Action Projects ..-.. --__- _".-.-l--_--l -_._ _- --- ~~~. . ..~ CONTENTS Page - - I NTRODUCTI ON 1 Purpose 1 Docket Contents 1 Exhibit I: Summary of Activities at Westinghouse Atomic Power Development Plant, East Pittsburgh Plant, Forest Hills, Pittsburgh, Pennsylvania I-l Exhibit II: Documents Supporting the Certification of Westinghouse Atomic Power Development Plant, East Pittsburgh Plant, Forest Hills, Pittsburgh, Pennsylvania iii II-1 . . .- .__.^ I ^_... _.-__^-____-. - CERTIFICATION DOCKET WESTINGHOUSE ATOMIC POWER DEVELOPMENT PLANT

429

Influence of reactor configuration on reliability of activated sludge process  

Science Journals Connector (OSTI)

The effect of uncertainty in system parameters and the accuracy of the mathematical model used on the design and reliability of the activated sludge process is investigated by Monte Carlo simulations. Simulations indicate that the coefficient of variation for a reactor volume varies from 0.56 for a single mixed tank reactor to 0.44 for a plug flow reactor. The coefficient of variation for effluent for reactors designed on nominal values was found to be 0.56 for a mixed-tank reactor, 1.28 for two reactors in series, 1.56 for three reactors in series and 1.6 for a plug flow reactor. Significant contributing parameters to the reliability of the process are established. Reactor volumes for desired reliability levels are also calculated.

Puneet Sarna; Sanjeev Chaudhari

2006-01-01T23:59:59.000Z

430

Certification of Plutonium Standards for KAMS Neutron Multiplicity Counter  

SciTech Connect (OSTI)

As part of the implementation of the PEIS record of decision in January of 1997, DOE will pursue two technologies to disposition fifty metric tons of its stockpile of plutonium. As a result of this and in order to expedite the closure of Rocky Flats Environmental Technology Site in Colorado, DOE decided to use existing facilities at the Savannah River Site (SRS) for storing all material containing plutonium at KAMS. A neutron multiplicity counter was designed and built to carry out receipt verification measurement at the facility. Since the material covers a wide range and different levels of impurities, it is essential that we obtain a set of working standards. An agreement was drafted to select the first drums to be these standards. A plan was developed for the certification of these standards using Rocky Flat's existing nondestructive assay equipment. This paper will discuss the types of materials to be shipped to SRS, number of standards to certify for each type of material, and the certification plan. It will also discuss the activities necessary to determine the nuclear content of these working standards to be used at SRS facilities in support of shipment and receipt of the Pu containing materials. Definition of instrument qualifications, measurement control processes, measurement methodologies, and calculations necessary to report the gram quantities and their uncertainties for plutonium, americium-241, uranium-235 (if present) and neptunium-237 (if present) will also be presented.

Salaymeh, S.R.

2002-05-31T23:59:59.000Z

431

Light Water Reactors Technology Development - Nuclear Reactors  

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

Light Water Reactors Light Water Reactors About Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library Visit Argonne Work with Argonne Contact us Nuclear Energy Why Nuclear Energy? Why are some people afraid of Nuclear Energy? How do nuclear reactors work? Cheaper & Safer Nuclear Energy Helping to Solve the Nuclear Waste Problem Nuclear Reactors Nuclear Reactors Early Exploration Training Reactors Basic and Applied Science Research LWR Technology Development BORAX-III lighting Arco, Idaho (Press Release) Heavy Water and Graphite Reactors Fast Reactor Technology Integral Fast Reactor Argonne Reactor Tree CP-1 70th Anniversary CP-1 70th Anniversary Argonne's Nuclear Science and Technology Legacy Argonne's Nuclear Science and Technology Legacy

432

Certifications and Assurances for Use with SF-424  

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

U.S. DEPARTMENT OF ENERGY FINANCIAL ASSISTANCE CERTIFICATIONS AND ASSURANCES FOR USE WITH SF 424 Applicant: Solicitation No.: DE- The following certifications and assurances must be completed and submitted with each application for financial assistance. The name of the person responsible for making the certifications and assurances must be typed in the signature block on the forms. Certifications Regarding Lobbying; Debarment, Suspension and Other Responsibility Matters; and Drug Free Workplace Requirements DOE F 1600.5, Assurance of Compliance Nondiscrimination in Federally Assisted Programs CERTIFICATIONS REGARDING LOBBYING; DEBARMENT, SUSPENSION AND OTHER RESPONSIBILITY MATTERS; AND DRUG FREE WORKPLACE REQUIREMENTS

433

Modular Inspection System for a Complete IN-Service Examination of Nuclear Reactor Pressure Vessel, Including Beltline Region  

SciTech Connect (OSTI)

Final Report for a DOE Phase II Contract Describing the design and fabrication of a reactor inspection modular rover prototype for reactor vessel inspection.

David H. Bothell

2000-04-30T23:59:59.000Z

434

Research Program of a Super Fast Reactor  

SciTech Connect (OSTI)

Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is not breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)

Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie; Terai, Takayuki; Nagasaki, Shinya; Muroya, Yusa; Abe, Hiroaki [Nuclear Professional School / Department of Nuclear Engineering and Management, The University of Tokyo, Tokaimura, Naka-gun, Ibaraki, 319-1188 (Japan); Mori, Hideo [Department of Mechanical Engineering, Kyushu University (Japan); Akiba, Masato; Akimoto, Hajime; Okumura, Keisuke; Akasaka, Naoaki [Japan Atomic Energy Agency (Japan); GOTO, Shoji [Tokyo Electric Power Company (Japan)

2006-07-01T23:59:59.000Z

435

Assessment of torsatrons as reactors  

SciTech Connect (OSTI)

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R[sub 0] = 6.6-8.8 m, on-axis magnetic field B[sup 0] = 4.8-7.5 T, B[sub max] (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. (Oak Ridge National Lab., TN (United States)) [Oak Ridge National Lab., TN (United States); Painter, S.L. (Australian National Univ., Canberra, ACT (Australia)) [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

436

Assessment of torsatrons as reactors  

SciTech Connect (OSTI)

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R{sub 0} = 6.6-8.8 m, on-axis magnetic field B{sup 0} = 4.8-7.5 T, B{sub max} (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Painter, S.L. [Australian National Univ., Canberra, ACT (Australia)

1992-12-01T23:59:59.000Z

437

Postgraduate Certificate in Safety and Risk Management  

E-Print Network [OSTI]

in safety and risk management, including health and safety legislation, safety policy and culture, risk be fully integrated into the organisation and the safety culture of the organisation developed accordinglyPostgraduate Certificate in Safety and Risk Management #12;Programme Structure The Postgraduate

Mottram, Nigel

438

Certificate Program in the Culinary Arts  

E-Print Network [OSTI]

, and future of the global food economy, and the principles of small- and large-scale food production handling and sanitation standards The program also provides a broader understanding of the past, present: cakes, pastries, tarts, cookies, breads Sanitation and certification in the proper handling of food

Spence, Harlan Ernest

439

NFC Mobile Payment with Citizen Digital Certificate  

E-Print Network [OSTI]

NFC Mobile Payment with Citizen Digital Certificate Wei-Dar Chen, Keith E. Mayes Smart Card Centre handsets, the mobile phone is likely to become the device of choice for accessing sophisticated services or to emulate smart cards. However the user registration process is relatively weak for access to mobile

Sheldon, Nathan D.

440

Roundtable on Sustainable Biofuels Certification Readiness Study  

E-Print Network [OSTI]

Roundtable on Sustainable Biofuels Certification Readiness Study: Hawai`i Biofuel Projects Prepared 12.1 Deliverable (item 2) Bioenergy Analyses Prepared by Hawai`i Biofuel Foundation And NCSI Americas: Hawaii Biofuel Projects Prepared For Hawaii Natural Energy Institute School of Ocean Earth Sciences

Note: This page contains sample records for the topic "reactor design certification" 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

Graduate Certificate in Geographic Information Systems (GIS)  

E-Print Network [OSTI]

Graduate Certificate in Geographic Information Systems (GIS) Texas A&M University GIS technologies 651/BAEN 651 ­ Geographic Information Systems · GEOG 660 ­ Applications for GIS Intermediate Level (Both are required) 6 hours · ESSM 652/BAEN 652 ­ Advanced Topics in GIS · GEOG 665 ­ GIS ­ based

442

Engineering Honors Certificate Student Completion Form  

E-Print Network [OSTI]

of program completion. requirements. Aerospace Engineering fall spring A B fall spring A B fall spring A BEngineering Honors Certificate Student Completion Form Students Name ENGR 181 Engineering Honors Seminar I 1 ENGR 281 Engineering Honors Seminar II 1 ENGR 381 Engineering

443

Heterogeneous Recycling in Fast Reactors  

SciTech Connect (OSTI)

Current sodium fast reactor (SFR) designs have avoided the use of depleted uranium blankets over concerns of creating weapons grade plutonium. While reducing proliferation risks, this restrains the reactor design space considerably. This project will analyze various blanket and transmutation target configurations that could broaden the design space while still addressing the non-proliferation issues. The blanket designs will be assessed based on the transmutation efficiency of key minor actinide (MA) isotopes and also on mitigation of associated proliferation risks. This study will also evaluate SFR core performance under different scenarios in which depleted uranium blankets are modified to include minor actinides with or without moderators (e.g. BeO, MgO, B4C, and hydrides). This will be done in an effort to increase the sustainability of the reactor and increase its power density while still offering a proliferation resistant design with the capability of burning MA waste produced from light water reactors (LWRs). Researchers will also analyze the use of recycled (as opposed to depleted) uranium in the blankets. The various designs will compare MA transmutation efficiency, plutonium breeding characteristics, proliferation risk, shutdown margins and reactivity coefficients with a current reference sodium fast reactor design employing homogeneous recycling. The team will also evaluate the out-of-core accumulation and/or burn-down rates of MAs and plutonium isotopes on a cycle-by-cycle basis. This cycle-by-cycle information will be produced in a format readily usable by the fuel cycle systems analysis code, VISION, for assessment of the sustainability of the deployment scenarios.

Dr. Benoit Forget; Michael Pope; Piet, Steven J.; Michael Driscoll

2012-07-30T23:59:59.000Z

444

SAFETY AND RELIABILITY ANALYSIS OF NUCLEAR REACTORS  

Science Journals Connector (OSTI)

Abstract A survey of the various aspects of safety and reliability analysis of nuclear reactors is presented with particular emphasis on the interrelation between structural reliability and systems reliability. In reactor design this interrelation is of overriding importance since it is the task of the control, protective and containment systems to protect the mechanical system and the structure from accidental overloading.

T.A. JAEGER

1972-01-01T23:59:59.000Z

445

Chemical Reactor Analysis and Optimal Digestion  

E-Print Network [OSTI]

J 310 Chemical Reactor Analysis and Optimal Digestion An optimal digestion theory can be readily derived from basic principles o f chemical reactor analysis and design Deborah L. Penry and Peter for formulating and solving optimization problems (Bellman 1957), the entire process is optimized only

Jumars, Pete

446

Environmental certification becoming increasingly crowded  

E-Print Network [OSTI]

Building Council -- which oversees the Leadership in Energy and Environmental Design (LEED) standards States and Canada as less onerous to comply with but still helpful to the impacts of logging. Fred

447

Tanden Mirror Reactor Systems Code (TMRSC)  

SciTech Connect (OSTI)

This paper describes a computer code developed to model a tandem mirror reactor. This is the first tandem mirror reactor model to couple the highly linked physics, magnetics, and neutronic analysis into a single code. Results from this code for two sensitivity studies are included in this paper. These studies are designed (1) to determine the impact of center cell plasma radius, length, and ion temperature on reactor cost and performance at constant fusion power and (2) to determine the impact of reactor power level on cost.

Reid, R.L.; Rothe, K.E.; Barrett, R.J.

1985-01-01T23:59:59.000Z

448

Photocatalytic reactor  

DOE Patents [OSTI]

A photocatalytic reactor is described for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane. 4 figs.

Bischoff, B.L.; Fain, D.E.; Stockdale, J.A.D.

1999-01-19T23:59:59.000Z

449

Critical assessment of thorium reactor technology .  

E-Print Network [OSTI]

??Thorium-based fuels for nuclear reactors are being considered for use with current and future designs in both large and small-scale energy production. Thorium-232 is as… (more)

Drenkhahn, Robert (Robert A.)

2012-01-01T23:59:59.000Z

450

Dust Divertor for a Tokamak Fusion Reactor  

Science Journals Connector (OSTI)

The conventional tokamak fusion reactor deploys a magnetic divertor design which channels...1], or covered by flowing liquid metals [2...]. A typical estimate for the plasma heat flux to the divertor for a tokama...

X. Z. Tang; G. L. Delzanno

2010-10-01T23:59:59.000Z

451

Radiation Damage and Tritium Breeding Study in a Fusion Reactor Using a Liquid Wall of Various Thorium Molten Salts  

Science Journals Connector (OSTI)

A new magnetic fusion reactor design, called APEX uses a liquid wall between fusion plasma and solid first wall to reach ... replacement of the first wall structure during the reactor’s operation due to the radia...

Mustafa Übeyli

2007-12-01T23:59:59.000Z

452

Consortium for Advanced Simulation of Light Water Reactors (CASL...  

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

has designed and operated 52 test reactors, including EBR-1, the world's first nuclear power plant Key Contributions System safety analysis Multiscale fuel performance...

453

Consortium for Advanced Simulation of Light Water Reactors (CASL...  

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

the better understanding of the system uncertainties and sensitivities afforded by the virtual reactor will identify improvements in both the operation and design of the fuel...

454

X-10 Graphite Reactor | Department of Energy  

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

X-10 Graphite Reactor X-10 Graphite Reactor X-10 Graphite Reactor X-10 Graphite Reactor When President Roosevelt in December 1942 authorized the Manhattan Project, the Oak Ridge site in eastern Tennessee had already been obtained and plans laid for an air-cooled experimental pile, a pilot chemical separation plant, and support facilities. The X-10 Graphite Reactor, designed and built in ten months, went into operation on November 4, 1943. The X-10 used neutrons emitted in the fission of uranium-235 to convert uranium-238 into a new element, plutonium-239. The reactor consists of a huge block of graphite, measuring 24 feet on each side, surrounded by several feet of high-density concrete as a radiation shield. The block is pierced by 1,248 horizontal diamond-shaped channels in

455

Hybrid adsorptive membrane reactor  

DOE Patents [OSTI]

A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

Tsotsis, Theodore T. (Huntington Beach, CA); Sahimi, Muhammad (Altadena, CA); Fayyaz-Najafi, Babak (Richmond, CA); Harale, Aadesh (Los Angeles, CA); Park, Byoung-Gi (Yeosu, KR); Liu, Paul K. T. (Lafayette Hill, PA)

2011-03-01T23:59:59.000Z

456

Biofuels and certification. A workshop at the Harvard Kennedy School of Government. Summary report  

SciTech Connect (OSTI)

Liquid biofuels can provide a substitute for fossil fuels in the transportation sector. Many countries have mandated the use of biofuels, by creating targets for their use. If not implemented with care, however, actions that increase biofuel production can put upward pressure on food prices, increase greenhouse gas (GHG) emissions, and exacerbate degradation of land, forest, and water sources. A strong global biofuels industry will not emerge unless these environmental and social concerns are addressed. Interested parties around the world are actively debating the design and implementation of policies to meet the biofuel goals, particularly those established in the United States and Europe. In general, policy options for managing the potential risks and benefits of biofuel development should specify not only clear standards governing biofuel content and production processes, but also certification processes for verifying whether particular biofuels meet those standards, and specific metrics or indicators on which to base the certification. Historically, many standards in the energy and environment fields have ultimately been set or supported by governments. Many of the certification processes have been voluntary, carried out by independent third parties. The biofuels case is a young one, however, with questions of goals, standards, certification, and metrics still in interdependent flux. The workshop focused its discussions on certification issues, but found the discussions naturally reaching into ongoing debates regarding possible goals, standards, and metrics. Many countries are proposing that for a biofuel to qualify as contributing to government-mandated targets or goals, it must be certified to meet certain standards. These standards could be limited to the amount of GHG emitted in the production process or could include a number of other environmental sustainability concerns ranging from deforestation and biodiversity to water resources. While the threat to both forests and food supplies from increased biofuel production is real, it is not clear that setting broad sustainability standards and then requiring sellers to certify that all of those standards have been met is the best way to address these interconnected problems. In particular, if too many standards and related certification requirements are put in place too soon, this could constrain the development of a global biofuels market. In contrast, certification targeted at a specific and limited set of problems and designed with the flexibility to adjust to changes in policies and programs can enhance the public's acceptance of the biofuel option while protecting key social and environmental goals. A second set of questions revolves around the locus of responsibility for certifying whether biofuel production meets sustainability targets. Should the biofuel processing firms, third parties, or governments be responsible for certifying the production of biofuels? This question also elicited significant discussion. While it could be easier to have individual country governments assume the certification of production responsibility, some governments may not have the capacity to implement an effective certification process. Production facilities that comply with international standards should not be kept out of the market because of their government's inability to manage the process. The possible contribution to effective certification of third party organizations or public-private partnerships should not be underestimated.

Devereaux, Charan; Lee, Henry

2009-06-01T23:59:59.000Z

457

STATEMENT OF CONSIDERATIONS Advance Test Reactor Class Waiver  

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

Advance Test Reactor Class Waiver Advance Test Reactor Class Waiver W(C)-2008-004 The Advanced Test Reactor (A TR) is a pressurized water test reactor at the Idaho National Laboratory (INL) that operates at low pressure and temperature. The ATR was originally designed to study the effects of intense radiation on reactor material and fuels . It has a "Four Leaf Clover" design that allows a diverse array of testing locations. The unique design allows for different flux in various locations and specialized systems also allow for certain experiments to be run at their own temperature and pressure. The U.S. Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007. This designation will allow the ATR to

458

Daya Bay Reactor Neutrino Project at NERSC  

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

Daya Bay Reactor Neutrino Daya Bay Reactor Neutrino Experiment Daya Bay Reactor Neutrino Experiment Daya Bay is an international neutrino-oscillation experiment designed to determine the last unknown neutrino mixing angle θ13 using anti-neutrinos produced by the Daya Bay and Ling Ao Nuclear Power Plant reactors. The experiment is being built by blasting three kilometers of tunnel through the granite rock under the mountains where the power plants are located. Data collection is now scheduled to start in in 2011. On the PDSF cluster at NERSC, Daya Bay performs simulations of the detectors, reactors, and surrounding mountains to help design and anticipate detector properties and behavior. Once real data are available, Daya Bay will be using NERSC to analyze data and NERSC HPSS will be the central U.S. repository for all raw

459

CESAR: Center for Exascale Simulation of Advanced Reactors | Argonne  

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

CESAR: Center for Exascale Simulation of Advanced Reactors CESAR: Center for Exascale Simulation of Advanced Reactors CESAR: Center for Exascale Simulation of Advanced Reactors CESAR is an interdisciplinary center for developing an innovative, next-generation nuclear reactor analysis tool that both utilizes and guides the development of exascale computing platforms. Existing reactor analysis codes are highly tuned and calibrated for commercial light-water reactors, but they lack the physics fidelity to seamlessly carry over to new classes of reactors with significantly different design characteristics-as, for example, innovative concepts such as TerraPower's Traveling Wave reactor and Small Modular Reactor concepts. Without vastly improved modeling capabilities, the economic and safety characteristics of these and other novel systems will require tremendous

460

GEN-IV Reactors  

Science Journals Connector (OSTI)

Generation-IV reactors are a set of nuclear reactors currently being developed under international collaborations targeting ... economics, proliferation resistance, and physical protection of nuclear energy. Nuclear

Taek K. Kim

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reactor design certification" 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.


461

The Netherlands Reactor Centre  

Science Journals Connector (OSTI)

... Two illustrated brochures in English have recently J. been issued by the Netherlands Reactor Centre ( ... Centre (Reactor Centrum Nederland). The first* gives a general survey of the ...

S. WEINTROUB

1964-04-04T23:59:59.000Z

462

How to Apply for ENERGY STAR® Certification  

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

ü ü ü ü ü ü ü ü ü ü ü ü ü ü ü ü ü ü ü "How To" Series How to Apply for ENERGY STAR ® Certification Commercial buildings that earn EPA's ENERGY STAR certification perform in the top 25 percent of similar buildings nationwide, as verified by a Licensed Professional (a Professional Engineer or a Registered Architect). ENERGY STAR certified buildings use an average of 35 percent less energy and are responsible for 35 percent fewer greenhouse gas emissions than average buildings. To qualify for the ENERGY STAR, a property must achieve an ENERGY STAR score of 75 or higher on EPA's 1 - 100 scale, which compares a property's energy performance to

463

Laboratory Equipment Donation Program - Certification Statement  

Office of Scientific and Technical Information (OSTI)

This certification is required by the Drug-Free Workplace Act of 1988 (Pub. This certification is required by the Drug-Free Workplace Act of 1988 (Pub. L. 100-690, Title V, Subtitle D), and is implemented through additions to the Department and Suspension regulations, published in the Federal Register on January 31, 1989. An organizational applicant certifies that it will provide a drug-free workplace by: Publishing a statement notifying employees that the unlawful manufacture, distribution, dispensing, possession, or use of a controlled substance is prohibited in the grantee's workplace and specifying the actions that will be taken against employees for violation of such prohibition. Establishing a drug-free awareness program to inform employees about: the dangers of drug abuse in the workplace; the grantee's policy of maintaining a drug-free workplace;

464

Certification of flow monitors for utility boilers  

SciTech Connect (OSTI)

The use of CEMS for measuring opacity, SO{sub 2}, NO{sub x}, CO{sub 2}, and O{sub 2} concentration was well proven prior to implementing the Part 75 CEMS program. However, the use of continuous flue gas flow monitoring devices is a relatively new instrumental technique. Limited operating data for flow monitors were available and little or no certification relative accuracy data were available prior to the Summer of 1993. However, because of the Part 75 requirements, utility companies contracted with CEMS vendors to install, start-up and certify flow monitors on Phase 1 and Phase 2 units. This paper presents the certification history of three different types of flow monitors (ultrasonic, pressure differential ({Delta}p) and thermal) installed at various utilities in the US. The data and experience was obtained from approximately 100 Phase 1 CEMS units and 200 Phase 1 CEMS units.

Bensink, J.; Beachler, D.; Joseph, J.

1995-12-31T23:59:59.000Z

465

U-182: Microsoft Windows Includes Some Invalid Certificates | Department of  

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

82: Microsoft Windows Includes Some Invalid Certificates 82: Microsoft Windows Includes Some Invalid Certificates U-182: Microsoft Windows Includes Some Invalid Certificates June 4, 2012 - 7:00am Addthis PROBLEM: A vulnerability was reported in Microsoft Windows. A remote user may be able to spoof code signing signatures. PLATFORM: Version(s): XP SP3, 2003 SP2, Vista SP2, 2008 SP2, 7 SP1, 2008 R2 SP1; and prior service packs ABSTRACT: The operating system includes some invalid intermediate certificates. The vulnerability is due to the certificate authorities and not the operating system itself. Reference Links: Security tracker ID 1027114 GENERIC-MAP-NOMATCH Vendor Advisory IMPACT ASSESSMENT: High Discussion: The invalid certificates and their thumbprints are: Microsoft Enforced Licensing Intermediate PCA: 2a 83 e9 02 05 91 a5 5f c6

466

Marketers' Certificate of Authority (Georgia) | Department of Energy  

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

Marketers' Certificate of Authority (Georgia) Marketers&#039; Certificate of Authority (Georgia) Marketers' Certificate of Authority (Georgia) < Back Eligibility Commercial Construction Developer Fuel Distributor Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Georgia Program Type Siting and Permitting The Marketers' Certificate of Authority is mandated by the Georgia Public Service Commission (PSC), and is a part of the Natural Gas Competition and Reregulation Act. It requires that any company seeking to distribute natural gas in the state obtain a certificate of authority from the PSC. To obtain a certificate of authority, an applicant must demonstrate to the Commission's satisfaction that it possesses adequate financial and technical capability to sell or offer to sell natural gas within the state

467

Creating security applications based on The Global Certificate Management System  

Science Journals Connector (OSTI)

The Certificate Management System (CMS) is a global network system whose primary services are generation, distribution, storage and verification of certificates. It supports various security applications which use public key cryptography by providing the means for the administration of certificates. This paper describes the interface between security enhanced application and the CMS. The interface layer with which the security applications are extended is named CMS Client. The CMS Client comprises a set of functions that enable the certification of users of security applications, retrieval of certificates and verification of retrieved certificates. The paper gives a short description of the CMS system and a detailed description of the CMS Client functions. Furthermore it describes how to extend the existing or create new security applications based on the CMS system.

Nada Kapidzic

1998-01-01T23:59:59.000Z

468

OMB No. 0925-0001 (Rev. 08/12 Approved Through 8/31/2015) Page 1 STTR Funding Agreement Certification STTR Funding Agreement Certification  

E-Print Network [OSTI]

.F.R. § 121.702. Yes No N/A Explain why N/A: 5. The birth certificates, naturalization papers, or passports Certification STTR Funding Agreement Certification Grant Application Number: Program Director must complete this certification at the time of award and any other time set forth in the Notice

Baker, Chris I.

469

OMB No. 0925-0001 (Rev. 08/12 Approved Through 8/31/2015) Page 1 SBIR Funding Agreement Certification SBIR Funding Agreement Certification  

E-Print Network [OSTI]

.F.R. § 121.702. Yes No N/A Explain why N/A: 5. The birth certificates, naturalization papers, or passports Certification SBIR Funding Agreement Certification Grant Application Number: Program Director must complete this certification at the time of award and any other time set forth in the Notice

Rau, Don C.

470

Solar and Wind Equipment Certification | Department of Energy  

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

Solar and Wind Equipment Certification Solar and Wind Equipment Certification Solar and Wind Equipment Certification < Back Eligibility Commercial Construction Industrial Installer/Contractor Residential Savings Category Home Weatherization Commercial Weatherization Solar Lighting Windows, Doors, & Skylights Heating & Cooling Commercial Heating & Cooling Heating Buying & Making Electricity Water Heating Wind Program Info State Arizona Program Type Equipment Certification Provider Arizona Solar Energy Industries Association Collectors, heat exchangers and storage units of solar energy systems -- and the installation of these systems -- sold or installed in Arizona must have a warranty of at least two years. The remaining components of the system and their installation must have a warranty of at least one year.

471

Rules Governing Water and Wastewater Operator Certification (Tennessee) |  

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

Rules Governing Water and Wastewater Operator Certification Rules Governing Water and Wastewater Operator Certification (Tennessee) Rules Governing Water and Wastewater Operator Certification (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Rules Governing Water and Wastewater Operator Certification are

472

2014-10-06 DOE Certification, Compliance, and Enforcement Overview...  

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

Dehumidifiers, Room Air Conditioners, Clothes Washers, Clothes Dryers, and Dishwashers 2014-10-06 DOE Certification, Compliance, and Enforcement Overview for Refrigerators,...

473

Considerations for Emerging Markets for Energy Savings Certificates  

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

70-44072 October 2008 Considerations for Emerging Markets for Energy Savings Certificates Barry Friedman and Lori Bird National Renewable Energy Laboratory Galen Barbose Lawrence...

474

Energy Performance Certification of Buildings: A Policy Tool...  

Open Energy Info (EERE)

Buildings: A Policy Tool to Improve Energy Efficiency Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Energy Performance Certification of Buildings: A Policy Tool to...

475

Forest Certification Programs in North and South America  

E-Print Network [OSTI]

Forest Certification Programs in North and South America: Motivation, Process, and Impacts compliance in Latin America discussion and corporate social responsibility Complex objectives

476

Certificate in Renewable Energy and the Environment | Photosynthetic...  

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

are organized into three discipline clusters: (1) Social Sciences & Humanities; (2) Architecture; and, (3) Natural Sciences & Engineering. The Certificate is granted by the...

477

Green Building Certification Systems Requirement for New Federal...  

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

CFR Parts 433, 435 and 436. greenblgcertcompare2014.docx More Documents & Publications Green Building Certification Systems Requirement for New Federal Buildings and Major...

478

Considerations for Emerging Markets for Energy Savings Certificates  

E-Print Network [OSTI]

RECs; state policy; renewable energy development; statefor renewable energy and energy savings. ” Energy Policy.renewable energy certificates (RECs) has emerged in both the voluntary and policy

Friedman, Barry

2009-01-01T23:59:59.000Z

479

Failure Rates from Certification Testing to UL and IEC Standards...  

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

Failure Rates from Certification Testing to UL and IEC Standards for Flat Plate PV Modules Larry Pratt*, Nicholas Riedel*, Martin Plass, and Michael Yamasaki CFV Solar Test...

480

Guidelines for Applicants for Energy Facility Site Certificates...  

Open Energy Info (EERE)

search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Guidelines for Applicants for Energy Facility Site CertificatesPermittingRegulatory...