Powered by Deep Web Technologies
Note: This page contains sample records for the topic "isotope reactor annual" 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.


1

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

2

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

3

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

4

2012 Annual Report Research Reactor Infrastructure Program  

SciTech Connect (OSTI)

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

Douglas Morrell

2012-11-01T23:59:59.000Z

5

Final Report on Isotope Ratio Techniques for Light Water Reactors  

SciTech Connect (OSTI)

The Isotope Ratio Method (IRM) is a technique for estimating the energy or plutonium production in a fission reactor by measuring isotope ratios in non-fuel reactor components. The isotope ratios in these components can then be directly related to the cumulative energy production with standard reactor modeling methods.

Gerlach, David C.; Gesh, Christopher J.; Hurley, David E.; Mitchell, Mark R.; Meriwether, George H.; Reid, Bruce D.

2009-07-01T23:59:59.000Z

6

High Flux Isotope Reactor power upgrade status  

SciTech Connect (OSTI)

A return to 100-MW operation is being planned for the High Flux Isotope Reactor (HFIR). Recent improvements in fuel element manufacturing procedures and inspection equipment will be exploited to reduce hot spot and hot streak factors sufficiently to permit the power upgrade without an increase in primary coolant pressure. Fresh fuel elements already fabricated for future use are being evaluated individually for power upgrade potential based on their measured coolant channel dimensions.

Rothrock, R.B.; Hale, R.E. [Oak Ridge National Lab., TN (United States); Cheverton, R.D. [Delta-21 Resources Inc., Oak Ridge, TN (United States)

1997-03-01T23:59:59.000Z

7

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Reactor Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. RADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor

8

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor

9

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

10

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor |  

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

Management- Oak Ridge National Laboratory High Flux Isotope Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope

11

The High Flux Isotope Reactor at Oak Ridge National Laboratory  

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

The High Flux Isotope Reactor at ORNL The High Flux Isotope Reactor at ORNL Aerial of the High Flux Isotope Reactor Site The High Flux Isotope Reactor site is located on the south side of the ORNL campus and is about a three-minute drive from her sister neutron facility, the Spallation Neutron Source. Operating at 85 MW, HFIR is the highest flux reactor-based source of neutrons for research in the United States, and it provides one of the highest steady-state neutron fluxes of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry, materials science, engineering, and biology. The intense neutron flux, constant power density, and constant-length fuel cycles are used by more than 500 researchers each year for neutron scattering research into

12

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

13

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

14

CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Oak Ridge National Laboratory High Flux Isotope Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Management - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications

15

High Flux Isotope Reactor (HFIR) | Nuclear Science | ORNL  

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

High Flux Isotope Reactor High Flux Isotope Reactor May 30, 2013 The High Flux Isotope Reactor (HFIR) first achieved criticality on August 25, 1965, and achieved full power in August 1966. It is a versatile 85-MW isotope production, research, and test reactor with the capability and facilities for performing a wide variety of irradiation experiments and a world-class neutron scattering science program. HFIR is a beryllium-reflected, light water-cooled and moderated flux-trap type swimming pool reactor that uses highly enriched uranium-235 as fuel. HFIR typically operates seven 23-to-27 day cycles per year. Irradiation facility capabilities include Flux trap positions: Peak thermal flux of 2.5X1015 n/cm2/s with similar epithermal and fast fluxes (Highest thermal flux available in the

16

High Flux Isotope Reactor named Nuclear Historic Landmark | ornl...  

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

late 1950s as a production reactor to meet anticipated demand for transuranic isotopes ("heavy" elements such as plutonium and curium). HFIR today is a DOE Office of Science User...

17

CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Training - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Conduct of Operations - Oak Ridge National Laboratory High Flux

18

Nuclear reactor fissile isotopes antineutrino spectra  

E-Print Network [OSTI]

Positron spectrum from inverse beta decay reaction on proton was measured in 1988-1990 as a result of neutrino exploration experiment. The measured spectrum has the largest statistics and lowest energy threshold between other neutrino experiments made that time at nuclear reactors. On base of the positron spectrum the standard antineutrino spectrum for typical reactor fuel composition was restored. In presented analysis the partial spectra forming this standard spectrum were extracted using specific method. They could be used for neutrino experiments data analysis made at any fuel composition of reactor core.

V. Sinev

2012-07-30T23:59:59.000Z

19

CRAD, Engineering- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Engineering Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

20

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

Note: This page contains sample records for the topic "isotope reactor annual" 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

CRAD, Training- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

22

Performance and safety parameters for the high flux isotope reactor  

SciTech Connect (OSTI)

A Monte Carlo depletion model for the High Flux Isotope Reactor (HFIR) Cycle 400 and its use in calculating parameters of relevance to the reactor performance and safety during the reactor cycle are presented in this paper. This depletion model was developed to serve as a reference for the design of a low-enriched uranium (LEU) fuel for an ongoing study to convert HFIR from high-enriched uranium (HEU) to LEU fuel; both HEU and LEU depletion models use the same methodology and ENDF/B-VII nuclear data as discussed in this paper. The calculated HFIR Cycle 400 parameters, which are compared with measurement data from critical experiments performed at HFIR, data included in the HFIR Safety Analysis Report (SAR), or data reported by previous calculations, provide a basis for verification or updating of the corresponding SAR data. (authors)

Ilas, G. [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831-6172 (United States); Primm III, T. [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831-6172 (United States); Primm Consulting, LLC, 945 Laurel Hill Road, Knoxville, TN 37923 (United States)

2012-07-01T23:59:59.000Z

23

High Flux Isotope Reactor (HFIR) | U.S. DOE Office of Science...  

Office of Science (SC) Website

(SUF) Division SUF Home About User Facilities User Facilities Dev X-Ray Light Sources Neutron Scattering Facilities High Flux Isotope Reactor (HFIR) Lujan Neutron Scattering...

24

Fabrication of control rods for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) is a research-type nuclear reactor that was designed and built in the early 1960s and has been in continuous operation since its initial criticality in 1965. Under current plans, the HFIR is expected to continue in operation until 2035. This report updates ORNL/TM-9365, Fabrication Procedure for HFIR Control Plates, which was mainly prepared in the early 1970's but was not issued until 1984, and reflects process changes, lessons learned in the latest control rod fabrication campaign, and suggested process improvements to be considered in future campaigns. Most of the personnel involved with the initial development of the processes and in part campaigns have retired or will retire soon. Because their unlikely availability in future campaigns, emphasis has been placed on providing some explanation of why the processes were selected and some discussions about the importance of controlling critical process parameters. Contained in this report is a description of the function of control rods in the reactor, the brief history of the development of control rod fabrication processes, and a description of procedures used in the fabrication of control rods. A listing of the controlled documents and procedures used in the last fabrication campaigns is referenced in Appendix A.

Sease, J.D.

1998-03-01T23:59:59.000Z

25

High Flux Isotope Reactor system RELAP5 input model  

SciTech Connect (OSTI)

A thermal-hydraulic computational model of the High Flux Isotope Reactor (HFIR) has been developed using the RELAP5 program. The purpose of the model is to provide a state-of-the art thermal-hydraulic simulation tool for analyzing selected hypothetical accident scenarios for a revised HFIR Safety Analysis Report (SAR). The model includes (1) a detailed representation of the reactor core and other vessel components, (2) three heat exchanger/pump cells, (3) pressurizing pumps and letdown valves, and (4) secondary coolant system (with less detail than the primary system). Data from HFIR operation, component tests, tests in facility mockups and the HFIR, HFIR specific experiments, and other pertinent experiments performed independent of HFIR were used to construct the model and validate it to the extent permitted by the data. The detailed version of the model has been used to simulate loss-of-coolant accidents (LOCAs), while the abbreviated version has been developed for the operational transients that allow use of a less detailed nodalization. Analysis of station blackout with core long-term decay heat removal via natural convection has been performed using the core and vessel portions of the detailed model.

Morris, D.G.; Wendel, M.W.

1993-01-01T23:59:59.000Z

26

Measuring of fissile isotopes partial antineutrino spectra in direct experiment at nuclear reactor  

E-Print Network [OSTI]

The direct measuring method is considered to get nuclear reactor antineutrino spectrum. We suppose to isolate partial spectra of the fissile isotopes by using the method of antineutrino spectrum extraction from the inverse beta decay positron spectrum applied at Rovno experiment. This admits to increase the accuracy of partial antineutrino spectra forming the total nuclear reactor spectrum. It is important for the analysis of the reactor core fuel composition and could be applied for non-proliferation purposes.

V. V. Sinev

2009-02-22T23:59:59.000Z

27

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

28

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

29

Determination of the theoretical feasibility for the transmutation of europium isotopes from high flux isotope reactor control cylinders  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is a 100 MWth light-water research reactor designed and built in the 1960s primarily for the production of transuranic isotopes. The HFIR is equipped with two concentric cylindrical blade assemblies, known as control cylinders, that are used to control reactor power. These control cylinders, which become highly radioactive from neutron exposure, are periodically replaced as part of the normal operation of the reactor. The highly radioactive region of the control cylinders is composed of europium oxide in an aluminum matrix. The spent HFIR control cylinders have historically been emplaced in the ORNL Waste Area Grouping (WAG) 6. The control cylinders pose a potential radiological hazard due to the long lived radiotoxic europium isotopes {sup 152}Eu, {sup 154}Eu, and {sup 155}Eu. In a 1991 health evaluation of WAG 6 (ERD 1991) it was shown that these cylinders were a major component of the total radioactivity in WAG 6 and posed a potential exposure hazard to the public in some of the postulated assessment scenarios. These health evaluations, though preliminary and conservative in nature, illustrate the incentive to investigate methods for permanent destruction of the europium radionuclides. When the cost of removing the control cylinders from WAG 6, performing chemical separations and irradiating the material in HFIR are factored in, the option of leaving the control cylinders in place for decay must be considered. Other options, such as construction of an engineered barrier around the disposal silos to reduce the chance of migration, should also be analyzed.

Elam, K.R.; Reich, W.J.

1995-09-01T23:59:59.000Z

30

Homogeneous fast-flux isotope-production reactor  

DOE Patents [OSTI]

A method is described for producing tritium in a liquid metal fast breeder reactor. Lithium target material is dissolved in the liquid metal coolant in order to facilitate the production and removal of tritium.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

31

Development of High Flux Isotope Reactor (HFIR) subcriticality monitoring methods  

SciTech Connect (OSTI)

Use of subcritical source multiplication measurements during refueling has been investigated as a possible replacement for out-of-reactor subcriticality measurements formerly made on fresh HFIR fuel elements at the ORNL Critical Experiment Facility. These measurements have been used in the past for preparation of estimated critical rod positions, and as a partial verification, prior to reactor startup, that the requirements for operational shutdown margin would be met. Results of subcritical count rate data collection during recent HFIR refuelings and supporting calculations are described illustrating the intended measurement method and its expected uncertainty. These results are compared to historical uses of the out-of-reactor core measurements and their accuracy requirements, and a planned in-reactor test is described which will establish the sensitivity of the method and calibrate it for future routine use during HFIR refueling. 2 refs., 1 fig., 2 tabs.

Rothrock, R.B.

1991-01-01T23:59:59.000Z

32

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Management portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

33

CRAD, Environmental Protection- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Environmental Compliance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

34

CRAD, Configuration Management- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

35

CRAD, Occupational Safety & Health- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Industrial Safety and Hygiene Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

36

CRAD, Configuration Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Configuration Management Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

37

CRAD, Emergency Management- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Emergency Management Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

38

CRAD, Conduct of Operations- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program in preparation for restart of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

39

CRAD, Conduct of Operations- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February, 2007 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, High Flux Isotope Reactor.

40

CRAD, Training- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Training Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

Note: This page contains sample records for the topic "isotope reactor annual" 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

CRAD, Radiological Controls- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Radiation Protection Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

42

CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

43

CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

44

CRAD, Maintenance- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Maintenance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

45

CRAD, Occupational Safety & Health- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Occupational Safety and Health Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

46

CRAD, Nuclear Safety- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

47

CRAD, Quality Assurance- Oak Ridge National Laboratory High Flux Isotope Reactor  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Quality Assurance Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

48

2014 Annual Planning Summary for the NNSA Naval Reactors  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the NNSA Naval Reactors.

49

Three-dimensional calculations of neutron streaming in the beam tubes of the ORNL HFIR (High Flux Isotope Reactor) Reactor  

SciTech Connect (OSTI)

The streaming of neutrons through the beam tubes in High Flux Isotope Reactor at Oak Ridge National Laboratory has resulted in a reduction of the fracture toughness of the reactor vessel. As a result, an evaluation of vessel integrity was undertaken in order to determine if the reactor can be operated again. As a part of this evaluation, three-dimensional neutron transport calculations were performed to obtain fluxes at points of interest in the wall of the vessel. By comparing the calculated and measured activation of dosimetry specimens from the vessel surveillance program, it was determined that the calculated flux shape was satisfactory to transpose the surveillance data to the locations in the vessel. A bias factor was applied to correct for the average C/E ratio of 0.69. 8 refs., 7 figs., 3 tabs.

Childs, R.L.; Rhoades, W.A.; Williams, L.R.

1988-01-01T23:59:59.000Z

50

High flux isotope reactor: Quarterly report October through December 1986  

SciTech Connect (OSTI)

Two routine cycles of operation of the HFIR reactor were completed during the quarter. The shutdowns to end these cycles were both scheduled. The end-of-cycle 287 shutdown was extended indefinitely to investigate the embrittlement of reactor vessel materials due to radiation damage. The reactor remains down at the end of the quarter. Following the scheduled end-of-cycle 287 shutdown period, subsequent shutdown time was designated as unscheduled. The two scheduled shutdowns, fourth quarter downtime resulting from a third quarter scheduled shutdown, and the extended unscheduled shutdown account for the low 44.2% on-stream time for the quarter. The scheduled control plate replacement and vessel internals inspection was completed at the end-of-cycle 287. The inspection revealed a blister on control cylinder 9. This flaw was attributed to a manufacturing defect.

Corbett, B.L.; Farrar, M.B.

1987-04-01T23:59:59.000Z

51

Evolution of isotopic composition of reprocessed uranium during the multiple recycling in light water reactors with natural uranium feed  

SciTech Connect (OSTI)

A complex approach based on the consistent modeling of neutron-physics processes and processes of cascade separation of isotopes is applied for analyzing physical problems of the multiple usage of reprocessed uranium in the fuel cycle of light water reactors. A number of scenarios of multiple recycling of reprocessed uranium in light water reactors are considered. In the process, an excess absorption of neutrons by the {sup 236}U isotope is compensated by re-enrichment in the {sup 235}U isotope. Specific consumptions of natural uranium for re-enrichment of the reprocessed uranium depending on the content of the {sup 232}U isotope are obtained.

Smirnov, A. Yu., E-mail: a.y.smirnoff@rambler.ru; Sulaberidze, G. A. [National Research Nuclear University MEPhI (Russian Federation); Alekseev, P. N.; Dudnikov, A. A.; Nevinitsa, V. A., E-mail: neva@dhtp.kiae.ru; Proselkov, V. N.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2012-12-15T23:59:59.000Z

52

A strategy for intensive production of molybdenum-99 isotopes for nuclear medicine using CANDU reactors  

Science Journals Connector (OSTI)

Technetium-99m is an important medical isotope utilized worldwide in nuclear medicine and is produced from the decay of its parent isotope, molybdenum-99. The online fueling capability and compact fuel of the CANDU®11CANDU is a trademark of Atomic Energy of Canada Limited. reactor allows for the potential production of large quantities of 99Mo. This paper proposes 99Mo production strategies using modified target fuel bundles loaded into CANDU fuel channels. Using a small group of channels a yield of 89–113% of the weekly world demand for 99Mo can be obtained.

A.C. Morreale; D.R. Novog; J.C. Luxat

2012-01-01T23:59:59.000Z

53

High flux isotope reactor. Quarterly report, January-March 1982  

SciTech Connect (OSTI)

Routine reactor operation with four end-of-cycle shutdowns and one scheduled shutdown for training purposes resulted in an on-stream time of 92.1% for the quarter. The outer control plates were changed. The control plate track guide bearings, the control plate extension tubes, and the shock absorbers were replaced and a semiannual core component inspection was made. Cracks were discovered in the outermost ring of the beryllium reflector.

Corbett, B.L.; Poteet, K.H.

1982-06-01T23:59:59.000Z

54

High Flux Isotope Reactor quarterly report, April-June 1986  

SciTech Connect (OSTI)

Four routine cycles of operation were completed during the second quarter. Four scheduled end-of-cycle shutdowns, three other scheduled shutdowns, and two unscheduled shutdowns resulted in an on-stream time of 90.7%. The control plates and cylinder were replaced during the end-of-cycle 281 shutdown. Control plate set 2 and previously unirradiated cylinder No. 9 were inserted into the reactor.

Corbett, B.L.; Farrar, M.B.

1986-08-01T23:59:59.000Z

55

External event Probabilistic Risk Assessment for the High Flux Isotope Reactor (HFIR)  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) is a high performance isotope production and research reactor which has been in operation at Oak Ridge National Laboratory (ORNL) since 1965. In late 1986 the reactor was shut down as a result of discovery of unexpected neutron embrittlement of the reactor vessel. In January of 1988 a level 1 Probabilistic Risk Assessment (PRA) (excluding external events) was published as part of the response to the many reviews that followed the shutdown and for use by ORNL to prioritize action items intended to upgrade the safety of the reactor. A conservative estimate of the core damage frequency initiated by internal events for HFIR was 3.11 {times} 10{sup {minus}4}. In June 1989 a draft external events initiated PRA was published. The dominant contributions from external events came from seismic, wind, and fires. The overall external event contribution to core damage frequency is about 50% of the internal event initiated contribution and is dominated by seismic events.

Flanagan, G.F.; Johnson, D.H.; Buttemer, D.; Perla, H.F.; Chien, S.H. (Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

56

Small break LOCA analysis of the ONRL high flux isotope reactor  

SciTech Connect (OSTI)

A digital simulation program, HFIRSYS, was developed using MMS to analyze small break loss of coolant events in the ORNL High Flux Isotope Reactor. The code evaluates the response of the primary reactor system including automatic controls actions resulting from breaks in auxiliary piping connected to the primary. The primary output of the code is the margin to the onset of nucleate boiling expressed as a ratio of heat flux which would cause boiling to the current hot channel heat flux. A description of the model, validation results and a sample transient are presented.

Wilson, T.L. Jr.; Cook, D.H.; Sozer, A.

1988-01-01T23:59:59.000Z

57

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

58

Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes  

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

Independent Oversight Review of the Independent Oversight Review of the Oak Ridge National Laboratory High Flux Isotope Reactor Implementation Verification Review Processes May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background........................................................................................................................................... 1 3.0 Scope..................................................................................................................................................... 2

59

Seismic, high wind, tornado, and probabilistic risk assessments of the High Flux Isotope Reactor  

SciTech Connect (OSTI)

Natural phenomena analyses were performed on the High Flux Isotope Reactor (HFIR) Deterministic and probabilistic evaluations were made to determine the risks resulting from earthquakes, high winds, and tornadoes. Analytic methods in conjunction with field evaluations and an earthquake experience data base evaluation methods were used to provide more realistic results in a shorter amount of time. Plant modifications completed in preparation for HFIR restart and potential future enhancements are discussed. 5 figs.

Harris, S.P.; Stover, R.L.; Hashimoto, P.S.; Dizon, J.O. (EQE, Inc., San Francisco, CA (USA); Oak Ridge National Lab., TN (USA); EQE, Inc., San Francisco, CA (USA))

1989-01-01T23:59:59.000Z

60

The computerized identification of reactor-produced isotopes in an activation analysis environment  

E-Print Network [OSTI]

- ability of a complete, positive identification appears small. How- ever, with the addition of a least squares method of resolving interferences and the application of a figure indicating the value (figure-of-merit) placed on each elimination test...THE COMPUTERIZED IDENTIFICATION OF REACTOR-PRODUCED ISOTOP ' S IN AN ACTIVATION ANALYSIS ENVIRON&vIENT A Thesi. s by DANIEI. aOIIN SCHLUETER Submitted to the Grec'u&ate College of Texas ARM University in pa. tial fulfillment o...

Schlueter, Daniel John

1971-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Annual Fossil-Fuel CO2 Emissions: Global Stable Carbon Isotopic Signature  

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

2 2 data Data image Documentation Contributors R.J. Andres, T.A. Boden, and G. Marland The 2012 revision of this database contains estimates of the annual, global mean value of δ 13C of CO2 emissions from fossil-fuel consumption and cement manufacture for 1751-2009. These estimates of the carbon isotopic signature account for the changing mix of coal, petroleum, and natural gas being consumed and for the changing mix of petroleum from various producing areas with characteristic isotopic signatures. This time series of global fossil-fuel del 13C signature provides an additional constraint for balancing the sources and sinks of the global carbon cycle and complements the atmospheric δ 13C measurements that are used to partition the uptake of fossil carbon emissions among the ocean, atmosphere, and terrestrial

62

Annual Fossil-Fuel CO2 Emissions: Global Stable Carbon Isotopic Signature  

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

3 3 data Data image Documentation Contributors R.J. Andres, T.A. Boden, and G. Marland The 2013 revision of this database contains estimates of the annual, global mean value of δ 13C of CO2 emissions from fossil-fuel consumption and cement manufacture for 1751-2010. These estimates of the carbon isotopic signature account for the changing mix of coal, petroleum, and natural gas being consumed and for the changing mix of petroleum from various producing areas with characteristic isotopic signatures. This time series of global fossil-fuel del 13C signature provides an additional constraint for balancing the sources and sinks of the global carbon cycle and complements the atmospheric δ 13C measurements that are used to partition the uptake of fossil carbon emissions among the ocean, atmosphere, and terrestrial

63

Annual Fossil-Fuel CO2 Emissions: Global Stable Carbon Isotopic Signature  

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

1 1 data Data image Documentation Contributors R.J. Andres, T.A. Boden, and G. Marland The 2011 revision of this database contains estimates of the annual, global mean value of del 13C of CO2 emissions from fossil-fuel consumption and cement manufacture for 1751-2008. These estimates of the carbon isotopic signature account for the changing mix of coal, petroleum, and natural gas being consumed and for the changing mix of petroleum from various producing areas with characteristic isotopic signatures. This time series of global fossil-fuel del 13C signature provides an additional constraint for balancing the sources and sinks of the global carbon cycle and complements the atmospheric del 13C measurements that are used to partition the uptake of fossil carbon emissions among the ocean, atmosphere, and terrestrial

64

Isotope correlations for determining the isotopic composition of plutonium produced in research and power reactors using the experimental data obtained by alpha and mass spectrometry  

Science Journals Connector (OSTI)

Correlations have been developed for obtaining the isotopic composition of Pu produced in Indian research (CIRUS, DHRUVA) and power (PHWR) reactors. The experimental data obtained on 238Pu/(239Pu + 240Pu) alpha activity ratio using alpha spectrometry and on 240Pu/239Pu, 241Pu/239Pu, 242Pu/239Pu atom ratios by thermal ionisation mass spectrometry were used for developing isotope correlations.

S.K. Aggarwal; D. Alamelu

2005-01-01T23:59:59.000Z

65

Integral Fast Reactor Program annual progress report, FY 1991  

SciTech Connect (OSTI)

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

Not Available

1992-06-01T23:59:59.000Z

66

Integral Fast Reactor Program annual progress report, FY 1991  

SciTech Connect (OSTI)

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R D.

Not Available

1992-06-01T23:59:59.000Z

67

RELAP5 model of the high flux isotope reactor with low enriched fuel thermal flux profiles  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) currently uses highly enriched uranium (HEU) fabricated into involute-shaped fuel plates. It is desired that HFIR be able to use low enriched uranium (LEU) fuel while preserving the current performance capability for its diverse missions in material irradiation studies, isotope production, and the use of neutron beam lines for basic research. Preliminary neutronics and depletion simulations of HFIR with LEU fuel have arrived to feasible fuel loadings that maintain the neutronics performance of the reactor. This article illustrates preliminary models developed for the analysis of the thermal-hydraulic characteristics of the LEU core to ensure safe operation of the reactor. The beginning of life (BOL) LEU thermal flux profile has been modeled in RELAP5 to facilitate steady state simulation of the core cooling, and of anticipated and unanticipated transients. Steady state results are presented to validate the new thermal power profile inputs. A power ramp, slow depressurization at the outlet, and flow coast down transients are also evaluated. (authors)

Banfield, J.; Mervin, B.; Hart, S.; Ritchie, J.; Walker, S.; Ruggles, A.; Maldonado, G. I. [Dept. of Nuclear Engineering, Univ. of Tennessee Knoxville, Knoxville, TN 37996-2300 (United States)

2012-07-01T23:59:59.000Z

68

Preliminary Notice of Violation - High Flux Isotope Reactor, November 18, 2003  

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

Department of Energy Department of Energy Washington, DC 20585 November 18, 2003 Dr. Jeffrey Wadsworth [ ] UT-Battelle P.O. Box 2008 Oak Ridge, TN 37831-6255 EA 2003-10 Subject: Preliminary Notice of Violation and Proposed Imposition of Civil Penalty $151,250 Dear Dr. Wadsworth: This letter refers to the Department of Energy's Office of Price-Anderson Enforcement (OE) investigation of the facts and circumstances surrounding nuclear safety work control issues at the High Flux Isotope Reactor (HFIR) and the Radiochemical Engineering Development Center (REDC). Our office initiated this investigation in response to a manual reactor shutdown due to a control cylinder maintenance safety deficiency and operation of a radiological [ ] without required containment, as

69

A neutronic feasibility study for LEU conversion of the high flux isotope reactor (HFIR).  

SciTech Connect (OSTI)

A neutronic feasibility study was performed to determine the uranium densities that would be required to convert the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) from HEU (93%) to LEU (<20%)fuel. The LEU core that was studied is the same as the current HEU core, except for potential changes in the design of the fuel plates. The study concludes that conversion of HFIR from HEU to LEU fuel would require an advanced fuel with a uranium density of 6-7 gU/cm{sup 3} in the inner fuel element and 9-10 gU/cm{sup 3} in the outer fuel element to match the cycle length of the HEU core. LEU fuel with uranium density up to 4.8 gU/cm{sup 3} is currently qualified for research reactor use. Modifications in fuel grading and burnable poison distribution are needed to produce an acceptable power distribution.

Mo, S. C.

1998-01-14T23:59:59.000Z

70

Establishing Specifications for Low Enriched Uranium Fuel Operations Conducted Outside the High Flux Isotope Reactor Site  

SciTech Connect (OSTI)

The National Nuclear Security Administration (NNSA) has funded staff at Oak Ridge National Laboratory (ORNL) to study the conversion of the High Flux Isotope Reactor (HFIR) from the current, high enriched uranium fuel to low enriched uranium fuel. The LEU fuel form is a metal alloy that has never been used in HFIR or any HFIR-like reactor. This report provides documentation of a process for the creation of a fuel specification that will meet all applicable regulations and guidelines to which UT-Battelle, LLC (UTB) the operating contractor for ORNL - must adhere. This process will allow UTB to purchase LEU fuel for HFIR and be assured of the quality of the fuel being procured.

Pinkston, Daniel [ORNL; Primm, Trent [ORNL; Renfro, David G [ORNL; Sease, John D [ORNL

2010-10-01T23:59:59.000Z

71

ISOTOPES  

E-Print Network [OSTI]

uranium, heavy-water-moderated CANDU reactor, as contrastedis important, and in the CANDU power reactor, which uses

Lederer, C. Michael

2013-01-01T23:59:59.000Z

72

Reactor Physics Studies of Reduced-Tantaulum-Content Control and Safety Elements for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

Some of the unirradiated High Flux Isotope Reactor (HFIR) control elements discharged during the late 1990s were observed to have cladding damage--local swelling or blistering. The cladding damage was limited to the tantalum/europium interface of the element and is thought to result from interaction of hydrogen and europium to form a compound of lower density than europium oxide, thus leading to a ''blistering'' of the control plate cladding. Reducing the tantalum loading in the control plates should help preclude this phenomena. The impact of the change to the control plates on the operation of the reactor was assessed. Regarding nominal, steady-state reactor operation, the impact of the change in the power distribution in the core due to reduced tantalum content was calculated and found to be insignificant. The magnitude and impact of the change in differential control element worth was calculated, and the differential worths of reduced tantalum elements vs the current elements from equivalent-burnup critical configurations were determined to be unchanged within the accuracy of the computational method and relevant experimental measurements. The location of the critical control elements symmetric positions for reduced tantalum elements was found to be 1/3 in. less withdrawn relative to existing control elements regardless of the value of fuel cycle burnup (time in the fuel cycle). The magnitude and impact of the change in the shutdown margin (integral rod worth) was assessed and found to be unchanged. Differential safety element worth values for the reduced-tantalum-content elements were calculated for postulated accident conditions and were found to be greater than values currently assumed in HFIR safety analyses.

Primm, R.T., III

2003-11-01T23:59:59.000Z

73

Irradiation research capabilities at HFIR (High Flux Isotope Reactor) and ANS (Advanced Neutron Source)  

SciTech Connect (OSTI)

A variety of materials irradiation facilities exist in the High Flux Isotope Reactor (HFIR) and are planned for the Advanced Neutron Source (ANS) reactor. In 1986 the HFIR Irradiation Facilities Improvement (HIFI) project began modifications to the HFIR which now permit the operation of two instrumented capsules in the target region and eight capsules of 46-mm OD in the RB region. Thus, it is now possible to perform instrumented irradiation experiments in the highest continuous flux of thermal neutrons available in the western world. The new RB facilities are now large enough to permit neutron spectral tailoring of experiments and the modified method of access to these facilities permit rotation of experiments thereby reducing fluence gradients in specimens. A summary of characteristics of irradiation facilities in HFIR is presented. The ANS is being designed to provide the highest thermal neutron flux for beam facilities in the world. Additional design goals include providing materials irradiation and transplutonium isotope production facilities as good, or better than, HFIR. The reference conceptual core design consists of two annular fuel elements positioned one above the other instead of concentrically as in the HFIR. A variety of materials irradiation facilities with unprecedented fluxes are being incorporated into the design of the ANS. These will include fast neutron irradiation facilities in the central hole of the upper fuel element, epithermal facilities surrounding the lower fuel element, and thermal facilities in the reflector tank. A summary of characteristics of irradiation facilities presently planned for the ANS is presented. 2 tabs.

Thoms, K.R.

1990-01-01T23:59:59.000Z

74

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

75

Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method  

SciTech Connect (OSTI)

For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios were measured again in unirradiated samples to obtain reference or starting values at the same time irradiated samples were analyzed. In particular, 49Ti/48Ti ratios were indistinguishably close to values determined several months earlier and to expected natural values. 2. 49Ti/48Ti ratios were measured in 3 irradiated samples thus far, and demonstrate marked departures from natural or initial ratios, well beyond analytical uncertainty, and the ratios vary with reported fluence values. The irradiated samples appear to have significant surface contamination or radiation damage which required more time for SIMS analyses. 3. Other activated impurity elements still limit the sample size for SIMS analysis of irradiated samples. The sub-samples chosen for SIMS analysis, although smaller than optimal, were still analyzed successfully without violating the conditions of the applicable Radiological Work Permit

Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J.; Hurley, David E.

2007-11-01T23:59:59.000Z

76

Reactor physics input to the safety analysis report for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

HFIR specific, few group neutron and coupled neutron-gamma libraries have been prepared. These are based on data from ENDF/B-V and beginning-of-life (BOL) conditions. The neutron library includes actinide data for curium target rods. Six critical experiments, collectively designated HFIR critical experiment 4, were analyzed. Calculated k-effective was 2% high at BOL-typical conditions but was 1.0 at end-of-life-typical conditions. The local power density distributions were calculated for each of the critical experiments. The axially averaged values at a given radius were frequently within experimental error. However at individual points, the calculated local power densities were significantly different from the experimentally derived values (several times greater than experimental uncertainty). A reassessment of the foil activation data with transport theory techniques seems desirable. Using the results of the critical experiments study, a model of current HFIR configuration was prepared. As with the critical experiments, BOL k-effective was high (3%). However, end-of-life k-effective was high (2%). The end-of-life concentrations of fission products were compared to those generated using the ORIGEN code. Agreement was generally good through differences in the inventories of some important nuclides, Xe and I, need to be understood. End-of-cycle curium target isotopics based on measured, discharged target rods were compared to calculated values and agreement was good. Axial flux plots at various irradiation positions were generated. Time-dependent power distributions based on two-dimensional calculations were provided.

Primm, R.T. III.

1992-03-01T23:59:59.000Z

77

Temperature Zonal Combustion Reactor for the 15-Nitrogen and 13-Carbon Isotopic Determination of Enriched Biosynthetic Materials  

Science Journals Connector (OSTI)

Temperature Zonal Combustion Reactor for the 15-Nitrogen and 13-Carbon Isotopic Determination of Enriched Biosynthetic Materials ... After the furnace controller had been reset from 250 °C (VHT) to 700 °C (combustion), the sample zone temperature increased at ?50 °C/min, which coincided with a pressure rise from 255 to 363 Torr (over some 8 min). ...

Michael May; John Kuo; Michael Gray; I. Knyazhansky; C. T. Tan

2010-03-31T23:59:59.000Z

78

A Review of Proposed Upgrades to the High Flux Isotope Reactor and Potential Impacts to Reactor Vessel Integrity  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) was scheduled in October 2000 to implement design upgrades that include the enlargement of the HB-2 and HB-4 beam tubes. Higher dose rates and higher radiation embrittlement rates were predicted for the two beam-tube nozzles and surrounding vessel areas. ORNL had performed calculations for the upgraded design to show that vessel integrity would be maintained at acceptable levels. Pacific Northwest National Laboratory (PNNL) was requested by the U.S. Department of Energy Headquarters (DOE/HQ) to perform an independent peer review of the ORNL evaluations. PNNL concluded that the calculated probabilities of failure for the HFIR vessel during hydrostatic tests and for operational conditions as estimated by ORNL are an acceptable basis for selecting pressures and test intervals for hydrostatic tests and for justifying continued operation of the vessel. While there were some uncertainties in the embrittlement predictions, the ongoing efforts at ORNL to measure fluence levels at critical locations of the vessel wall and to test materials from surveillance capsules should be effective in dealing with embrittlement uncertainties. It was recommended that ORNL continue to update their fracture mechanics calculations to reflect methods and data from ongoing research for commercial nuclear power plants. Such programs should provide improved data for vessel fracture mechanics calculations.

Simonen, Fredric A.

2001-05-31T23:59:59.000Z

79

Assessment of Non-traditional Isotopic Ratios by Mass Spectrometry for Analysis of Nuclear Activities: Annual Report Year 2  

SciTech Connect (OSTI)

The objective of this work is to identify isotopic ratios suitable for analysis via mass spectrometry that distinguish between commercial nuclear reactor fuel cycles, fuel cycles for weapons grade plutonium, and products from nuclear weapons explosions. Methods will also be determined to distinguish the above from medical and industrial radionuclide sources. Mass spectrometry systems will be identified that are suitable for field measurement of such isotopes in an expedient manner. Significant progress has been made with this project within the past year: (1) Isotope production from commercial nuclear fuel cycles and nuclear weapons fuel cycles have been modeled with the ORIGEN and MCNPX codes. (2) MCNPX has been utilized to calculate isotopic inventories produced in a short burst fast bare sphere reactor (to approximate the signature of a nuclear weapon). (3) Isotopic ratios have been identified that are good for distinguishing between commercial and military fuel cycles as well as between nuclear weapons and commercial nuclear fuel cycles. (4) Mass spectrometry systems have been assessed for analysis of the fission products of interest. (5) A short-list of forensic ratios have been identified that are well suited for use in portable mass spectrometry systems.

Biegalski, S; Buchholz, B

2009-08-26T23:59:59.000Z

80

Large break loss-of-coolant accident analyses for the high flux isotope reactor  

SciTech Connect (OSTI)

The US Department of Energy's High Flux Isotope Reactor (HFIR) was analyzed to evaluate it's response to a spectrum of loss-of-coolant accidents (LOCAs) with potential for leading to core damage. The MELCOR severe accident analysis code (version 1.7.1) was used to evaluate the overall dynamic response of HFIR. Before conducting LOCA analyses, the steady-state thermal-hydraulic parameters evaluated by MELCOR for various loop sections were verified against steady-state operating data. Thereafter, HFIR depressurization tests were simulated to evaluate the system pressure change for a given depletion in coolant inventory. Interesting and important safety-related phenomena were observed. The current analyses (which should be considered preliminary) that occur over a period from 1 to 3 seconds do not lead to core wide fuel melting. Core fluid flashing during the initial rapid depressurization does cause fuel temperature excursions due to adiabatic-like heatup. 3 refs., 4 figs.

Taleyarkhan, R.P. (Oak Ridge National Lab., TN (USA))

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

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

82

Reactivity Accountability Attributed to Reflector Poisons in the High Flux Isotope Reactor  

SciTech Connect (OSTI)

The objective of this study is to develop a methodology to predict the reactivity impact as a function of outage time between cycles of 3He, 6Li, and other poisons in the High Flux Isotope Reactor s (HFIR) beryllium reflector. The reactivity worth at startup of the HFIR has been incorrectly predicted in the past after the reactor has been shut-down for long periods of time. The incorrect prediction was postulated to be due to the erroneous calculation of 3He buildup in the beryllium reflector. It is necessary to develop a better estimate of the start-of-cycle symmetric critical control element positions since if the estimated and actual symmetrical critical control element positions differ by more than $1.55 in reactivity (approximately one-half inch in control element startup position), HFIR is to be shutdown and a technical evaluation is performed to resolve the discrepancy prior to restart. 3He is generated and depleted during operation, but during an outage, the depletion of 3He ceases because it is a stable isotope. 3He is born from the radioactive decay of tritium, and thus the concentration of 3He increases during shutdown. SCALE, specifically the TRITON and CSAS5 control modules including the KENO V.A, COUPLE, and ORIGEN functional modules were utilized in this study. An equation relating the down time (td) to the change in symmetric control element position was generated and validated against measurements for approximately 40 HFIR operating cycles. The newly-derived correlation was shown to improve accuracy of predictions for long periods of down time.

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL

2009-12-01T23:59:59.000Z

83

Extraction of gadolinium from high flux isotope reactor control plates. [Alternative method  

SciTech Connect (OSTI)

Gadolinium-153 is an important radioisotope used in the diagnosis of various bone disorders. Recent medical and technical developments in the detection and cure of osteoporosis, a bone disease affecting an estimated 50 million people, have greatly increased the demand for this isotope. The Oak Ridge National Laboratory (ORNL) has produced /sup 153/Gd since 1980 primarily through the irradiation of a natural europium-oxide powder followed by the chemical separation of the gadolinium fraction from the europium material. Due to the higher demand for /sup 153/Gd, an alternative production method to supplement this process has been investigated. This process involves the extraction of gadolinium from the europium-bearing region of highly radioactive, spent control plates used at the High Flux Isotope Reactor (HFIR) with a subsequent re-irradiation of the extracted material for the production of the /sup 153/Gd. Based on the results of experimental and calculational analyses, up to 25 grams of valuable gadolinium (greater than or equal to60% enriched in /sup 152/Gd) resides in the europium-bearing region of the HFIR control components of which 70% is recoverable. At a specific activity yield of 40 curies of /sup 153/Gd for each gram of gadolinium re-irradiated, 700 one-curie sources can be produced from each control plate assayed.

Kohring, M.W.

1987-04-01T23:59:59.000Z

84

STATUS OF HIGH FLUX ISOTOPE REACTOR IRRADIATION OF SILICON CARBIDE/SILICON CARBIDE JOINTS  

SciTech Connect (OSTI)

Development of silicon carbide (SiC) joints that retain adequate structural and functional properties in the anticipated service conditions is a critical milestone toward establishment of advanced SiC composite technology for the accident-tolerant light water reactor (LWR) fuels and core structures. Neutron irradiation is among the most critical factors that define the harsh service condition of LWR fuel during the normal operation. The overarching goal of the present joining and irradiation studies is to establish technologies for joining SiC-based materials for use as the LWR fuel cladding. The purpose of this work is to fabricate SiC joint specimens, characterize those joints in an unirradiated condition, and prepare rabbit capsules for neutron irradiation study on the fabricated specimens in the High Flux Isotope Reactor (HFIR). Torsional shear test specimens of chemically vapor-deposited SiC were prepared by seven different joining methods either at Oak Ridge National Laboratory or by industrial partners. The joint test specimens were characterized for shear strength and microstructures in an unirradiated condition. Rabbit irradiation capsules were designed and fabricated for neutron irradiation of these joint specimens at an LWR-relevant temperature. These rabbit capsules, already started irradiation in HFIR, are scheduled to complete irradiation to an LWR-relevant dose level in early 2015.

Katoh, Yutai [ORNL; Koyanagi, Takaaki [ORNL; Kiggans, Jim [ORNL; Cetiner, Nesrin [ORNL; McDuffee, Joel [ORNL

2014-09-01T23:59:59.000Z

85

Radioisotopic Impurities in Promethium-147 Produced at the ORNL High Flux Isotope Reactor.  

E-Print Network [OSTI]

??There is an intense interest in the availability of radioactive isotopes that could be developed into nuclear batteries. Promethium-147 is one of the isotopes of… (more)

Hinderer, James Howard

2010-01-01T23:59:59.000Z

86

Density of Gadolinium Nitrate Solutions for the High Flux Isotope Reactor  

SciTech Connect (OSTI)

In late 1992, the High Flux Isotope Reactor (HFIR) was planning to switch the solution contained in the poison injection tank from cadmium nitrate to gadolinium nitrate. The poison injection system is an emergency system used to shut down the reactor by adding a neutron poison to the cooling water. This system must be able to supply a minimum of 69 pounds of gadolinium to the reactor coolant system in order to guarantee that the reactor would become subcritical. A graph of the density of gadolinium nitrate solutions over a concentration range of 5 to 30 wt% and a temperature range of 15 to 40{sup o}C was prepared. Routine density measurements of the solution in the poison injection tank are made by HFIR personnel, and an adaptation of the original graph is used to determine the gadolinium nitrate concentration. In late 2008, HFIR personnel decided that the heat tracing that was present on the piping for the poison injection system could be removed without any danger of freezing the solution; however, the gadolinium nitrate solution might get as cold as 5{sup o}C. This was outside the range of the current density-concentration correlation, so the range needed to be expanded. This report supplies a new density-concentration correlation that covers the extended temperature range. The correlation is given in new units, which greatly simplifies the calculation that is required to determine the pounds of gadolinium in the tank solution. The procedure for calculating the amount of gadolinium in the HFIR poison injection system is as follows: (1) Calculate the usable volume in the system; (2) Measure the density of the solution; (3) Calculate the gadolinium concentration using the following equation: Gd(lb/ft{sup 3}) = measured density (g/mL) x 34.681 - 34.785; (4) Calculate the amount of gadolinium in the system using the following equation: Amount of Gd(lb) = Gd concentration (lb/ft{sup 3}) x usable volume (ft{sup 3}). The equation in step 3 is exact for a temperature of 5{sup o}C, and overestimates the gadolinium concentration at all higher temperatures. This guarantees that the calculation is conservative, in that the actual concentration will be at least as high as that calculated. If an additional safety factor is desired, it is recommended that an administrative control limit be set that is higher than the required minimum amount of gadolinium.

Taylor, Paul Allen [ORNL; Lee, Denise L [ORNL

2009-05-01T23:59:59.000Z

87

The use of PRA (Probabilistic Risk Assessment) in the management of safety issues at the High Flux Isotope Reactor  

SciTech Connect (OSTI)

The High Flux Isotope reactor (HFIR) is a high performance isotope production and research reactor which has been in operation at Oak Ridge National Laboratory (ORNL) since 1965. In late 1986 the reactor was shut down as a result of discovery of unexpected neutron embrittlement of the reactor vessel. In January of 1988, a level 1 Probabilistic Risk Assessment (PRA) (excluding external events) was published as part of the response to the many reviews that followed the shutdown and for use by ORNL to prioritize action items intended to upgrade the safety of the reactor. A conservative estimate of the core damage frequency initiated by internal events for HFIR was 3.11 {times} 10{sup {minus}4}. In June 1989 a draft external events initiated PRA was published. The dominant contributions from external events came from seismic, wind, and fires. The overall external event contribution to core damage frequency is about 138% of the internal event initiated contribution and is dominated by wind initiators. The PRA has provided a basis for the management of a wide range of safety and operation issues at the HFIR. 3 refs., 4 figs., 2 tabs.

Flanagan, G.F.

1990-01-01T23:59:59.000Z

88

Effect to the High Flux Isotope Reactor by the nearby heavy load drop  

SciTech Connect (OSTI)

In this calculation, GE-2000 cask of 25,000 lbs is assumed to drop from a height of 20-ft above the bottom of the High Flux Isotope Reactor (HFIR) pool slab with end velocity of 430 in/sec at the loading station. The consequences of the dynamic impact to the bottom slab of the pool and to the nearby HFIR reactor vessel are analyzed by applying ABAQUS computer code. The results show that both HFIR vessel structure and its supporting legs are subjected to elastic disturbances only and will not be damaged. The bottom slab of the pool will be damaged. The plastic strain that will cause failure to the concrete slab at the point of impact extends a distance approximately half of the slab thickness of 36 inches. The plastic strain of failure for concrete is assumed to be 0.45%. The velocity response spectrum at the concrete slab next to HFIR vessel as a result of the impact is also obtained. The maximum spectral velocity is approximately 10 in/sec. It is approximately equal to the maximum magnitude of the Oak Ridge velocity spectrum formulated recently with 0.26g peak ground acceleration and 5% damping. However, the peak ground acceleration that is associated with the impact generated response spectrum curve can be as much as 20g. The high frequency acceleration waves are generated in impact problems. It is concluded that the damage caused by heavy load drop at loading station is controlled by the slab damage. The damage of slab will not be severe enough to cause the leakage of pool water.

Chang, S.J. [Oak Ridge National Lab., TN (United States). Research Reactors Div.

1996-06-01T23:59:59.000Z

89

Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation - Vandellos II Reactor  

SciTech Connect (OSTI)

This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemical assay data and the use of the data to validate computer code predictions of isotopic composition for spent nuclear fuel, to establish the uncertainty and bias associated with code predictions. The experimental data analyzed in the current report were acquired from a high-burnup fuel program coordinated by Spanish organizations. The measurements included extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Six unique spent fuel samples from three uranium oxide fuel rods were analyzed. The fuel rods had a 4.5 wt % {sup 235}U initial enrichment and were irradiated in the Vandellos II pressurized water reactor operated in Spain. The burnups of the fuel samples range from 42 to 78 GWd/MTU. The measurements were used to validate the two-dimensional depletion sequence TRITON in the SCALE computer code system.

Ilas, Germina [ORNL; Gauld, Ian C [ORNL

2011-01-01T23:59:59.000Z

90

Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation  

SciTech Connect (OSTI)

The trapping of tritium in silicon carbide (SiC) injected from ceramic breeding materials was examined via tritium measurements using imaging plate (IP) techniques. Monolithic SiC in contact with ternary lithium oxide (lithium titanate and lithium aluminate) as a ceramic breeder was irradiated in the High Flux Isotope Reactor (HFIR) in Oak Ridge, Tennessee, USA. The distribution of photo-stimulated luminescence (PSL) of tritium in SiC was successfully obtained, which separated the contribution of 14C ß-rays to the PSL. The tritium incident from ceramic breeders was retained in the vicinity of the SiC surface even after irradiation at 1073 K over the duration of ~3000 h, while trapping of tritium was not observed in the bulk region. The PSL intensity near the SiC surface in contact with lithium titanate was higher than that obtained with lithium aluminate. The amount of the incident tritium and/or the formation of a Li2SiO3 phase on SiC due to the reaction with lithium aluminate under irradiation likely were responsible for this observation.

H. Katsui; Y. Katoh; A. Hasegawa; M. Shimada; Y. Hatano; T. Hinoki; S. Nogami; T. Tanaka; S. Nagata; T. Shikama

2013-11-01T23:59:59.000Z

91

On RELAP5-simulated High Flux Isotope Reactor reactivity transients: Code change and application  

SciTech Connect (OSTI)

This paper presents a new and innovative application for the RELAP5 code (hereafter referred to as the code''). The code has been used to simulate several transients associated with the (presently) draft version of the High-Flux Isotope Reactor (HFIR) updated safety analysis report (SAR). This paper investigates those thermal-hydraulic transients induced by nuclear reactivity changes. A major goal of the work was to use an existing RELAP5 HFIR model for consistency with other thermal-hydraulic transient analyses of the SAR. To achieve this goal, it was necessary to incorporate a new self-contained point kinetics solver into the code because of a deficiency in the point-kinetics reactivity model of the Mod 2.5 version of the code. The model was benchmarked against previously analyzed (known) transients. Given this new code, four event categories defined by the HFIR probabilistic risk assessment (PRA) were analyzed: (in ascending order of severity) a cold-loop pump start; run-away shim-regulating control cylinder and safety plate withdrawal; control cylinder ejection; and generation of an optimum void in the target region. All transients are discussed. Results of the bounding incredible event transient, the target region optimum void, are shown. Future plans for RELAP5 HFIR applications and recommendations for code improvements are also discussed.

Freels, J.D.

1993-01-01T23:59:59.000Z

92

On RELAP5-simulated High Flux Isotope Reactor reactivity transients: Code change and application  

SciTech Connect (OSTI)

This paper presents a new and innovative application for the RELAP5 code (hereafter referred to as ``the code``). The code has been used to simulate several transients associated with the (presently) draft version of the High-Flux Isotope Reactor (HFIR) updated safety analysis report (SAR). This paper investigates those thermal-hydraulic transients induced by nuclear reactivity changes. A major goal of the work was to use an existing RELAP5 HFIR model for consistency with other thermal-hydraulic transient analyses of the SAR. To achieve this goal, it was necessary to incorporate a new self-contained point kinetics solver into the code because of a deficiency in the point-kinetics reactivity model of the Mod 2.5 version of the code. The model was benchmarked against previously analyzed (known) transients. Given this new code, four event categories defined by the HFIR probabilistic risk assessment (PRA) were analyzed: (in ascending order of severity) a cold-loop pump start; run-away shim-regulating control cylinder and safety plate withdrawal; control cylinder ejection; and generation of an optimum void in the target region. All transients are discussed. Results of the bounding incredible event transient, the target region optimum void, are shown. Future plans for RELAP5 HFIR applications and recommendations for code improvements are also discussed.

Freels, J.D.

1993-07-01T23:59:59.000Z

93

Office of Analysis and Evaluation of Operational Data 1989 annual report, Power reactors  

SciTech Connect (OSTI)

The annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1989. The report is published in two separate parts. This document, NUREG-1272, Vol. 4, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC's Operations Center. This report also compiles the status of staff actions resulting from previous Incident Investigation Team (IIT) reports. 16 figs., 9 tabs.

None

1990-07-01T23:59:59.000Z

94

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

95

Validation of a Monte Carlo based depletion methodology via High Flux Isotope Reactor HEU post-irradiation examination measurements  

SciTech Connect (OSTI)

The purpose of this study is to validate a Monte Carlo based depletion methodology by comparing calculated post-irradiation uranium isotopic compositions in the fuel elements of the High Flux Isotope Reactor (HFIR) core to values measured using uranium mass-spectrographic analysis. Three fuel plates were analyzed: two from the outer fuel element (OFE) and one from the inner fuel element (IFE). Fuel plates O-111-8, O-350-1, and I-417-24 from outer fuel elements 5-O and 21-O and inner fuel element 49-I, respectively, were selected for examination. Fuel elements 5-O, 21-O, and 49-1 were loaded into HFIR during cycles 4, 16, and 35, respectively (mid to late 1960s). Approximately one year after each of these elements were irradiated, they were transferred to the High Radiation Level Examination Laboratory (HRLEL) where samples from these fuel plates were sectioned and examined via uranium mass-spectrographic analysis. The isotopic composition of each of the samples was used to determine the atomic percent of the uranium isotopes. A Monte Carlo based depletion computer program, ALEPH, which couples the MCNP and ORIGEN codes, was utilized to calculate the nuclide inventory at the end-of-cycle (EOC). A current ALEPH/MCNP input for HFIR fuel cycle 400 was modified to replicate cycles 4, 16, and 35. The control element withdrawal curves and flux trap loadings were revised, as well as the radial zone boundaries and nuclide concentrations in the MCNP model. The calculated EOC uranium isotopic compositions for the analyzed plates were found to be in good agreement with measurements, which reveals that ALEPH/MCNP can accurately calculate burn-up dependent uranium isotopic concentrations for the HFIR core. The spatial power distribution in HFIR changes significantly as irradiation time increases due to control element movement. Accurate calculation of the end-of-life uranium isotopic inventory is a good indicator that the power distribution variation as a function of space and time is accurately calculated, i.e. an integral check. Hence, the time dependent heat generation source terms needed for reactor core thermal hydraulic analysis, if derived from this methodology, have been shown to be accurate for highly enriched uranium (HEU) fuel.

Chandler, David [ORNL; Maldonado, G Ivan [ORNL; Primm, Trent [ORNL

2010-01-01T23:59:59.000Z

96

Isotope and Nuclear Chemistry Division annual report FY 1986, October 1985-September 1986  

SciTech Connect (OSTI)

This report describes progress in the major research and development programs carried out in FY 1986 by the Isotope and Nuclear Chemistry Division. The report includes articles on radiochemical diagnostics and weapons tests; weapons radiochemical diagnostics research and development; other unclassified weapons research; stable and radioactive isotope production and separation; chemical biology and nuclear medicine; element and isotope transport and fixation; actinide and transition metal chemistry; structural chemistry, spectroscopy, and applications; nuclear structure and reactions; irradiation facilities; advanced concepts and technology; and atmospheric chemistry.

Heiken, J.H. (ed.)

1987-06-01T23:59:59.000Z

97

Continuous production of tritium in an isotope-production reactor with a separate circulation system  

DOE Patents [OSTI]

A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium is allowed to flow through the reactor in separate loops in order to facilitate the production and removal of tritium.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

98

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

99

Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 1: Reactors  

SciTech Connect (OSTI)

This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC`s Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC`s mission in 1996.

NONE

1997-12-01T23:59:59.000Z

100

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

QUALITY ASSURANCE (QA) QUALITY ASSURANCE (QA) OBJECTIVE QA-1: The RRD QA program has been appropriately modified to reflect the CS modification and its reactor interface, and sufficient numbers of qualified QA personnel are provided to ensure services are adequate to support reactor operation. The QA functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. QA personnel exhibit awareness of the applicable requirements pertaining to reactor operation with the CS and the associated hazards. Through their actions, they have demonstrated a high-priority commitment to comply with these requirements. The level of knowledge of QA personnel related to reactor

Note: This page contains sample records for the topic "isotope reactor annual" 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

Report of the ANS Project Feasibility Workshop for a High Flux Isotope Reactor-Center for Neutron Research Facility  

SciTech Connect (OSTI)

The Advanced Neutron Source (ANS) Conceptual Design Report (CDR) and its subsequent updates provided definitive design, cost, and schedule estimates for the entire ANS Project. A recent update to this estimate of the total project cost for this facility was $2.9 billion, as specified in the FY 1996 Congressional data sheet, reflecting a line-item start in FY 1995. In December 1994, ANS management decided to prepare a significantly lower-cost option for a research facility based on ANS which could be considered during FY 1997 budget deliberations if DOE or Congressional planners wished. A cost reduction for ANS of about $1 billion was desired for this new option. It was decided that such a cost reduction could be achieved only by a significant reduction in the ANS research scope and by maximum, cost-effective use of existing High Flux Isotope Reactor (HFIR) and ORNL facilities to minimize the need for new buildings. However, two central missions of the ANS -- neutron scattering research and isotope production-were to be retained. The title selected for this new option was High Flux Isotope Reactor-Center for Neutron Research (HFIR-CNR) because of the project`s maximum use of existing HFIR facilities and retention of selected, central ANS missions. Assuming this shared-facility requirement would necessitate construction work near HFIR, it was specified that HFIR-CNR construction should not disrupt normal operation of HFIR. Additional objectives of the study were that it be highly credible and that any material that might be needed for US Department of Energy (DOE) and Congressional deliberations be produced quickly using minimum project resources. This requirement made it necessary to rely heavily on the ANS design, cost, and schedule baselines. A workshop methodology was selected because assessment of each cost and/or scope-reduction idea required nearly continuous communication among project personnel to ensure that all ramifications of propsed changes.

Peretz, F.J.; Booth, R.S. [comp.

1995-07-01T23:59:59.000Z

102

Progress in the Use of Isotopes: The Atomic Triad - Reactors, Radioisotopes and Radiation  

DOE R&D Accomplishments [OSTI]

Recent years have seen a substantial growth in the use of isotopes in medicine, agriculture, and industry: up to the minute information on the production and use of isotopes in the U.S. is presented. The application of radioisotopes to industrial processes and manufacturing operations has expanded more rapidly than any one except its most ardent advocates expected. New uses and new users are numerous. The adoption by industry of low level counting techniques which make possible the use of carbon-14 and tritium in the control of industrial processes and in certain exploratory and research problems is perhaps most promising of current developments. The latest information on savings to industry will be presented. The medical application of isotopes has continued to develop at a rapid pace. The current trend appears to be in the direction of improvements in technique and the substitution of more effective isotopes for those presently in use. Potential and actual benefits accruing from the use of isotopes in agriculture are reviewed. The various methods of production of radioisotopes are discussed. Not only the present methods but also interesting new possibilities are covered. Although isotopes are but one of the many peaceful uses of the atom, it is the first to pay its way. (auth)

Libby, W. F.

1958-08-04T23:59:59.000Z

103

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

Training & Qualification Training & Qualification OBJECTIVE TR-1: The selection, training and qualification programs associated with CS modifications, operation, hazards, and reactor operations with the hydrogen- moderated CS have been established, documented, and implemented. The selection process and applicable position-specific training for managers and staff, associated with CS modifications and hazards, and reactor operations with the hydrogen- moderated CS ensures competence commensurate with responsibilities (the training and qualification program encompasses the range of duties required to be performed). (CR - 1, CR - 2, CR - 6) Criteria * The Training program is established, documented, and functioning to support reactor operations with the CS modification. Functions, responsibilities, and

104

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

EMERGENCY PREPAREDNESS (EP) EMERGENCY PREPAREDNESS (EP) OBJECTIVE EP-1: A routine drill program and emergency operations drill program, including program records, have been established and implemented. (Core Requirement 11) Criteria * Reactor operation with the CS has been appropriately incorporated into the emergency preparedness hazards analysis and emergency response procedures. * The implemented routine and emergency operations drill program, including program records, have incorporated the CS SSCs and the CS's operation, hazards, and reactor interface. * Proficiency to appropriately respond to incidents and accidents associated with reactor operation has been demonstrated through the implemented routine and emergency operations drill program. Approach Record Review: Examine ORNL/RRD/INT-114, HFIR Emergency Planning Hazards

105

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

ENGINEERING (ENG) ENGINEERING (ENG) OBJECTIVE ENG-1: The engineering program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified engineering personnel are provided, and adequate facilities and equipment are available to ensure engineering services are adequate to support reactor and CS operations. The engineering functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. Engineering personnel exhibit awareness of the applicable requirements pertaining to reactor operation with the CS and with CS operations and hazards. Through their actions, they have demonstrated a high-priority commitment

106

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

OPERATIONS OPERATIONS OBJECTIVE OP-1: Operations staff and management exhibit awareness of applicable requirements pertaining to CS operation, hazards, and reactor operations with the hydrogen-moderated CS. Through their actions, they have demonstrated a high-priority commitment to comply with these requirements. The level of knowledge of reactor operations and CS system operations managers and staff related to CS operations, hazards, and reactor operations with the hydrogen-moderated CS is adequate based on interviews. Sufficient numbers of qualified reactor operations and CS system operations staff and management are available to conduct and support safe operations with the hydrogen-moderated CS. (CR - 1, CR - 4, CR - 6) Criteria * Minimum staffing requirements have been established for operations and support

107

Fuel pins with both target and fuel pellets in an isotope-production reactor  

DOE Patents [OSTI]

A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium target pellets are placed in close contact with fissile fuel pellets in order to increase the tritium production rate.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

108

Assemblies with both target and fuel pins in an isotope-production reactor  

DOE Patents [OSTI]

A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium target material is placed in pins adjacent to fuel pins in order to increase the tritium production rate.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

109

Vented target elements for use in an isotope-production reactor. [LMFBR  

DOE Patents [OSTI]

A method is described for producing tritium gas in a fast breeder reactor cooled with liquid metal. Lithium target material is placed in pins equipped with vents, and tritium gas is recovered from the coolant.

Cawley, W.E.; Omberg, R.P.

1982-08-19T23:59:59.000Z

110

Neutron Scattering Science User Office, neutronusers@ornl.gov or (865) 574-4600. Proposals for beam time at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR)  

E-Print Network [OSTI]

Neutron Scattering Science User Office, neutronusers@ornl.gov or (865) 574-4600. Proposals for beam Wildgruber, wildgrubercu@ornl.gov. VISION CallforProposals neutrons.ornl.gov Neutron Scattering Science - Oak time at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR) and Spallation Neutron Source

Pennycook, Steve

111

Isotope Program Facilities | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

include the High Flux Isotope Reactor at Oak Ridge National Laboratory and the Advanced Test Reactor at Idaho National Laboratory. The DOE Isotope Program also supports isotope...

112

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

INDUSTRIAL SAFETY AND HYGIENE (IS&H) INDUSTRIAL SAFETY AND HYGIENE (IS&H) OBJECTIVE IS&H-1: The RRD industrial safety and hygiene (IS&H) program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified IS&H staff and management are provided, and adequate IS&H facilities and equipment are available to ensure services are adequate to support reactor operation with the CS. The IS&H functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. IS&H staff and management exhibit awareness of applicable requirements pertaining to reactor operation with the CS and the associated hazards. Through their actions, they have demonstrated a high-

113

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

ENGINEERING ENGINEERING OBJECTIVE ES-1: The engineering program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified engineering staff and management are provided, and adequate facilities and equipment are available to ensure services are adequate to conduct and support reactor operations with the hydrogen-moderated CS. Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. (CR-1, CR-2, CR- 6) Criteria * The engineering organization and associated programs are established and functioning to support the RRD operations organization. Functions, responsibilities, and reporting relationships are clearly defined, understood, and

114

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

MAINTENANCE MAINTENANCE OBJECTIVE MT-1: The maintenance and test programs have been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified maintenance and testing staff and management are provided, and adequate facilities and equipment are available to ensure services are adequate to conduct and support reactor operations with the hydrogen-moderated CS. Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. (CR - 1, CR - 2, CR - 6) Criteria * The maintenance and test programs and organizations are established and functioning to support the RRD operations organization. Functions,

115

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

Emergency Preparedness Emergency Preparedness OBJECTIVE EP-1: The emergency preparedness program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified emergency preparedness staff and management are provided, and adequate facilities and equipment are available to ensure services are adequate to conduct and support reactor operations with the hydrogen-moderated CS. Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. (CR-1, CR-2, CR-6) Criteria * The emergency preparedness program and organization are established and functioning to support the RRD operations organization. Functions,

116

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

AUTHORIZATION BASIS MANAGEMENT AUTHORIZATION BASIS MANAGEMENT OBJECTIVE AB-1: The nuclear safety program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified nuclear safety staff and management are provided, and adequate facilities and equipment are available to ensure services are adequate to conduct and support operations with the CS modification. Functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. (CR-1, CR-2, CR-6) Criteria The nuclear safety program and organization are established and functioning to support reactor operations with the CS modification. Functions, responsibilities, and

117

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

CONFIGURATION MANAGEMENT (CM) CONFIGURATION MANAGEMENT (CM) OBJECTIVE CM-1: The facility systems and procedures, as affected by the facility modifications, are consistent with the description of the facility, procedures, and accident analysis included in the safety basis. (Core Requirement 9) Criteria * The CS and reactor systems affected by the CS and facility modifications are consistent with the description and accident analysis included in the DSA. * The reactor and CS procedures (including system drawings, operating procedures, annunciator response procedures, abnormal operating procedures, emergency operating procedures, surveillance test procedures, and other procedures affected by the CS modification) are consistent with the description and accident analysis included in the DSAs.

118

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

FIRE PROTECTION (FP) FIRE PROTECTION (FP) OBJECTIVE FP-1: The fire protection program has been appropriately modified to reflect the CS and its reactor interface, sufficient numbers of qualified fire protection personnel are available to support operations, and adequate facilities and equipment are available to ensure fire protection services are adequate for operations. The fire protection functions, assignments, responsibilities, and reporting relationships, including those between the line operating organization and the fire protection organization, are clearly defined, understood, and effectively implemented with line management responsibility for control of safety. The level of knowledge of fire protection personnel related to reactor operation with the CS and the associated hazards is adequate.

119

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

SciTech Connect (OSTI)

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

Gat, U.; Kasten, P.R.

1980-11-01T23:59:59.000Z

120

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

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


121

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G...

122

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of...

123

CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope...  

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

Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

124

CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope...  

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

Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR CRAD, Maintenance - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR...

125

CRAD, Management- Oak Ridge National Laboratory High Flux Isotope...  

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

Management- Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Management- Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

126

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

Configuration Management Configuration Management OBJECTIVE CM-1: The CS system and reactor systems affected by the CS modification and associated drawings are consistent with the description and accident analysis included in the DSA and a system to maintain control over their design and modification is established. (CR-9) Criteria * The design requirements have been formally established, documented, and maintained for the CS. * An adequate process has been implemented to ensure that documentation for systems critical to the safety of the facility during operation with the CS exists and is kept current as appropriate for their safety functions, and the documentation is available to the operators. * Cold Source and reactor interface equipment has been included in the

127

Medical isotope production: A new research initiative for the Annular Core Research Reactor  

SciTech Connect (OSTI)

An investigation has been performed to evaluate the capabilities of the Annular Core Research Reactor and its supporting Hot Cell Facility for the production of {sup 99}Mo and its separation from the fission product stream. Various target irradiation locations for a variety of core configurations were investigated, including the central cavity, fuel and reflector locations, and special target configurations outside the active fuel region. Monte Carlo techniques, in particular MCNP using ENDF B-V cross sections, were employed for the evaluation. The results indicate that the reactor, as currently configured, and with its supporting Hot Cell Facility, would be capable in meeting the current US demand if called upon. Modest modifications, such as increasing the capacity of the external heat exchangers, would permit significantly higher continuous power operation and even greater {sup 99}Mo production ensuring adequate capacity for future years.

Coats, R.L.; Parma, E.J.

1993-12-31T23:59:59.000Z

128

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

Management Management OBJECTIVE MG-1: Line management has established programs to ensure safe accomplishment of work. Personnel exhibit awareness of public and worker safety, health, and environmental protection requirements, and through their actions, they demonstrate a high-priority commitment to comply with these requirements. (Core Requirements 1 and 2) Criteria * Line management has integrated programs within its existing ISMS and implementing mechanisms that appropriately address the major changes implemented during this outage, notably the CS, in order to continue to assure safe accomplishment of work. * Senior management and RRD management exhibit awareness of the applicable requirements pertaining to reactor operation, with emphasis on the

129

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

RADIOLOGICAL PROTECTION (RP) RADIOLOGICAL PROTECTION (RP) OBJECTIVE RP-1: The RRD radiological protection program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified radiological protection personnel are provided, and adequate radiological protection facilities and equipment are available to ensure that services are adequate to conduct and support HFIR operation. The radiological protection functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. Radiological protection personnel exhibit awareness of the applicable radiological protection requirements pertaining to HFIR operation and the associated hazards.

130

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

Management and Organization Management and Organization OBJECTIVE MG-1: Line management has integrated within its existing ISM system and implementing mechanisms, programs that appropriately address CS operations, hazards, and reactor interface to assure safe accomplishment of work. Safety management programs of particular interest include the following (CR - 1): * maintenance and testing (addressed by MT-1) * conduct of operations (addressed by OP-1and -5) * training/qualification (addressed by TR-1) * nuclear safety (addressed by AB-2) * emergency management (addressed by EP-1and -2) * configuration management (addressed by ES-3) * fire protection (addressed by ESH-4) * industrial safety and hygiene (addressed by ESH-2) * quality assurance (addressed by ESH-6)

131

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

132

Three-dimensional discrete ordinates radiation transport calculations of neutron fluxes for beginning-of-cycle at several pressure vessel surveillance positions in the high flux isotope reactor  

SciTech Connect (OSTI)

The objective of this research was to determine improved thermal, epithermal, and fast fluxes and several responses at mechanical test surveillance location keys 2, 4, 5, and 7 of the pressure vessel of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) for the beginning of the fuel cycle. The purpose of the research was to provide essential flux data in support of radiation embrittlement studies of the pressure vessel shell and beam tubes at some of the important locations.

Pace, J.V. III; Slater, C.O.; Smith, M.S.

1993-11-01T23:59:59.000Z

133

ORNL - Restart of the High Flux Isotope Reactor 2-07  

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

NUCLEAR SAFETY (NS) NUCLEAR SAFETY (NS) OBJECTIVE NS-1: The nuclear safety program has been appropriately modified to reflect the CS modification and its reactor interface, sufficient numbers of qualified nuclear safety personnel are provided, and adequate facilities and equipment are available to ensure that nuclear safety services are adequate to support HFIR operation with the CS. The nuclear safety functions, assignments, responsibilities, and reporting relationships are clearly defined, understood, and effectively implemented with line management control of safety. The level of knowledge of nuclear safety personnel with respect to operation of HFIR with the CS is adequate. (Core Requirements 1, 2, 4, and 6) Criteria * The nuclear safety program is established and functioning to support HFIR

134

Occupational radiation exposure at commercial nuclear power reactors and other facilities 1996: Twenty-ninth annual report. Volume 18  

SciTech Connect (OSTI)

This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission`s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1996 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high level waste currently licensed, only six categories will be considered in this report. Annual reports for 1996 were received from a total of 300 NRC licensees, of which 109 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted by the 300 licensees indicated that 138,310 individuals were monitored, 75,139 of whom received a measurable dose. The collective dose incurred by these individuals was 21,755 person-cSv (person-rem){sup 2} which represents a 13% decrease from the 1995 value. The number of workers receiving a measurable dose also decreased, resulting in the average measurable dose of 0.29 cSv (rem) for 1996. The average measurable dose is defined to be the total collective dose (TEDE) divided by the number of workers receiving a measurable dose. These figures have been adjusted to account for transient reactor workers. Analyses of transient worker data indicate that 22,348 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1996, the average measurable dose calculated from reported was 0.24 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.29 cSv (rem).

Thomas, M.L. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Hagemeyer, D. [Science Applications International Corp., Oak Ridge, TN (United States)

1998-02-01T23:59:59.000Z

135

Assumptions and Criteria for Performing a Feasability Study of the Conversion of the High Flux Isotope Reactor Core to Use Low-Enriched Uranium Fuel  

SciTech Connect (OSTI)

A computational study will be initiated during fiscal year 2006 to examine the feasibility of converting the High Flux Isotope Reactor from highly enriched uranium fuel to low-enriched uranium. The study will be limited to steady-state, nominal operation, reactor physics and thermal-hydraulic analyses of a uranium-molybdenum alloy that would be substituted for the current fuel powder--U{sub 3}O{sub 8} mixed with aluminum. The purposes of this document are to (1) define the scope of studies to be conducted, (2) define the methodologies to be used to conduct the studies, (3) define the assumptions that serve as input to the methodologies, (4) provide an efficient means for communication with the Department of Energy and American research reactor operators, and (5) expedite review and commentary by those parties.

Primm, R.T., III; Ellis, R.J.; Gehin, J.C.; Moses, D.L.; Binder, J.L.; Xoubi, N. (U. of Cincinnati)

2006-02-01T23:59:59.000Z

136

unstable isotope  

Science Journals Connector (OSTI)

unstable isotope, radioisotope ? unstabiles Isotop n, nichtstabiles Isotop, radioaktives Isotop, Radioisotop

2014-08-01T23:59:59.000Z

137

Isolation of metals from liquid wastes: Reactive scavenging in turbulent thermal reactors. 1998 annual progress report  

SciTech Connect (OSTI)

'The objective of this project is to develop the fundamental science base necessary to assess the utility of high-temperature processes to volatilize metals in DOE metal-bearing liquid wastes, so that they can be reactively scavenged by sorbents. The problem is addressed through a collaborative research program involving a team of five senior scientists and their respective laboratories, at four institutions. Specific goals are to: (1) Understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals in the DOE liquid waste inventory (e.g., Cs and Sr), using a laminar-flow reactor for which extraction of kinetic data is not complicated by turbulence; (2) Develop models to predict both trajectories of individual droplets in turbulent high-temperature reactors, and rates of metal evolution from droplets, and compare model predictions with experimental data from a pilot-scale turbulent thermal reactor; (3) Connect the reaction kinetic models with the droplet trajectory/mass evolution models, in order to predict and optimize metal scavenging processes in turbulent-flow reactors, and to test these combined models against data taken from a turbulent high temperature reactor. This report summarizes work at a point midway through the first year of a 3-year project. At the University of Arizona (UA), two tasks are underway. The first task is concerned with attempting to understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals. The second task is concerned with applying Kerstein''s One Dimensional Turbulence model to prediction of droplet trajectories in turbulent flow.'

Wendt, J.O.L. [Univ. of Arizona, Tucson, AZ (US); Linak, W.P. [Environmental Protection Agency, Research Triangle Park, NC (US); Kerstein, A.R. [Sandia National Labs., Livermore, CA (US); Pearlstein, A.J.; Scheeline, A. [Univ. of Illinois, Urbana, IL (US)

1998-06-01T23:59:59.000Z

138

Development of CFD models to support LEU Conversion of ORNL s High Flux Isotope Reactor  

SciTech Connect (OSTI)

The US Department of Energy s National Nuclear Security Administration (NNSA) is participating in the Global Threat Reduction Initiative to reduce and protect vulnerable nuclear and radiological materials located at civilian sites worldwide. As an integral part of one of NNSA s subprograms, Reduced Enrichment for Research and Test Reactors, HFIR is being converted from the present HEU core to a low enriched uranium (LEU) core with less than 20% of U-235 by weight. Because of HFIR s importance for condensed matter research in the United States, its conversion to a high-density, U-Mo-based, LEU fuel should not significantly impact its existing performance. Furthermore, cost and availability considerations suggest making only minimal changes to the overall HFIR facility. Therefore, the goal of this conversion program is only to substitute LEU for the fuel type in the existing fuel plate design, retaining the same number of fuel plates, with the same physical dimensions, as in the current HFIR HEU core. Because LEU-specific testing and experiments will be limited, COMSOL Multiphysics was chosen to provide the needed simulation capability to validate against the HEU design data and previous calculations, and predict the performance of the proposed LEU fuel for design and safety analyses. To achieve it, advanced COMSOL-based multiphysics simulations, including computational fluid dynamics (CFD), are being developed to capture the turbulent flows and associated heat transfer in fine detail and to improve predictive accuracy [2].

Khane, Vaibhav B [ORNL] [ORNL; Jain, Prashant K [ORNL] [ORNL; Freels, James D [ORNL] [ORNL

2012-01-01T23:59:59.000Z

139

Annual  

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

19 19 th Annual Triple "E" Seminar Presented by U.S. Department of Energy National Energy Technology Laboratory and Spectroscopy Society of Pittsburgh Thursday, January 20, 2011 8:00 a.m. Registration & Breakfast 8:30 a.m. Opening Remarks/Welcome Michael Nowak, Senior Management & Technical Advisor National Energy Technology Laboratory 8:35 a.m. Overview of Energy Issues Michael Nowak, Senior Management & Technical Advisor National Energy Technology Laboratory 8:45 a.m. Introduction of Presenters McMahan Gray National Energy Technology Laboratory 8:50 a.m. Jane Konrad, Pgh Regional Center for Science Teachers "Green - What Does it Mean" 9:45 a.m. Break 10:00 a.m. John Varine, Spectroscopy Society of Pittsburgh

140

Monthly/Annual Energy Review - nuclear section  

Reports and Publications (EIA)

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

2015-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Office for Analysis and Evaluation of Operational Data 1992 annual report: Power reactors. Volume 7, No. 1  

SciTech Connect (OSTI)

The annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1992. The report is published in two separate parts. NUREG-1272, Vol. 7, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance, measures. The report also includes the principal findings and issues identified in AEOD studies over the past year, and summarizes information from such sources as licensee event report% diagnostic evaluations, and reports to the NRC`s Operations Center. The reports contain a discussion of the Incident Investigation Team program and summarize the Incident Investigation Team and Augmented Inspection Team reports for that group of licensees. NUREG-1272, Vol. 7, No. 2, covers nonreactors and presents a review of the events and concerns during 1992 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Each volume contains a list of the AEOD reports issued for 1984--1992.

none,

1993-07-01T23:59:59.000Z

142

2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2012-02-01T23:59:59.000Z

143

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

SciTech Connect (OSTI)

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

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

2002-11-01T23:59:59.000Z

144

Nuclear Research Reactors  

Science Journals Connector (OSTI)

... their countries for the advent of nuclear power. A few countries had built large research reactors for the production of isotopes and to study the behaviour of nuclear fuel, but ... production of isotopes and to study the behaviour of nuclear fuel, but the small training reactor had not been developed. Since then, research ...

T. E. ALLIBONE

1963-07-20T23:59:59.000Z

145

Estimates of Radioxenon Released from Southern Hemisphere Medical isotope Production Facilities Using Measured Air Concentrations and Atmospheric Transport Modeling  

SciTech Connect (OSTI)

Abstract The International Monitoring System (IMS) of the Comprehensive-Nuclear-Test-Ban-Treaty monitors the atmosphere for radioactive xenon leaking from underground nuclear explosions. Emissions from medical isotope production represent a challenging background signal when determining whether measured radioxenon in the atmosphere is associated with a nuclear explosion prohibited by the treaty. The Australian Nuclear Science and Technology Organisation (ANSTO) operates a reactor and medical isotope production facility in Lucas Heights, Australia. This study uses two years of release data from the ANSTO medical isotope production facility and Xe-133 data from three IMS sampling locations to estimate the annual releases of Xe-133 from medical isotope production facilities in Argentina, South Africa, and Indonesia. Atmospheric dilution factors derived from a global atmospheric transport model were used in an optimization scheme to estimate annual release values by facility. The annual releases of about 6.8×1014 Bq from the ANSTO medical isotope production facility are in good agreement with the sampled concentrations at these three IMS sampling locations. Annual release estimates for the facility in South Africa vary from 1.2×1016 to 2.5×1016 Bq and estimates for the facility in Indonesia vary from 6.1×1013 to 3.6×1014 Bq. Although some releases from the facility in Argentina may reach these IMS sampling locations, the solution to the objective function is insensitive to the magnitude of those releases.

Eslinger, Paul W.; Friese, Judah I.; Lowrey, Justin D.; McIntyre, Justin I.; Miley, Harry S.; Schrom, Brian T.

2014-04-06T23:59:59.000Z

146

Enforcement Letter, International Isotopes Idaho Inc - August...  

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

Isotopes Idaho, Inc. related to the Relocation of an Irradiated Pellet at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental...

147

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

SciTech Connect (OSTI)

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

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

1992-05-01T23:59:59.000Z

148

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

149

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

150

TABLE 1. Nuclear Reactor, State, Type, Net Capacity, Generation...  

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

TABLE 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor " "PlantReactor Name","Generator ID","State","Type","2009 Summer Capacity"," 2010 Annual...

151

2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2012–October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Noncompliance issues • Discussion of the facility’s environmental impacts. During the 2013 permit year, approximately 238 million gallons of wastewater was discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

Mike Lewis

2014-02-01T23:59:59.000Z

152

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

153

E-Print Network 3.0 - almaty wwr-k reactor Sample Search Results  

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

High Flux Isotope Reactor Center for Nanophase Materials Sciences... International Thermonuclear Experimental Reactor Center for Computational Sciences National Security 0 0 61 1...

154

Annual Reports  

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

Occupational Radiation Exposure Occupational Radiation Exposure Home Welcome What's New Register Dose History Request Data File Submittal REMS Data Selection HSS Logo Annual Reports User Survey on the Annual Report Please take the time to complete a survey on the Annual Report. Your input is important to us! The 2012 Annual Report View or print the annual report in PDF format The 2011 Annual Report View or print the annual report in PDF format The 2010 Annual Report View or print the annual report in PDF format The 2009 Annual Report View or print the annual report in PDF format The 2008 Annual Report View or print the annual report in PDF format The 2007 Annual Report View or print the annual report in PDF format The 2006 Annual Report View or print the annual report in PDF format The 2005 Annual Report

155

Annual Reports  

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

Annual Reports science-innovationassetsimagesicon-science.jpg Annual Reports x Strategic Plan Annual Report - 2011 (pdf) Advancing Science for National Security See more Los...

156

Isotope Evidence for Ozone Formation on Surfaces  

Science Journals Connector (OSTI)

Remarkably, the gas-phase recombination or association reaction of ozone has an unusually large (?10%) isotope effect and shows almost equal enrichments of the ozone molecules containing two different oxygen isotopes. ... For a better understanding of the pressure and temperature dependence of ozone isotopic composition in oxygen discharges, we developed a relatively simple isotope kinetic model that accounts for the processes of (i) heterogeneous ozone formation at the reactor walls, (ii) isotope exchange of oxygen atoms with O2 molecules, and (iii) ozone formation in the gas phase. ...

Christof Janssen; Béla Tuzson

2010-05-06T23:59:59.000Z

157

Online Catalog of Isotope Products from DOE's National Isotope Development Center  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

The National Isotope Development Center (NIDC) interfaces with the User Community and manages the coordination of isotope production across the facilities and business operations involved in the production, sale, and distribution of isotopes. A virtual center, the NIDC is funded by the Isotope Development and Production for Research and Applications (IDPRA) subprogram of the Office of Nuclear Physics in the U.S. Department of Energy Office of Science. The Isotope subprogram supports the production, and the development of production techniques of radioactive and stable isotopes that are in short supply for research and applications. Isotopes are high-priority commodities of strategic importance for the Nation and are essential for energy, medical, and national security applications and for basic research; a goal of the program is to make critical isotopes more readily available to meet domestic U.S. needs. This subprogram is steward of the Isotope Production Facility (IPF) at Los Alamos National Laboratory (LANL), the Brookhaven Linear Isotope Producer (BLIP) facility at BNL, and hot cell facilities for processing isotopes at ORNL, BNL and LANL. The subprogram also coordinates and supports isotope production at a suite of university, national laboratory, and commercial accelerator and reactor facilities throughout the Nation to promote a reliable supply of domestic isotopes. The National Isotope Development Center (NIDC) at ORNL coordinates isotope production across the many facilities and manages the business operations of the sale and distribution of isotopes.

158

Solid tags for identifying failed reactor components  

DOE Patents [OSTI]

A solid tag material which generates stable detectable, identifiable, and measurable isotopic gases on exposure to a neutron flux to be placed in a nuclear reactor component, particularly a fuel element, in order to identify the reactor component in event of its failure. Several tag materials consisting of salts which generate a multiplicity of gaseous isotopes in predetermined ratios are used to identify different reactor components.

Bunch, Wilbur L. (Richland, WA); Schenter, Robert E. (Richland, WA)

1987-01-01T23:59:59.000Z

159

Isotope Analysis  

Science Journals Connector (OSTI)

Naturally occurring oxygen includes three stable isotopes,16O,17O, and18O, with the relative abundances of 99.763%, 0.0375%, and 0.1995%, respectively. Isotopic analysis does not consider the absolute abundances ...

Tandong Yao; Wusheng Yu; Huabiao Zhao…

2014-08-01T23:59:59.000Z

160

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope  

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

CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Nuclear Safety Program in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

Note: This page contains sample records for the topic "isotope reactor annual" 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

CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope  

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

Reactor Contractor ORR Reactor Contractor ORR CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR February 2007 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Safety Basis - Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR More Documents & Publications CRAD, Engineering - Oak Ridge National Laboratory High Flux Isotope Reactor

162

Canadian university research reactors  

SciTech Connect (OSTI)

In Canada there are seven university research reactors: one medium-power (2-MW) swimming pool reactor at McMaster University and six low-power (20-kW) SLOWPOKE reactors at Dalhousie University, Ecole Polytechnique, the Royal Military College, the University of Toronto, the University of Saskatchewan, and the University of Alberta. This paper describes primarily the McMaster Nuclear Reactor (MNR), which operates on a wider scale than the SLOWPOKE reactors. The MNR has over a hundred user groups and is a very broad-based tool. The main applications are in the following areas: (1) neutron activation analysis (NAA); (2) isotope production; (3) neutron beam research; (4) nuclear engineering; (5) neutron radiography; and (6) nuclear physics.

Ernst, P.C.; Collins, M.F.

1989-11-01T23:59:59.000Z

163

Carbon Isotopes  

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

Atmospheric Trace Gases » Carbon Isotopes Atmospheric Trace Gases » Carbon Isotopes Carbon Isotopes Gateway Pages to Isotopes Data Modern Records of Carbon and Oxygen Isotopes in Atmospheric Carbon Dioxide and Carbon-13 in Methane 800,000 Deuterium Record and Shorter Records of Various Isotopic Species from Ice Cores Carbon-13 13C in CO Measurements from Niwot Ridge, Colorado and Montana de Oro, California (Tyler) 13C in CO2 NOAA/CMDL Flask Network (White and Vaughn) CSIRO GASLAB Flask Network (Allison, Francey, and Krummel) CSIRO in situ measurements at Cape Grim, Tasmania (Francey and Allison) Scripps Institution of Oceanography (Keeling et al.) 13C in CH4 NOAA/CMDL Flask Network (Miller and White) Northern & Southern Hemisphere Sites (Quay and Stutsman) Northern & Southern Hemisphere Sites (Stevens)

164

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

165

GENERATION OF RADIOXENON ISOTOPES  

SciTech Connect (OSTI)

With the continued population of the International Monitoring System (IMS) network and the certification of radioxenon laboratory systems it has become necessary to calibrate and test these systems using as many of the radioxenon isotopes as possible. Several very promising techniques have been explored recently that allow for convenient production of Xe-133, Xe-131m, the short-lived isotope Xe-135, and even the difficult to obtain Xe-133m. IMS national and international laboratories have traditionally obtained Xe-133 from medical isotope suppliers. The activity of these medical dose samples is extremely high (~ 740 MBq) and requires very careful fume hood work to dilute down to appropriate levels (~ 10 Bq). By waiting for 10 or more half-lives it is possible to reduce the handling regimen considerably, while also obtaining a strong Xe-131m signature due to its longer half-life (11.9 days). The short-lived isotope Xe-135 (9.14 hrs) and the longer lived parent nuclide Xe-133m (2.2 day half-life) are never present in these samples. To obtain these isotopes another source or technique is required. This paper will discuss the two techniques developed and implemented at Pacific Northwest National Lab (PNNL) and show the results obtained from each technique. The first is an in-house method that allows for on demand production of two of these isotopes, Xe-133 and Xe-135, using HEU and a modest flux neutron source. The second method uses a research reactor at the Pullman campus of Washington State University to produce Xe-133, Xe-133m and Xe-135.

McIntyre, Justin I.; Pratt, Sharon L.; Bowyer, Ted W.; Cooper, Matthew W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, Charles W.; Miley, Harry S.; Ripplinger, Mike D.

2008-09-23T23:59:59.000Z

166

MODULAR PEBBLE BED REACTOR PROJECT UNIVERSITY RESEARCH CONSORTIUM  

E-Print Network [OSTI]

Annual Report Page ii MODULAR PEBBLE BED REACTOR ABSTRACT This project is developing a fundamental. Publication of an archival journal article covering this work is being prepared. · Detailed gas reactor Abstract

167

Strategic Isotope Production | ornl.gov  

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

Strategic Isotope Strategic Isotope Production SHARE Strategic Isotope Production Typical capsules used in the transport of 252Cf source material inside heavily shielded shipping casks. ORNL's unique facilities at the High Flux Isotope Reactor (HFIR), Radiochemical Engineering Development Center (REDC), Irradiated Fuels Examination Laboratory (IFEL), and Irradiated Materials Examination Testing facility (IMET) are routinely used in the production, purification, packaging, and shipping of a number of isotopes of national importance, including: 75Se, 63Ni, 238Pu, 252Cf, and others. The intense neutron flux of the HFIR (2.0 x 1015 neutrons/cm²·s) permits the rapid formation of such isotopes. These highly irradiated materials are then processed and packaged for shipping using the facilities at the REDC, IFEL, and IMET.

168

Final Report, NEAC Subcommittee for Isotope Research & Production Planning  

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

Final Report, NEAC Subcommittee for Isotope Research & Production Final Report, NEAC Subcommittee for Isotope Research & Production Planning Final Report, NEAC Subcommittee for Isotope Research & Production Planning Isotopes, including both radioactive and stable isotopes, make important contributions to research, medicine, and industry in the United States and throughout the world. For nearly fifty years, the Department of Energy (DOE) has actively promoted the use of isotopes by funding (a) production of isotopes at a number of national laboratories with unique nuclear reactors or particle accelerators, (b) nuclear medicine research at the laboratories and in academia, (c) research into industrial applications of isotopes, and (d) research into isotope production and processing methods. The radio- pharmaceutical and radiopharmacy industries have their origin in

169

The Uranium Institute 24th Annual Symposium  

E-Print Network [OSTI]

the waste U-238 into Pu-239 for burning. By this means 100 times as much energy can be obtained from it to extract the uranium, enriching the natural uranium in the fissile isotope U-235, burning the U-235 than the uranium fuel it burns, leading to a breeder reactor. In addition, if the reactor is a fast

Laughlin, Robert B.

170

Development and validation of a real-time SAFT-UT system for the inspection of light water reactor components: Annual report, October 1984-September 1985  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering data base to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1984 through September 1985.

Doctor, S.R.; Hall, T.E.; Reid, L.D.; Crawford, S.L.; Littlefield, R.J.; Gilbert, R.W.

1987-06-01T23:59:59.000Z

171

Apparatus for isotopic alteration of mercury vapor  

DOE Patents [OSTI]

An apparatus for enriching the isotopic Hg content of mercury is provided. The apparatus includes a reactor, a low pressure electric discharge lamp containing a fill including mercury and an inert gas. A filter is arranged concentrically around the lamp. In a preferred embodiment, constant mercury pressure is maintained in the filter by means of a water-cooled tube that depends from it, the tube having a drop of mercury disposed in it. The reactor is arranged around the filter, whereby radiation from said lamp passes through the filter and into said reactor. The lamp, the filter and the reactor are formed of a material which is transparent to ultraviolet light.

Grossman, Mark W. (Belmont, MA); George, William A. (Gloucester, MA); Marcucci, Rudolph V. (Danvers, MA)

1988-01-01T23:59:59.000Z

172

Laser Isotope Enrichment for Medical and Industrial Applications  

SciTech Connect (OSTI)

Laser Isotope Enrichment for Medical and Industrial Applications by Jeff Eerkens (University of Missouri), Jay Kunze (Idaho State University), and Leonard Bond (Idaho National Laboratory) The principal isotope enrichment business in the world is the enrichment of uranium for commercial power reactor fuels. However, there are a number of other needs for separated isotopes. Some examples are: 1) Pure isotopic targets for irradiation to produce medical radioisotopes. 2) Pure isotopes for semiconductors. 3) Low neutron capture isotopes for various uses in nuclear reactors. 4) Isotopes for industrial tracer/identification applications. Examples of interest to medicine are targets to produce radio-isotopes such as S-33, Mo-98, Mo-100, W-186, Sn-112; while for MRI diagnostics, the non-radioactive Xe-129 isotope is wanted. For super-semiconductor applications some desired industrial isotopes are Si-28, Ga-69, Ge-74, Se-80, Te-128, etc. An example of a low cross section isotope for use in reactors is Zn-68 as a corrosion inhibitor material in nuclear reactor primary systems. Neutron activation of Ar isotopes is of interest in industrial tracer and diagnostic applications (e.g. oil-logging). . In the past few years there has been a sufficient supply of isotopes in common demand, because of huge Russian stockpiles produced with old electromagnetic and centrifuge separators previously used for uranium enrichment. Production of specialized isotopes in the USA has been largely accomplished using old ”calutrons” (electromagnetic separators) at Oak Ridge National Laboratory. These methods of separating isotopes are rather energy inefficient. Use of lasers for isotope separation has been considered for many decades. None of the proposed methods have attained sufficient proof of principal status to be economically attractive to pursue commercially. Some of the authors have succeeded in separating sulfur isotopes using a rather new and different method, known as condensation repression. In this scheme a gas, of the selected isotopes for enrichment, is irradiated with a laser at a particular wavelength that would excite only one of the isotopes. The entire gas is subject to low temperatures sufficient to cause condensation on a cold surface. Those molecules in the gas that the laser excited are not as likely to condense as are the unexcited molecules. Hence the gas drawn out of the system will be enriched in the isotope that was excited by the laser. We have evaluated the relative energy required in this process if applied on a commercial scale. We estimate the energy required for laser isotope enrichment is about 20% of that required in centrifuge separations, and 2% of that required by use of "calutrons".

Leonard Bond

2006-07-01T23:59:59.000Z

173

from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Facility April 13, 2012 Isotope Production Facility produces cancer-fighting actinium 2:32 Isotope cancer treatment...

174

One Step Biomass Gas Reforming-Shift Separation Membrane Reactor - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

9 9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Michael Roberts (Primary Contact), Razima Souleimanova Gas Technology Institute (GTI) 1700 South Mount prospect Rd, Des Plaines, IL 60018 Phone: (847) 768-0518 Email: roberts@gastechnology.org DOE Managers HQ: Sara Dillich Phone: (202) 586-7925 Email: Sara.Dillich@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FG36-07GO17001 Subcontractors: * National Energy Technology Laboratory (NETL), Pittsburgh, PA * Schott North America, Duryea, PA * ATI Wah Chang, Albany, OR Project Start Date: February 1, 2007 Project End Date: June 30, 2013

175

Development of Hydrogen Selective Membranes/Modules as Reactors/Separators for Distributed Hydrogen Production - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

3 3 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Paul KT Liu Media and Process Technology Inc. (M&P) 1155 William Pitt Way Pittsburgh, PA 15238 Phone: (412) 826-3711 Email: pliu@mediaandprocess.com DOE Managers HQ: Sara Dillich Phone: (202) 586-7925 Email: Sara.Dillich@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FG36-05GO15092 Subcontractor: University of Southern California Project Start Date: July 1, 2005 Projected End Date: December 31, 2012 Fiscal Year (FY) 2012 Objectives The water-gas shift (WGS) reaction becomes less efficient when high CO conversion is required, such as for distributed hydrogen production applications. Our project

176

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

177

Reactor physics project progress report no. 2  

E-Print Network [OSTI]

This is the second annual report in an experimental and theoretical program to develop and apply single and few element heterogeneous methods for the determination of reactor lattice parameters. During the period covered ...

Driscoll, Michael J.

1969-01-01T23:59:59.000Z

178

CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope  

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

Oak Ridge National Laboratory High Flux Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a DOE independent oversight assessment of the Oak Ridge National Laboratory programs for oversight of its contractors. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, DOE Oversight - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications CRAD, Nuclear Safety - Oak Ridge National Laboratory High Flux Isotope Reactor

179

Delayed neutron energy spectrum measurements of actinide waste isotopes  

E-Print Network [OSTI]

was irradiated using the Texas A&M Nuclear Science Center Reactor (NSCR). Three proton recoil detectors, operating individually, in conjunction with MCNP calculated response functions, were used to measure the delayed neutron energy spectra of each isotope...

Comfort, Christopher M.

2012-06-07T23:59:59.000Z

180

Isotope studies in photosynthesis  

Science Journals Connector (OSTI)

Isotope studies in photosynthesis ... Examines the use of isotopic oxygen, hydrogen, carbon, and phosphorus in the study of photosynthesis. ...

J. A. Bassham; A. A. Benson; Melvin Calvin

1953-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

GUM Analysis for TIMS and SIMS Isotopic Ratios in Graphite  

SciTech Connect (OSTI)

This report describes GUM calculations for TIMS and SIMS isotopic ratio measurements of reactor graphite samples. These isotopic ratios are used to estimate reactor burn-up, and currently consist of various ratios of U, Pu, and Boron impurities in the graphite samples. The GUM calculation is a propagation of error methodology that assigns uncertainties (in the form of standard error and confidence bound) to the final estimates.

Heasler, Patrick G.; Gerlach, David C.; Cliff, John B.; Petersen, Steven L.

2007-04-01T23:59:59.000Z

182

Selected Isotopes for Optimized Fuel Assembly Tags  

SciTech Connect (OSTI)

In support of our ongoing signatures project we present information on 3 isotopes selected for possible application in optimized tags that could be applied to fuel assemblies to provide an objective measure of burnup. 1. Important factors for an optimized tag are compatibility with the reactor environment (corrosion resistance), low radioactive activation, at least 2 stable isotopes, moderate neutron absorption cross-section, which gives significant changes in isotope ratios over typical fuel assembly irradiation levels, and ease of measurement in the SIMS machine 2. From the candidate isotopes presented in the 3rd FY 08 Quarterly Report, the most promising appear to be Titanium, Hafnium, and Platinum. The other candidate isotopes (Iron, Tungsten, exhibited inadequate corrosion resistance and/or had neutron capture cross-sections either too high or too low for the burnup range of interest.

Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J.; Hurley, David E.

2008-10-01T23:59:59.000Z

183

2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2009 through October 31, 2010. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Discussion of the facility’s environmental impacts During the 2010 permit year, approximately 164 million gallons of wastewater were discharged to the Cold Waste Pond. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

mike lewis

2011-02-01T23:59:59.000Z

184

Department of Energy's Isotope Development and Production for Research and Applications Program's Fiscal Year 2009 Balance Sheet Audit, OAS-FS-12-08  

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

Department of Energy's Isotope Department of Energy's Isotope Development and Production for Research and Applications Program's Fiscal Year 2009 Balance Sheet OAS-FS-12-08 March 2012 ISOTOPE DEVELOPMENT AND PRODUCTION FOR RESEARCH AND APPLICATIONS PROGRAM Fiscal Year 2009 Annual Report and Balance Sheet September 30, 2009 i UNITED STATES DEPARTMENT OF ENERGY ISOTOPE DEVELOPMENT AND PRODUCTION FOR RESEARCH AND APPLICATIONS PROGRAM Fiscal Year 2009 Annual Report and Balance Sheet Table of Contents Page Management's Discussion and Analysis 1 Isotope Program Overview 2 Isotope Program Funding 4 Isotope Program Performance 5 Financial Performance 6 Management Challenges and Significant Issues 7 Balance Sheet Limitations 7

185

E-Print Network 3.0 - argonne high flux reactor Sample Search...  

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

for: argonne high flux reactor Page: << < 1 2 3 4 5 > >> 1 Thirteenth National School on Neutron and X-ray Scattering Summary: Neutron Source and High Flux Isotope Reactor...

186

High Flux Isotope Reactor | ORNL Neutron Sciences  

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

How to Work with HFIR How to Work with HFIR HFIR Workflow Please contact the experiment interface or coordinator for additional information and guidance. There are many...

187

Enforcement Letter, International Isotopes Idaho Inc - August 20, 1999 |  

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

International Isotopes Idaho Inc - August 20, International Isotopes Idaho Inc - August 20, 1999 Enforcement Letter, International Isotopes Idaho Inc - August 20, 1999 August, 20, 1999 Issued to International Isotopes Idaho, Inc. related to the Relocation of an Irradiated Pellet at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory This letter refers to the Department of Energy's (DOE) evaluation of the facts and circumstances concerning the relocation of an irradiated [isotope] pellet from within a hot cell to an adjoining, outside, charging port service area. This incident occurred on January 6, 1999, at the Idaho National Engineering and Environmental Laboratory's Test Reactor Area Hot Cell Facility (TRA-632). Building TRA-632 is utilized by International

188

Enforcement Letter, International Isotopes Idaho Inc - August 20, 1999 |  

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

International Isotopes Idaho Inc - August 20, International Isotopes Idaho Inc - August 20, 1999 Enforcement Letter, International Isotopes Idaho Inc - August 20, 1999 August, 20, 1999 Issued to International Isotopes Idaho, Inc. related to the Relocation of an Irradiated Pellet at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory This letter refers to the Department of Energy's (DOE) evaluation of the facts and circumstances concerning the relocation of an irradiated [isotope] pellet from within a hot cell to an adjoining, outside, charging port service area. This incident occurred on January 6, 1999, at the Idaho National Engineering and Environmental Laboratory's Test Reactor Area Hot Cell Facility (TRA-632). Building TRA-632 is utilized by International

189

lead-isotope dating  

Science Journals Connector (OSTI)

lead-isotope dating, lead-lead dating, lead-isotope age measurement, lead-lead age measurement ? Blei-Isotopen(-Alters)bestimmung, f, Blei-Isotopen-Datierung

2014-08-01T23:59:59.000Z

190

isotopic ratio | EMSL  

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

isotopic ratio isotopic ratio Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

191

Water Resources Center Annual Technical Report  

E-Print Network [OSTI]

Water Resources Center Annual Technical Report FY 1999 Introduction This year has seen changes, UC Santa Barbara Assessment of Intraseasonal Variations in California Rainfall and the Role on Carbon Isotope Signatures in Food Webs Supporting Salmonids in Northern California Rivers, Mary Power, UC

192

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

193

Isotope Science and Production  

E-Print Network [OSTI]

of Energy National Isotope Program http://www.nuclear.energy.gov/isotopes/nelsotopes2a.html Isotopes for Environmental Science Isotopes produced at Los Alamos National Laboratory are used as environmental tracers change and its effects. Los Alamos National Laboratory can produce Si-32 needed for oceanographic tracing

194

Stable isotope studies  

SciTech Connect (OSTI)

The research has been in four general areas: (1) correlation of isotope effects with molecular forces and molecular structures, (2) correlation of zero-point energy and its isotope effects with molecular structure and molecular forces, (3) vapor pressure isotope effects, and (4) fractionation of stable isotopes. 73 refs, 38 figs, 29 tabs.

Ishida, T.

1992-01-01T23:59:59.000Z

195

ANNUAL WINTER SCHOOLANNUAL WINTER SCHOOL Petersburg Nuclear Physics Institute  

E-Print Network [OSTI]

ANNUAL WINTER SCHOOLANNUAL WINTER SCHOOL Petersburg Nuclear Physics Institute National Research February ­ 1 March, 2014 Petersburg Nuclear Physics Institute (PNPI) conducts the XLVIII Annual Winter Physics · Theoretical Physics School · School on Nuclear Reactor Physics · Accelerator Physics School

Titov, Anatoly

196

CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope  

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

Fire Protection - Oak Ridge National Laboratory High Flux Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor February 2006 A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a February 2006 Commencement of Operations assessment of the Fire Protection program at the Idaho National Laboratory, Idaho Accelerated Retrieval Project Phase II. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Fire Protection - Oak Ridge National Laboratory High Flux Isotope Reactor More Documents & Publications

197

Annual Reports | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Annual Reports | National Nuclear Security Administration Annual Reports | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Annual Reports Home > Our Mission > Powering the Nuclear Navy > Annual Reports Annual Reports NNSA's Naval Reactors is committed to providing information about its operations. Environmental Monitoring Report NT-12-1 - May 2012 - ENVIRONMENTAL MONITORING AND DISPOSAL OF

198

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

199

Annual Report  

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

09 09 THROUGH 09/30/2010 The following Annual Freedom of Information Act report covers the Period 10/01/2009, through 09/30/2010, as required by 5 U.S.C. 552. I. BASIC INFORMATION REGARDING REPORT 1. Kevin T. Hagerty, Director Office of Information Resources, MA-90 U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 202-586-5955 Alexander Morris, FOIA Officer Sheila Jeter, FOIA/Privacy Act Specialist FOIA Office, MA-90 Office of Information Resources U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 202-586-5955 2. An electronic copy of the Freedom of Information Act (FOIA) report can be obtained at http://management.energy.gov/documents/annual_reports.htm. The report can then be accessed by clicking FOIA Annual Reports.

200

Annual Training Plan Template  

Broader source: Energy.gov [DOE]

The Annual Training Plan Template is used by an organization's training POC to draft their organization's annual training plan.

Note: This page contains sample records for the topic "isotope reactor annual" 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

Isotopically pumped isotopic CF4 laser  

Science Journals Connector (OSTI)

Single-mode optical pumping of CF4 to generate 16-µm frequencies has been extended to include the isotopic species 12CF4,...

Eckhardt, Roger; Telle, John; Haynes, Larry

1982-01-01T23:59:59.000Z

202

Cancer-fighting treatment gets boost from Isotope Production Facility  

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

Cancer-fighting treatment gets boost from Isotope Production Cancer-fighting treatment gets boost from Isotope Production Facility Cancer-fighting treatment gets boost from Isotope Production Facility New capability expands existing program, creates treatment product in quantity. April 13, 2012 Medical Isotope Work Moves Cancer Treatment Agent Forward Medical Isotope Work Moves Cancer Treatment Agent Forward - Los Alamos scientist Meiring Nortier holds a thorium foil test target for the proof-of-concept production experiments. Research indicates that it will be possible to match current annual, worldwide production of Ac-225 in just two to five days of operations using the accelerator at Los Alamos and analogous facilities at Brookhaven. Alpha particles are energetic enough to destroy cancer cells but are unlikely to move beyond a tightly controlled target region and destroy

203

Preliminary Notice of Violation, International Isotopes Idaho, Inc.- EA-2000-04  

Broader source: Energy.gov [DOE]

Issued to International Isotopes Idaho, Inc., related to Work Planning and Control Deficiencies associated with Replacement of Exhaust Ventilation Filters at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory, May 19, 2000

204

NERSC 2001 Annual Report  

E-Print Network [OSTI]

issue in designing fusion reactors, namely, the realisticof building an efficient fusion reactor is best served byissue in designing a fusion reactor is the realistic assess-

Hules editor, John

2001-01-01T23:59:59.000Z

205

Isotope Geothermometry | Open Energy Information  

Open Energy Info (EERE)

Isotope Geothermometry Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotope Geothermometry Details Activities (0) Areas (0) Regions (0)...

206

THE ISOTOPES OF AMERICIUM  

E-Print Network [OSTI]

spectrographic analysis of the americium samples. It is a48 J'---_I" THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.Elements THE ISOTOPES OF AMERICIUM K. Street, Jr. , A.

Street, K.; Ghiroso, A.; Seaborg, G.T.

2008-01-01T23:59:59.000Z

207

Expert Panel: Forecast Future Demand for Medical Isotopes | Department of  

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

Expert Panel: Forecast Future Demand for Medical Isotopes Expert Panel: Forecast Future Demand for Medical Isotopes Expert Panel: Forecast Future Demand for Medical Isotopes The Expert Panel has concluded that the Department of Energy and National Institutes of Health must develop the capability to produce a diverse supply of radioisotopes for medical use in quantities sufficient to support research and clinical activities. Such a capability would prevent shortages of isotopes, reduce American dependence on foreign radionuclide sources and stimulate biomedical research. The expert panel recommends that the U.S. government build this capability around either a reactor, an accelerator or a combination of both technologies as long as isotopes for clinical and research applications can be supplied reliably, with diversity in adequate

208

Electrochemical Isotope Effect and Lithium Isotope Separation  

Science Journals Connector (OSTI)

In a series of papers Kavner et al. (2005, 2008)(2, 3) derive an equation predicting isotopic fractionation due to an electrochemical isotope effect (?EIE), defined by the ratio of electron transfer rates (k?/k) for isotopically substituted species (prime for heavy isotopologues): where v, ?G, kB, T, m, ?eq, QP/QR, z, e, and ? denote collision frequency, activation free energy, Boltzmann’s constant, temperature, mass in motion, equilibrium fractionation factor, partition function ratio of abundant isotopologues of product (P) and reactant (R), number of electrons, charge of electron, and Marcus reorganization energy, respectively. ... fractional isotope evolution of Zn isotopes during an electroplating process which stepwise removes most of the Zn from the aq. ...

Jay R. Black; Grant Umeda; Bruce Dunn; William F. McDonough; Abby Kavner

2009-07-06T23:59:59.000Z

209

Perchlorate Isotope Forensics  

Science Journals Connector (OSTI)

In this study, comprehensive stable isotope analyses (37Cl/35Cl and 18O/17O/16O) of perchlorate from known synthetic and natural sources reveal systematic differences in isotopic characteristics that are related to the formation mechanisms. ... ?37Cl and ?18O are measures of mass-dependent fractionation of Cl and O isotopes by normal physical, chemical, or biological processes. ...

John Karl Böhlke; Neil C. Sturchio; Baohua Gu; Juske Horita; Gilbert M. Brown; W. Andrew Jackson; Jacimaria Batista; Paul B. Hatzinger

2005-11-04T23:59:59.000Z

210

Isotope Effect in Adhesion  

Science Journals Connector (OSTI)

Isotope Effect in Adhesion ... We report the first observation of an isotope effect in adhesion. ... The results are presented in Figure 3. Clearly, the isotope effect is very significant, substantiating the proposed H-bonding interactions between the PDMS and Si?OH(D) surfaces. ...

Gun Young Choi; Abraham Ulman; Yitzhak Shnidman; Walter Zurawsky; Cathy Fleischer

2000-05-25T23:59:59.000Z

211

ANNUAL ENERGY  

Gasoline and Diesel Fuel Update (EIA)

(93) (93) ANNUAL ENERGY OUTLOOK 1993 With Projections to 2010 EIk Energy Information Administration January 1993 For Further Information ... The Annual Energy Outlook (AEO) is prepared by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting, under the direction of Mary J. Hutzler (202/586-2222). General questions concerning energy demand or energy markets may be addressed to Mark E. Rodekohr (202/586-1130), Director of the Energy Demand and Integration Division. General questions regarding energy supply and conversion activities may be addressed to Mary J. Hutzler (202/586-2222), Acting Director of the Energy Supply and Conversion Division. Detailed questions may be addressed to the following EIA analysts: Framing the 1993 Energy Outlook ............. Susan H. Shaw (202/586-4838)

212

Annual Report  

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

1 1 2011 Annual Report to the Oak Ridge Community Annual Report to the Oak Ridge Community DOE/ORO/2399 Progress Cleanup P Progress Cleanup P 2 This report was produced by URS | CH2M Oak Ridge LLC, DOE's Environmental Management contractor for the Oak Ridge Reservation. About the Cover After recontouring and revegetation, the P1 Pond at East Tennessee Technology Park is flourishing. The contaminated pond was drained, recontoured, and restocked with fish that would not disturb the pond sediment. 1 Message from the Acting Manager Department of Energy Oak Ridge Office To the Oak Ridge Community: Fiscal Year (FY) 2011 marked many accomplishments in Oak Ridge. Our Environmental Management (EM) program completed a majority of its American Recovery and Reinvestment Act (ARRA)-funded projects,

213

Annual Energy  

Gasoline and Diesel Fuel Update (EIA)

11) | April 2011 11) | April 2011 with Projections to 2035 Annual Energy Outlook 2011 For further information . . . The Annual Energy Outlook 2011 was prepared by the U.S. Energy Information Administration (EIA), under the direction of John J. Conti (john.conti@eia.gov, 202-586-2222), Assistant Administrator of Energy Analysis; Paul D. Holtberg (paul.holtberg@eia.gov, 202/586-1284), Co-Acting Director, Office of Integrated and International Energy Analysis, and Team Leader, Analysis Integration Team; Joseph A. Beamon (joseph.beamon@eia.gov, 202/586-2025), Director, Office of Electricity, Coal, Nuclear, and Renewables Analysis; A. Michael Schaal (michael.schaal@eia.gov, 202/586-5590), Director, Office of Petroleum, Gas, and Biofuel Analysis;

214

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"...

215

ARM - Measurement - Isotope ratio  

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

govMeasurementsIsotope ratio govMeasurementsIsotope ratio ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Isotope ratio Ratio of stable isotope concentrations. Categories Atmospheric Carbon, Atmospheric State Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. ARM Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Field Campaign Instruments FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes Datastreams FLASK : Flask Samplers for Carbon Cycle Gases and Isotopes

216

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

217

LNG Annual Report - 2005 | Department of Energy  

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

5 LNG Annual Report - 2005 LNG Annual Report - 2005 LNG Annual Report - 2005 More Documents & Publications LNG Annual Report - 2004 LNG Annual Report - 2006 LNG Annual Report -...

218

LNG Annual Report - 2006 | Department of Energy  

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

6 LNG Annual Report - 2006 LNG Annual Report - 2006 LNG Annual Report - 2006 More Documents & Publications LNG Annual Report - 2007 LNG Annual Report - 2005 LNG Annual Report -...

219

LNG Annual Report - 2004 | Department of Energy  

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

4 LNG Annual Report - 2004 LNG Annual Report - 2004 LNG Annual Report - 2004 More Documents & Publications LNG Annual Report - 2005 LNG Annual Report - 2007 LNG Annual Report -...

220

Nuclear reactor characteristics and operational history  

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

Nuclear > U.S. reactor operation status tables Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: November 2012 See also: Table 2. Ownership Data, Table 3. Characteristics and Operational History Table 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor PDF XLS Plant/Reactor Name Generator ID State Type 2009 Summer Capacity Net MW(e)1 2010 Annual Generation Net MWh2 Capacity Factor Percent3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas Nuclear One 2 AR PWR 993 8,415,588 97 Beaver Valley 1 PA PWR 892 7,119,413 91 Beaver Valley 2 PA PWR 885 7,874,151 102 Braidwood Generation Station 1 IL PWR 1,178 9,196,689 89

Note: This page contains sample records for the topic "isotope reactor annual" 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

2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT RESEARCH REPORT2010ANNUAL RESEARCH REPORT2010ANNUAL RESEARCH REPORT  

E-Print Network [OSTI]

2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT RESEARCH REPORT2010ANNUAL RESEARCH REPORT2010ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT 2010 ANNUAL RESEARCH REPORT RESEARCH REPORT2010ANNUAL RESEARCH REPORT2010ANNUAL RESEARCH REPORT

Jawitz, James W.

222

Isotope Program Transportation | Department of Energy  

Office of Environmental Management (EM)

Isotope Program Transportation Isotope Program Transportation Isotope Program Transportation More Documents & Publications Nuclear Fuel Storage and Transportation Planning Project...

223

Intra-event trends in stable isotopes: Exploring mid-latitude precipitation using a vertically-pointing micro rain radar  

Science Journals Connector (OSTI)

Annual, monthly and daily analyses of stable isotopes in precipitation are commonly made worldwide, yet only a few studies have explored the variations occurring on short timescales within individual precipitation events, particularly at mid-...

Catherine L. Muller; Andy Baker; Ian J. Fairchild; Chris Kidd; Ian Boomer

224

Annual Reports | Department of Energy  

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

Documents Documents » Annual Reports Annual Reports Note: Some of the following documents are in PDF and will require Adobe Reader for viewing. Freedom of Information Act Annual Reports Annual Report for 2012 Annual Report for 2011 Annual Report for 2010 Annual Report for 2009 Annual Report for 2008 (pdf) Annual Report for 2007 (pdf) Annual Report for 2006 (pdf) Annual Report for 2005 (pdf) Annual Report for 2004 (pdf) Annual Report for 2003 (pdf) Annual Report for 2002 (pdf) (Revised 11/03/03) Annual Report for 2001 (pdf) Annual Report for 2000 (pdf) Annual Report for 1999 (pdf) Annual Report for 1998 (pdf) Annual Report for 1997 (pdf) Annual Report for 1996 (pdf) Annual Report for 1995 (pdf) Annual Report for 1994 (pdf) Chief FOIA Officers Reports Aviation Management Green Leases

225

Forward model calculations for determining isotopic compositions of materials used in a radiological dispersal device  

E-Print Network [OSTI]

for the multiple radial-region pin cell was 7 times that of the 2D pin cell. For this reason, the 2D pin cell was used to benchmark the isotopics with data from other reactors. The reactors from which the methodology was benchmarked were Calvert Cliffs Unit #1...

Burk, David Edward

2005-08-29T23:59:59.000Z

226

Determination of americium and curium by isotope dilution  

SciTech Connect (OSTI)

The authors propose a method for the determination of americium and curium in solutions of spent fuels from water cooled and moderated reactors that is based on isotope dilution with Am 241 and Cm 244 combined with extraction chromatography of americium and curium and alpha spectroscopy of the labels.

Yablochkin, A.V.; Krapivin, M.I.; Fedotov, S.N.; Yudina, V.G.; Yakobson, A.A.

1987-11-01T23:59:59.000Z

227

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...

228

Mass-Independent Isotope Effects  

Science Journals Connector (OSTI)

Scientific interests: ESR and NMR spectroscopies, molecular magnets, mechanisms of chemical and biochemical reactions, spin physics and chemistry, isotopes and isotope effects in chemistry and biochemistry. ... Another mass-independent isotope effect was detected in 1983 as a deviation of isotopic distribution in reaction products from that which would be expected from the mass-dependent isotope effect. ... Later, Nomura et al.(92) have found isotopic 233U anomaly in the U4+–U6+ exchange reaction; they noted that the isotope effect was correlated with isotope shifts in the atomic spectra of uranium isotopes. ...

Anatoly L. Buchachenko

2013-01-09T23:59:59.000Z

229

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

230

ARM - Annual Reports  

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

Annual Reports Program Fact Sheets Campaign Backgrounders Education and Outreach Posters Brochures Research Highlights Summaries Annual Reports For proper viewing, the ARM...

231

Annual Growth Bands in Hymenaea courbaril  

SciTech Connect (OSTI)

One significant source of annual temperature and precipitation data arises from the regular annual secondary growth rings of trees. Several tropical tree species are observed to form regular growth bands that may or may not form annually. Such growth was observed in one stem disk of the tropical legume Hymenaea courbaril near the area of David, Panama. In comparison to annual reference {Delta}{sup 14}C values from wood and air, the {Delta}{sup 14}C values from the secondary growth rings formed by H. courbaril were determined to be annual in nature in this one stem disk specimen. During this study, H. courbaril was also observed to translocate recently produced photosynthate into older growth rings as sapwood is converted to heartwood. This process alters the overall {Delta}{sup 14}C values of these transitional growth rings as cellulose with a higher {Delta}{sup 14}C content is translocated into growth rings with a relatively lower {Delta}{sup 14}C content. Once the annual nature of these growth rings is established, further stable isotope analyses on H. courbaril material in other studies may help to complete gaps in the understanding of short and of long term global climate patterns.

Westbrook, J A; Guilderson, T P; Colinvaux, P A

2004-02-09T23:59:59.000Z

232

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method is described for yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus. 2 figures.

Maya, J.

1991-06-18T23:59:59.000Z

233

Hybrid isotope separation scheme  

DOE Patents [OSTI]

A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which a scavenger, radiating the gas with a wave length or frequency characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photochemical reaction between the scavenger, and collecting the specific isotope-containing chemical by using a recombination surface or by a scooping apparatus.

Maya, Jakob (Brookline, MA)

1991-01-01T23:59:59.000Z

234

Stable isotope enrichment  

SciTech Connect (OSTI)

Brian Egle is working to increase the nation's capacity to produce stable isotopes for use including medicine, industry and national security.

Egle, Brian

2014-07-14T23:59:59.000Z

235

EMSL - isotopic ratio  

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

isotopic-ratio en Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. http:www.emsl.pnl.govemslwebpublicationsmagnesium-behavior-and-structural-def...

236

Safe new reactor for radionuclide production  

SciTech Connect (OSTI)

In late 1995, DOE is schedule to announce a new tritium production unit. Near the end of the last NPR (New Production Reactors) program, work was directed towards eliminating risks in current designs and reducing effects of accidents. In the Heavy Water Reactor Program at Savannah River, the coolant was changed from heavy to light water. An alternative, passively safe concept uses a heavy-water-filled, zircaloy reactor calandria near the bottom of a swimming pool; the calandria is supported on a light-water-coolant inlet plenum and has upflow through assemblies in the calandria tubes. The reactor concept eliminates or reduces significantly most design basis and severe accidents that plague other deigns. The proven, current SRS tritium cycle remains intact; production within the US of medical isotopes such as Mo-99 would also be possible.

Gray, P.L.

1995-02-15T23:59:59.000Z

237

LNG Annual Report - 2009 | Department of Energy  

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

9 LNG Annual Report - 2009 LNG Annual Report - 2009 LNG Annual Report - 2009 More Documents & Publications LNG Annual Report - 2008...

238

Stable Carbon Isotope Ratios of Phenolic Compounds in Secondary Particulate Organic Matter Formed by Photooxidation of Toluene  

E-Print Network [OSTI]

Compound-specific stable carbon isotope ratios for phenolic compounds in secondary particulate organic matter (POM) formed by photooxidation of toluene were studied. Secondary POM generated by photooxidation of toluene using a continuous-flow reactor and an 8 cubic meter indoor smog chamber was collected, and then extracted with acetonitrile. Eight phenolic compounds were identified in the extracts by a gas chromatograph coupled with a mass spectrometer, and their compound-specific stable carbon isotope ratios were determined by a gas chromatograph coupled with a combustion furnace followed by an isotope ratio mass spectrometer. The majority of the products, including methylnitrophenols and methylnitrocatechols, were isotopically depleted by 5 to 6 permil compared to the initial isotope ratio for toluene, whereas the isotope ratio for 4_nitrophenol remained the same as the initial isotope ratio for toluene. Based on the reaction mechanisms postulated in literature, stable carbon isotope ratios of these produc...

Irei, Satoshi; Huang, Lin; Auld, Janeen; Collin, Fabrice; Hastie, Donald

2014-01-01T23:59:59.000Z

239

Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors  

SciTech Connect (OSTI)

Burnable poisons are used in nuclear reactors to produce a more level distribution of power in the reactor core and to reduce to necessity for a large control system. An ideal burnable poison would burn at the same rate as the fuel. In this study, separation of neutron-absorbing isotopes was investigated in order to eliminate isotopes that remain as absorbers at the end of fuel life, thus reducing useful fuel life. The isotopes Gd-157, Dy-164, and Er-167 were found to have desirable properties. These isotopes were separated from naturally occurring elements by means of plasma separation to evaluate feasibility and cost. It was found that pure Gd-157 could save approximately $6 million at the end of four years. However, the cost of separation, using the existing facility, made separation cost- ineffective. Using a magnet with three times the field strength is expected to reduce the cost by a factor of ten, making isotopically separated burnable poisons a favorable method of increasing fuel life in commercial reactors, in particular Generation-IV reactors. The project also investigated various burnable poison configurations, and studied incorporation of metallic burnable poisons into fuel cladding.

M. L. Grossbeck J-P.A. Renier Tim Bigelow

2003-09-30T23:59:59.000Z

240

NERSC Annual Report 2004  

E-Print Network [OSTI]

injected into a tokamak fusion reactor. See page 40 for moreinto a toka- mak fusion reactor. The isosurfaces show theQPS), an experi- mental fusion reactor that is expected to

Hules, John; Bashor, Jon; Yarris, Lynn; McCullough, Julie; Preuss, Paul; Bethel, Wes

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

NERSC Annual Report 2005  

E-Print Network [OSTI]

issue in the design of fusion reactors, a long-anticipatedfrozen fuel pellets in fusion reactors What happens when youfirst production-scale fusion reactor, ITER will help answer

Hules Ed., John

2006-01-01T23:59:59.000Z

242

High-purity, isotopically enriched bulk silicon  

SciTech Connect (OSTI)

The synthesis and characterization of dislocation-free, undoped, single crystals of Si enriched in all 3 stable isotopes is reported: {sup 28}Si (99.92%), {sup 29}Si (91.37%), and {sup 30}Si (89.8%). A silane-based process compatible with the relatively small amounts of isotopically enriched precursors that are practically available was used. The silane is decomposed to silicon on a graphite starter rod heated to 700-750 C in a recirculating flow reactor. A typical run produces 35 gm of polycrystalline Si at a growth rates of 5 {micro}m/min and conversion efficiency >95%. Single crystals are grown by the floating zone method and characterized by electrical and optical measurements. Concentrations of shallow dopants (P and B) are as low as mid-10{sup 13} cm{sup -3}. Concentrations of C and O lie below 10{sup 16} and 10{sup 15} cm{sup -3}, respectively.

Ager III, J.W.; Beeman, J.W.; Hansen, W.L.; Haller, E.E.; Sharp, I.D.; Liao, C.; Yang, A.; Thewalt, M.L.W.; Riemann, H.

2004-11-17T23:59:59.000Z

243

Celebrating The Isotope  

Science Journals Connector (OSTI)

Celebrating The Isotope ... The notion of isotopes and the rest of Soddy’s lifetime body of work on radioactivity, the group displacement laws, the social responsibility of scientists, and the environment have had a profound effect on science and society. ...

GEORGE B. KAUFFMAN

2013-12-02T23:59:59.000Z

244

Isotope - based Quantum Information  

E-Print Network [OSTI]

This paper is brief review of three aspects of the isotope - based quantum information: computation, teleportation and cryptography. Our results demonstrate not only that entanglement exists in elementary excitation of isotope - mixed solids but also it can be used for quantum information processing.

Vladimir G. Plekhanov

2009-09-04T23:59:59.000Z

245

PRI Annual Report 2003  

E-Print Network [OSTI]

The Annual Report highlights the activities and people that make PRI a multidisciplinary research center.

Maynard-Moody, Steven

2004-10-29T23:59:59.000Z

246

Annual Energy Outlook-List of Acronyms  

Gasoline and Diesel Fuel Update (EIA)

ABWR ABWR Advanced Boiling Water Reactor AD Associated-dissolved (natural gas) AECL Atomic Energy Canada Limited AEO2003 Annual Energy Outlook 2003 AEO2004 Annual Energy Outlook 2004 ALAPCO Association of Local Air Pollution Control Officials AMT Alternative Minimum Tax ANWR Arctic National Wildlife Refuge AP1000 Advanced Pressurized Water Reactor ARI Advanced Resources International AT-PZEV Advanced technology partial zero-emission vehicle BLS Bureau of Labor Statistics BNFL British Nuclear Fuels Limited plc Btu British thermal unit CAAA90 Clean Air Act Amendments of 1990 CAFE Corporate average fuel economy CARB California Air Resources Board CBO Congressional Budget Office CCAP Climate Change Action Plan CGES Centre for Global Energy Studies CHP Combined heat and power CO 2 Carbon dioxide DB Deutsche Bank A.G. DES Department of Environmental Services (New Hampshire)

247

Development and validation of a real-time SAFT-UT (synthetic aperture focusing technique for ultrasonic testing) system for the inspection of light water reactor components: Annual report, October 1985-September 1986  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering data base to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1985 through September 1986. 45 figs., 8 tabs.

Doctor, S.R.; Hall, T.E.; Reid, L.D.; Mart, G.A.

1987-07-01T23:59:59.000Z

248

Comparison of isotopic transmutation modelling codes  

E-Print Network [OSTI]

. STAMATELATOS, "Fission Product Data for Thermal Reactors Part 2: Users Manual for EPRI-CINDER Code and Data, " LA-6746-MS, Los Alamos National Laboratory (Dec. 1976). 5. H. BATEMAN, ~RGE~di gH gf ~t gym~id 6. M. J. BEIL, "ORIGEN ? The ORNL Isotope... Generation and Depletion Code, " ORNL-4628, Oak Ridge National Laboratory (May, 1973). 7. O. W. HERMANN and R. M. WESTFALL, "ORIGEN-S Scale System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product. Buildup and Decay...

Beard, Carl Allen

1990-01-01T23:59:59.000Z

249

Current Annualized Request  

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

Organization Organization FY 2012 FY 2013 FY 2014 Current Annualized Request CR $ % National Security Weapons Activities* 7,214,834 7,557,342 7,868,409 +311,067 +4.1% Defense Nuclear Nonproliferation 2,300,950 2,409,930 2,140,142 -160,808 -7.0% Naval Reactors 1,080,000 1,086,610 1,246,134 +166,134 +15.4% Office of the Administrator 410,000 412,509 397,784 -12,216 -3.0% Total, National Nuclear Security Administration 11,005,784 11,466,391 11,652,469 +304,177 +2.8% Energy and Environment Energy Efficiency and Renewable Energy 1,780,548 1,820,713 2,775,700 +995,152 +55.9% Electricity Delivery and Energy Reliability 136,178 139,954 169,015 +32,837 +24.1% Fossil Energy 554,806 714,033 637,975 +83,169 +15.0% Nuclear Energy 853,816 863,996 735,460 -118,356 -13.9% Race to the Top for Energy Efficiency and Grid Modernization

250

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

251

Reduce, reuse and recycle: A green solution to Canada's medical isotope shortage  

Science Journals Connector (OSTI)

Abstract Due to the unforeseen maintenance issues at the National Research Universal (NRU) reactor at Chalk River and coincidental shutdowns of other international reactors, a global shortage of medical isotopes (in particular technetium-99m, Tc-99m) occurred in 2009. The operation of these research reactors is expensive, their age creates concerns about their continued maintenance and the process results in a large amount of long-lived nuclear waste, whose storage cost has been subsidized by governments. While the NRU has since revived its operations, it is scheduled to cease isotope production in 2016. The Canadian government created the Non-reactor based medical Isotope Supply Program (NISP) to promote research into alternative methods for producing medical isotopes. The NRC was a member of a collaboration looking into the use of electron linear accelerators (LINAC) to produce molybdenum-99 (Mo-99), the parent isotope of Tc-99m. This paper outlines NRC’s involvement in every step of this process, from the production, chemical processing, recycling and preliminary animal studies to demonstrate the equivalence of LINAC Tc-99m with the existing supply. This process stems from reusing an old idea, reduces the nuclear waste to virtually zero and recycles material to create a green solution to Canada's medical isotope shortage.

R. Galea; C. Ross; R.G. Wells

2014-01-01T23:59:59.000Z

252

LNG Annual Report - 2011 | Department of Energy  

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

1 LNG Annual Report - 2011 LNG Annual Report - 2011 (Revised 3152012) LNG Annual Report 2011 More Documents & Publications LNG Annual Report - 2012 LNG Annual Report - 2013 LNG...

253

LNG Annual Report - 2007 | Department of Energy  

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

7 LNG Annual Report - 2007 LNG Annual Report - 2007 (Revised 10102008) LNG Annual Report - 2007 More Documents & Publications LNG Annual Report - 2008 LNG Annual Report - 2006...

254

LNG Annual Report - 2010 | Department of Energy  

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

10 LNG Annual Report - 2010 LNG Annual Report - 2010 LNG Annual Report - 2010 More Documents & Publications LNG Annual Report - 2009 LNG Annual Report - 2008...

255

LNG Annual Report - 2012 | Department of Energy  

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

2 LNG Annual Report - 2012 LNG Annual Report - 2012 (Revised 3212013) LNG Annual Report - 2012 More Documents & Publications LNG Annual Report - 2013 LNG Annual Report - 2011 LNG...

256

Draft 2014 Annual Plan | Department of Energy  

Office of Environmental Management (EM)

Draft 2014 Annual Plan Draft 2014 Annual Plan Section 999: Draft 2014 Annual Plan Section 999 - Draft 2014 Annual Plan More Documents & Publications 2011 Annual Plan 2013...

257

Uranium Marketing Annual Report - Energy Information Administration  

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

Uranium Marketing Annual Report Uranium Marketing Annual Report With Data for 2012 | Release Date: May 16, 2013 | Next Release Date: May 2014 | full report Previous uranium marketing annual reports Year: 2011 2010 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1998 1997 1996 1995 1994 1993 1992 Go Uranium purchases and prices Owners and operators of U.S. civilian nuclear power reactors ("civilian owner/operators" or "COOs") purchased a total of 58 million pounds U3O8e (equivalent1) of deliveries from U.S. suppliers and foreign suppliers during 2012, at a weighted-average price of $54.99 per pound U3O8e. The 2012 total of 58 million pounds U3O8e increased 5 percent compared with the 2011 total of 55 million pounds U3O8e. The 2012 weighted-average price of

258

Axi-symmetrical flow reactor for [sup 196]Hg photochemical enrichment  

DOE Patents [OSTI]

The present invention is directed to an improved photochemical reactor useful for the isotopic enrichment of a predetermined isotope of mercury, especially, [sup 196]Hg. Specifically, two axi-symmetrical flow reactors were constructed according to the teachings of the present invention. These reactors improve the mixing of the reactants during the photochemical enrichment process, affording higher yields of the desired [sup 196]Hg product. Measurements of the variation of yield (Y) and enrichment factor (E) along the flow axis of these reactors indicates very substantial improvement in process uniformity compared to previously used photochemical reactor systems. In one preferred embodiment of the present invention, the photoreactor system was built such that the reactor chamber was removable from the system without disturbing the location of either the photochemical lamp or the filter employed therewith. 10 figures.

Grossman, M.W.

1991-04-30T23:59:59.000Z

259

lead-isotope age  

Science Journals Connector (OSTI)

lead-isotope age, lead-lead age [An age in years calculated from the ratio of lead-207 to lead-206, a by-product of the uranium-thorium-lead age method] ? Blei-Isotopen-Alter n

2014-08-01T23:59:59.000Z

260

ISOTOPES IN WATER  

Science Journals Connector (OSTI)

The study of isotopic prosies ha two different though related basic aims: an understanding of the way in which the water cycle in linked to alterations in climate, and how the carbon cycle has responded to the...

W. GEORGE DARLING; ADRIAN H. BATH…

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

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

262

Nuclear isotope thermometry  

Science Journals Connector (OSTI)

We discuss different aspects which might influence temperatures deduced from experimental isotopic yields in the multifragmentation process. It is shown that fluctuations due to the finite size of the system and distortions due to the decay of hot primary fragments conspire to blur the temperature determination in multifragmentation reactions. These facts suggest that caloric curves obtained through isotope thermometers, which were taken as evidence for a first-order phase transition in nuclear matter, should be investigated very carefully.

S. R. Souza, W. P. Tan, R. Donangelo, C. K. Gelbke, W. G. Lynch, and M. B. Tsang

2000-11-10T23:59:59.000Z

263

Spectral Structure of Electron Antineutrinos from Nuclear Reactors  

E-Print Network [OSTI]

Recent measurements of the positron energy spectrum obtained from inverse beta decay interactions of reactor electron antineutrinos show an excess in the 4 to 6 MeV region relative to current predictions. First-principle calculations of fission and beta decay processes within a typical pressurized water reactor core identify prominent fission daughter isotopes as a possible origin for this excess. These calculations also predict percent-level substructure in the antineutrino spectrum due to Coulomb effects in beta decay. Precise measurement of this substructure can constrain nuclear reactor physics. The substructure can be a systematic uncertainty for measurements utilizing the detailed spectral shape.

D. A. Dwyer; T. J. Langford

2014-07-04T23:59:59.000Z

264

Strengthening the nuclear-reactor fuel cycle against proliferation  

SciTech Connect (OSTI)

Argonne National Laboratory (ANL) conducts several research programs that serve to reduce the risks of fissile-material diversion from the nuclear-reactor fuel cycle. The objectives are to provide economical and efficient neutron or power generation with the minimum of inherent risks, and to further minimize risks by utilizing sophisticated techniques to detect attempts at material diversion. This paper will discuss the Reduced Enrichment Research and Test Reactor (RERTR) Program, the Isotope Correlation Technique (ICT), and Proliferation-Resistant Closed-Cycle Reactors. The first two are sponsored by the DOE Office of Arms Control and Nonproliferation.

Travelli, A.; Snelgrove, J.; Persiani, P. [Argonne National Lab., IL (United States). Arms Control and Nonproliferation Program

1992-12-31T23:59:59.000Z

265

Oak Ridge Isotope Products and Services - Current and Expected Supply and Demand  

SciTech Connect (OSTI)

Oak Ridge National Laboratory (ORNL) has been a major center of isotope production research, development, and distribution for over 50 years. Currently, the major isotope production activities include (1) the production of transuranium element radioisotopes, including 252 Cf; (2) the production of medical and industrial radioisotopes; (3) maintenance and expansion of the capabilities for production of enriched stable isotopes; and, (4) preparation of a wide range of custom-order chemical and physical forms of isotope products, particularly in accelerator physics research. The recent supply of and demand for isotope products and services in these areas, research and development (R&D), and the capabilities for future supply are described in more detail below. The keys to continuing the supply of these important products and services are the maintenance, improvement, and potential expansion of specialized facilities, including (1) the High Flux Isotope Reactor (HFIR), (2) the Radiochemical Engineering Development Center (REDC) and Radiochemical Development Laboratory (RDL) hot cell facilities, (3) the electromagnetic calutron mass separators and the plasma separation process equipment for isotope enrichment, and (4) the Isotope Research Materials Laboratory (IRML) equipment for preparation of specialized chemical and physical forms of isotope products. The status and plans for these ORNL isotope production facilities are also described below.

Aaron, W.S.; Alexander, C.W.; Cline, R.L.; Collins, E.D.; Klein, J.A.; Knauer, J.B., Jr.; Mirzadeh, S.

1999-08-29T23:59:59.000Z

266

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

267

2006 TEPP Annual Report  

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

Emergency Emergency Preparedness Program 2006 Annual Report US Department of Energy - Offi ce of Environmental Management Transportation Emergency Preparedness Program 2006 Annual Report 2 2 Table of Contents Executive Summary.......................................................................................................................4 I. Transportation Emergency Preparedness Program Purpose.......................................6

268

Preliminary Notice of Violation, Isotopes Idaho, Inc. - EA-2000-04 |  

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

Isotopes Idaho, Inc. - EA-2000-04 Isotopes Idaho, Inc. - EA-2000-04 Preliminary Notice of Violation, Isotopes Idaho, Inc. - EA-2000-04 May 19, 2000 Preliminary Notice of Violation issued to International Isotopes Idaho, Inc., related to Work Planning and Control Deficiencies associated with Replacement of Exhaust Ventilation Filters at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory, This letter refers to the Department of Energy's (DOE) investigation of the facts and circumstances concerning work planning and work control deficiencies with regard to the replacement of hot cell exhaust ventilation filters at Test Reactor Area Building 632, Idaho National Engineering and Environmental Laboratory (INEEL). The result of these deficiencies was that

269

Preliminary Notice of Violation, Isotopes Idaho, Inc. - EA-2000-04 |  

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

Isotopes Idaho, Inc. - EA-2000-04 Isotopes Idaho, Inc. - EA-2000-04 Preliminary Notice of Violation, Isotopes Idaho, Inc. - EA-2000-04 May 19, 2000 Preliminary Notice of Violation issued to International Isotopes Idaho, Inc., related to Work Planning and Control Deficiencies associated with Replacement of Exhaust Ventilation Filters at the Test Reactor Area Hot Cell Facility at the Idaho National Engineering and Environmental Laboratory, This letter refers to the Department of Energy's (DOE) investigation of the facts and circumstances concerning work planning and work control deficiencies with regard to the replacement of hot cell exhaust ventilation filters at Test Reactor Area Building 632, Idaho National Engineering and Environmental Laboratory (INEEL). The result of these deficiencies was that

270

Library Annual Report Library Annual Report  

E-Print Network [OSTI]

Library Annual Report 2007 Library Annual Report 2007 #12;www.library.uwa.edu.au Our mission: By delivering excellent information resources and services the Library is integral to the University's mission of advancing, transmitting and sustaining knowledge. Our vision: The Library will continue to be at the heart

Tobar, Michael

271

Fusion power faces big crunch Europe poised to decide whether to go it alone on 3bn trial reactor  

E-Print Network [OSTI]

, in more than half a century of hard scientific slog, nuclear fusion has been a tough nut to crack, or 10 times its predicted input. The reactor will work by fusing two isotopes of hydrogen: deuterium

272

In-situ U-Pb analyses of highly altered zircon from sediments overlying the Bangombé natural fission reactor, Gabon  

Science Journals Connector (OSTI)

In-situ isotopic analyses of Pb and U in the highly altered zircons found in the clay and black shale layers above the Bangombé natural reactor, Republic of Gabon, were analyzed using a sensitive high resolution....

Makiko Kikuchi; Hiroshi Hidaka

2009-09-01T23:59:59.000Z

273

Computational Nuclear Forensics Analysis of Weapons-grade Plutonium Separated from Fuel Irradiated in a Thermal Reactor  

E-Print Network [OSTI]

have been irradiated to the desired burnup in the Oak Ridge National Laboratory- High Flux Isotope Reactor (ORNL-HFIR), and then separated using the PUREX process to experimentally determine the intrinsic signature of the fuel. The experimental data...

Coles, Taylor Marie

2014-04-27T23:59:59.000Z

274

Annual Report 2008.doc  

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

Cold War FY08 Annual Summary Report Cold War FY08 Annual Summary Report Page 1 of 14 Savannah River Site (SRS) Cold War Built Environment Historic Preservation Annual Summary Report Fiscal Year (FY) 2008 October 2008 Prepared by: The U. S. Department of Energy (DOE) Savannah River Operations Office (SR) SRS Cold War FY08 Annual Summary Report Page 2 of 14 TABLE OF CONTENTS Page BASIS.............................................................................................3

275

ANNUAL REVIEW FACTSHEET WORKFLOW  

E-Print Network [OSTI]

that the PhD has updated his T&SP (15. Second annual review). The PhD and the Promotor have to plan a date for the second annual review and the PhD has to enter that date in ProDoc (20 Date second annual review plannedANNUAL REVIEW FACTSHEET WORKFLOW PhD Candidate / Promotor / Dean / TGS / Doctorate Board / Pro

Twente, Universiteit

276

Annual Energy Review 2002  

Gasoline and Diesel Fuel Update (EIA)

Information Administration Annual Energy Review 2002 125 a Unfinished oils, motor gasoline blending components, aviation gasoline blending components, and other...

277

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

278

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

279

Annual Report and Accounts  

E-Print Network [OSTI]

Annual Report and Accounts 2013�2014 The Research Agency of the Forestry CommissionHC 2 #12;Forest Research Annual Report and Accounts 2013�2014 Presented to the House of Commons pursuant to Section 7 Annual Report and Accounts 2013�2014 Forest Research 1 #12;� Crown Copyright 2014 You may re

280

Atomic Spectroscopy and Separated Isotopes  

Science Journals Connector (OSTI)

The advantages in the use of separated isotopes in atomic spectroscopy for the determination of nuclear momentsI ? Q and for studies of the isotope-shift phenomena are discussed. Illustrations of spectra are given for mercury uranium and samarium. In addition a summary is given of twenty-two so-called problem nuclei i.e. those naturally occurring isotopes for which the nuclear moments are completely uncertain. Concluding remarks are made on such problems as the evaluation of the absolute magnitude of isotope shifts the role of “forbidden transitions” in isotope spectra and the potential future value of spectro-isotopic assay techniques.

J. R. McNally Jr.

1952-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

A one-group parametric sensitivity analysis for the graphite isotope ratio method and other related techniques using ORIGEN 2.2  

E-Print Network [OSTI]

Several methods have been developed previously for estimating cumulative energy production and plutonium production from graphite-moderated reactors. The Graphite Isotope Ratio Method (GIRM) is one well-known technique. This method is based...

Chesson, Kristin Elaine

2009-06-02T23:59:59.000Z

282

Radioactive Kr Isotopes  

Science Journals Connector (OSTI)

A radioactive isotope of 1.1-hour half-life has been produced in krypton by alpha-particle bombardment of Se74, enriched electromagnetically from 0.9 percent to 14.1 percent. Assignment of the isotope is made to Kr77. Aluminum absorption measurements indicate a positron end point of 1.7 Mev. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se74(?,n) reaction is computed as 2.6. The krypton 1.42-day isotope has been produced by an ?,n reaction on electromagnetically enriched Se76. The isotope is located as Kr79 and its half-life confirmed. A positron end point of 1.0 Mev is determined by aluminum absorption measurements. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se76(?,n) reaction is computed to be 50. The cross-section ratio for formation of Kr77 compared to Kr79 by alpha-particle bombardment of selenium is computed as 1.4. The 4.6-hour Kr85 isotope has been produced by a Se(?,n) reaction.

L. L. Woodward; D. A. Mccown; M. L. Pool

1948-10-01T23:59:59.000Z

283

International Nuclear Energy Research Initiative 2010 Annual Report  

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

2010 I-NERI Annual Report 2010 I-NERI Annual Report  | i Foreword The U.S. Department of Energy, Office of Nuclear Energy (DOE-NE), established the International Nuclear Energy Research Initiative (I-NERI) in fiscal year (FY) 2001 to conduct advanced nuclear energy systems research in collaboration with international partners. This annual report provides an update on research and development (R&D) accomplishments which the I-NERI program achieved during FY 2010. I-NERI supports bilateral scientific and engineering collaboration in advanced reactor systems and the nuclear fuel cycle and is linked to two of DOE-NE's primary research programs: Reactor Concepts Research, Development and Demonstration and the Fuel Cycle Research and Development program. I-NERI is designed to foster international partnerships to address key issues

284

Isotope separation apparatus  

DOE Patents [OSTI]

Isotope separation apparatus consisting of a plurality of cells disposed adjacent to each other in an evacuated container. A common magnetic field is established extending through all of the cells. A source of energetic electrons at one end of the container generates electrons which pass through the cells along the magnetic field lines. Each cell includes an array of collector plates arranged in parallel or in tandem within a common magnetic field. Sets of collector plates are disposed adjacent to each other in each cell. Means are provided for differentially energizing ions of a desired isotope by applying energy at the cyclotron resonant frequency of the desired isotope. As a result, the energized desired ions are preferentially collected by the collector plates.

Arnush, Donald (Rancho Palos Verdes, CA); MacKenzie, Kenneth R. (Pacific Palisades, CA); Wuerker, Ralph F. (Palos Verdes Estates, CA)

1980-01-01T23:59:59.000Z

285

Nuclear reactors built, being built, or planned 1992  

SciTech Connect (OSTI)

Nuclear Reactors Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1992. The Office of Scientific and Technical Information, US Department of Energy, gathers this information annually from Washington headquarters and field offices of DOE from the US Nuclear Regulatory Commission (NRC); from the US reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from US and foreign embassies; and from foreign governmental nuclear departments. Information is presented on five parts: Civilian, Production, Military, Export and Critical Assembly.

Not Available

1993-07-01T23:59:59.000Z

286

Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel  

SciTech Connect (OSTI)

This paper reviews the accuracy and precision of methods used by United States electric utilities to determine the actinide isotopic and element content of irradiated fuel. After an extensive literature search, three key code suites were selected for review. Two suites of computer codes, CASMO and ARMP, are used for reactor physics calculations; the ORIGEN code is used for spent fuel calculations. They are also the most widely used codes in the nuclear industry throughout the world. Although none of these codes calculate actinide isotopics as their primary variables intended for safeguards applications, accurate calculation of actinide isotopic content is necessary to fulfill their function.

Horak, W.C.; Lu, Ming-Shih

1991-12-01T23:59:59.000Z

287

SRS Small Modular Reactors  

SciTech Connect (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2012-04-27T23:59:59.000Z

288

SRS Small Modular Reactors  

ScienceCinema (OSTI)

The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

None

2014-05-21T23:59:59.000Z

289

Raman spectroscopic and mass spectrometric investigations of the hydrogen isotopes and isotopically labelled methane  

SciTech Connect (OSTI)

Suitable analytical methods must be tested and developed for monitoring the individual process steps within the fuel cycle of a fusion reactor and for tritium accountability. The utility of laser-Raman spectroscopy accompanied by mass spectrometry with an Omegatron was investigated using the analysis of all hydrogen isotopes and isotopically labeled methanes as an example. The Omegatron is useful for analyzing all hydrogen isotopes mixed with the stable helium isotopes. The application of this mass spectrometer were demonstrated by analyzing mixtures of deuterated methanes. In addition, it was employed to study the radiochemical Witzbach exchange reaction between tritium and methanes. A laser-Raman spectrometer was designed for analysis of tritium-containing gases and was built from individual components. A tritium-compatible, metal-sealed Raman cuvette having windows with good optical properties and additional means for measuring the stray light was first used successfully in this work. The Raman spectra of the hydrogen isotopes were acquired in the pure rotation mode and in the rotation-vibration mode and were used for on. The deuterated methanes were measured by Raman spectroscopy, the wavenumbers determined were assigned to the corresponding vibrations, and the wavenumbers for the rotational fine-structure were summarized in tables. The fundamental Vibrations of the deuterated methanes produced Witzbach reactions were detected and assigned. The fundamental vibrations of the molecules were obtained with Raman spectroscopy for the first time in this work. The @-Raman spectrometer assembled is well suited for the analysis of tritium- containing gases and is practical in combination with mass spectrometry using an Omegatron, for studying gases used in fusion.

Jewett, J.R., Fluor Daniel Hanford

1997-02-24T23:59:59.000Z

290

Isotope Effect of Mercury Diffusion in Air  

Science Journals Connector (OSTI)

Isotope fractionation describes the separation of a reservoir with one isotope composition into “fractions” with different isotope compositions due to small isotopic differences in equilibrium partitioning, rates of mass transfer, or rates of transformation. ... (29) ?202Hg is the value most frequently used to examine mass dependent fractionation of mercury isotopes as 202Hg is the heaviest mercury isotope without significant isobaric interferences. ...

Paul G. Koster van Groos; Bradley K. Esser; Ross W. Williams; James R. Hunt

2013-12-23T23:59:59.000Z

291

i TrT\\YT(V^/f%\\ Ris-R-435 Department of Reactor  

E-Print Network [OSTI]

of Reliability Techniques 15 3. REACTOR PHYSICS AND DYNAMICS 19 3.1. Interface Methods for Solving the Neutron Accident Analysis 36 4.2. Experiments 39 5. THE DR 1 REACTOR 42 5.1. Neutron Radiography 42 5.2. Reactivityi« TrT\\YT(V^/f%\\ Risø-R-435 · e £ Department of Reactor Technology Annual Progress Report 1January

292

Nuclear reactor  

DOE Patents [OSTI]

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

293

LNG Annual Report - 2013 | Department of Energy  

Energy Savers [EERE]

Annual Report - 2013 LNG Annual Report - 2013 LNG Annual Report - 2013 LNG 2013.pdf More Documents & Publications LNG Annual Report - 2012 LNG Monthly Report - August 2014...

294

LNG Annual Report - 2008 | Department of Energy  

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

8 LNG Annual Report - 2008 LNG Annual Report - 2008 (Revised 10142009) LNG Annual Report - 2008 More Documents & Publications LNG Annual Report - 2009...

295

LM Annual Post Competition Accountability Reports | Department...  

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

LM Annual Post Competition Accountability Reports LM Annual Post Competition Accountability Reports Third Annual Post Competition Accountability Report Second Annual Post...

296

High Flux Isotope Reactor quarterly report, January-March 1986  

SciTech Connect (OSTI)

Four routine cycles of operation were completed during the first quarter. Four scheduled end-of-cycle shutdowns and two unscheduled shutdowns resulted in an on-stream time of 86.9%. An unscheduled control plate and control cylinder replacement was performed after tantalum contamination in the primary coolant system was traced to the inner cylinder.

Corbett, B.L.; Farrar, M.B.

1986-06-01T23:59:59.000Z

297

Selection of Isotopes and Elements for Fuel Cycle Analysis  

SciTech Connect (OSTI)

Fuel cycle system analysis simulations examine how the selection among fuel cycle options for reactors, fuel, separation, and waste management impact uranium ore utilization, waste masses and volumes, radiotoxicity, heat to geologic repositories, isotope-dependent proliferation resistance measures, and so forth. Previously, such simulations have tended to track only a few actinide and fission product isotopes, those that have been identified as important to a few criteria from the standpoint of recycled material or waste, taken as a whole. After accounting for such isotopes, the residual mass is often characterized as “fission product other” or “actinide other”. However, detailed assessment of separation and waste management options now require identification of key isotopes and residual mass for Group 1A/2A elements (Rb, Cs, Sr, Ba), inert gases (Kr, Xe), halogens (Br, I), lanthanides, transition metals, transuranic (TRU), uranium, actinide decay products. The paper explains the rationale for a list of 81 isotopes and chemical elements to better support separation and waste management assessment in dynamic system analysis models such as Verifiable Fuel Cycle Simulation (VISION)

Steven J. Piet

2009-04-01T23:59:59.000Z

298

Historical Natural Gas Annual  

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

Annual . 1996 Published October 1997 1997 Published October 1998 1998 Published October 1999 1999 Published October 2000 2000 Published December 2001...

299

Annual Report Generator.  

E-Print Network [OSTI]

?? This report analyzes the needs to build an annual report generator which has the properties of Modularity, Simplicity in use and Maintainability based on… (more)

Lin, Yingwei

2006-01-01T23:59:59.000Z

300

Historical Natural Gas Annual  

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

8 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

Note: This page contains sample records for the topic "isotope reactor annual" 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

Historical Natural Gas Annual  

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

6 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

302

Historical Natural Gas Annual  

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

7 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at...

303

BPA 2002 Annual Report  

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

STATEMENTS 2002 Annual Report of the Bonneville Power Administration Cover photo BPA fish biologist Andy Thoms (upper right) works with students from H.B. Lee Middle School...

304

Annual Energy Outlook 2012  

Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

and may differ slightly from official EIA data reports. Sources: 2010 data based on: Oak Ridge National Laboratory, Transportation Energy Data Book: Edition 28 and Annual (Oak...

305

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

Federal Highway Administration, Highway Statistics 2009 (Washington, DC, April 2011); Oak Ridge National Laboratory, Transportation Energy Data Book: Edition 30 and Annual (Oak...

306

2007 Annual Report  

SciTech Connect (OSTI)

This annual report includes: a brief overview of Western; FY 2007 highlights; FY 2007 Integrated Resource Planning, or IRP, survey; and financial data.

none,

2007-01-01T23:59:59.000Z

307

Annual Performance Report  

Office of Legacy Management (LM)

left blank U.S. Department of Energy Annual Performance Report, Shiprock, New Mexico October 2014 Doc. No. S12021 Page i Contents Abbreviations ......

308

NLC Annual Conference  

Broader source: Energy.gov [DOE]

The National League of Cities (NLC) is hosting its annual Congressional City Conference in Washington, D.C., from March 7-11, 2015.

309

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

4 Regional maps Figure F3. Petroleum Administration for Defense Districts 216 U.S. Energy Information Administration Annual Energy Outlook 2010 Figure F3. Petroleum...

310

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

36 Reference case Energy Information Administration Annual Energy Outlook 2012 6 Table A3. Energy prices by sector and source (2010 dollars per million Btu, unless otherwise...

311

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

9 U.S. Energy Information Administration | Annual Energy Outlook 2012 Table G1. Heat rates Fuel Units Approximate heat content Coal 1 Production . . . . . . . . . . . . . . . . . ....

312

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

-- -- -- -- not reported. See notes at end of table. (continued on next page) U.S. Energy Information Administration | Annual Energy Outlook 2012 116 Comparison with other...

313

SFU LIBRARY ANNUAL REPORT  

E-Print Network [OSTI]

SFU LIBRARY ANNUAL REPORT 2006/07 #12;22 TABLE OF CONTENTS Message from the University Librarian................................................... ....................................... 7 WAC Bennett Library.................................................................. ....................................... 8 Samuel and Frances Belzberg Library

314

Annual Coal Distribution Report  

Gasoline and Diesel Fuel Update (EIA)

Distribution Report Release Date: December 19, 2013 | Next Release Date: December 12, 2014 | full report | RevisionCorrection Revision to the Annual Coal Distribution Report...

315

EMSL 2009 Annual Report  

SciTech Connect (OSTI)

The EMSL 2009 Annual Report describes the science conducted at EMSL during 2009 as well as outreach activities and awards and honors received by users and staff.

Showalter, Mary Ann; Kathmann, Loel E.; Manke, Kristin L.; Wiley, Julie G.; Reed, Jennifer R.

2010-02-26T23:59:59.000Z

316

SPEER Third Annual Summit  

Broader source: Energy.gov [DOE]

The South-Central Partnership for Energy Efficiency as a Resource (SPEER) is hosting their 3rd Annual Summit in Dallas, Texas.

317

OPSI Annual Meeting  

Broader source: Energy.gov [DOE]

The Organization of PJM States, Inc. (OPSI) is hosting its annual meeting in Chicago, IL, on October 13-14, 2014.

318

Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report  

SciTech Connect (OSTI)

Overview Fast reactors were evaluated to enable the transmutation of transuranic isotopes generated by nuclear energy systems. The motivation for this was that TRU isotopes have high radiotoxicity and relatively long half-lives, making them unattractive for disposal in a long-term geologic repository. Fast reactors provide an efficient means to utilize the energy content of the TRUs while destroying them. An enabling technology that requires research and development is the fabrication metallic fuel containing TRU isotopes using powder metallurgy methods. This project focused upon developing a powder metallurgical fabrication method to produce U-Zr-transuranic (TRU) alloys at relatively low processing temperatures (500ºC to 600ºC) using either hot extrusion or alpha-phase sintering for charecterization. Researchers quantified the fundamental aspects of both processing methods using surrogate metals to simulate the TRU elements. The process produced novel solutions to some of the issues relating to metallic fuels, such as fuel-cladding chemical interactions, fuel swelling, volatility losses during casting, and casting mold material losses. Workscope There were two primary tasks associated with this project: 1. Hot working fabrication using mechanical alloying and extrusion • Design, fabricate, and assemble extrusion equipment • Extrusion database on DU metal • Extrusion database on U-10Zr alloys • Extrusion database on U-20xx-10Zr alloys • Evaluation and testing of tube sheath metals 2. Low-temperature sintering of U alloys • Design, fabricate, and assemble equipment • Sintering database on DU metal • Sintering database on U-10Zr alloys • Liquid assisted phase sintering on U-20xx-10Zr alloys Appendices Outline Appendix A contains a Fuel Cycle Research & Development (FCR&D) poster and contact presentation where TAMU made primary contributions. Appendix B contains MSNE theses and final defense presentations by David Garnetti and Grant Helmreich outlining the beginning of the materials processing setup. Also included within this section is a thesis proposal by Jeff Hausaman. Appendix C contains the public papers and presentations introduced at the 2010 American Nuclear Society Winter Meeting. Appendix A—MSNE theses of David Garnetti and Grant Helmreich and proposal by Jeff Hausaman A.1 December 2009 Thesis by David Garnetti entitled “Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.2 September 2009 Presentation by David Garnetti (same title as document in Appendix B.1) A.3 December 2010 Thesis by Grant Helmreich entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications” A.4 October 2010 Presentation by Grant Helmreich (same title as document in Appendix B.3) A.5 Thesis Proposal by Jeffrey Hausaman entitled “Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors” Appendix B—External presentations introduced at the 2010 ANS Winter Meeting B.1 J.S. Hausaman, D.J. Garnetti, and S.M. McDeavitt, “Powder Metallurgy of Alpha Phase Uranium Alloys for TRU Burning Fast Reactors,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.2 PowerPoint Presentation Slides from C.1 B.3 G.W. Helmreich, W.J. Sames, D.J. Garnetti, and S.M. McDeavitt, “Uranium Powder Production Using a Hydride-Dehydride Process,” Proceedings of 2010 ANS Winter Meeting, Las Vegas, Nevada, USA, November 7-10, 2010 B.4. PowerPoint Presentation Slides from C.3 B.5 Poster Presentation from C.3 Appendix C—Fuel cycle research and development undergraduate materials and poster presentation C.1 Poster entitled “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys” presented at the Fuel Cycle Technologies Program Annual Meeting C.2 April 2011 Honors Undergraduate Thesis by William Sames, Research Fellow, entitled “Uranium Metal Powder Production, Particle Dis

Sean M. McDeavitt

2011-04-29T23:59:59.000Z

319

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: DUPIC Fuel Fabrication Cost  

SciTech Connect (OSTI)

A preliminary conceptual design of a Direct Use of spent Pressurized water reactor (PWR) fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel fabrication plant was studied, which annually converts spent PWR fuel of 400 tonnes heavy element (HE) into CANDU fuel. The capital and operating costs were estimated from the viewpoint of conceptual design. Assuming that the annual discount rate is 5% during the construction (5 yr) and operation period (40 yr) and contingency is 25% of the capital cost, the levelized unit cost (LUC) of DUPIC fuel fabrication was estimated to be 616 $/kg HE, which is mostly governed by annual operation and maintenance costs that correspond to 63% of LUC. Among the operation and maintenance cost components being considered, the waste disposal cost has the dominant effect on LUC ({approx}49%). From sensitivity analyses of production capacity, discount rate, and contingency, it was found that the production capacity of the plant is the major parameter that affects the LUC.

Choi, Hangbok; Ko, Won Il; Yang, Myung Seung [Korea Atomic Energy Research Institute (Korea, Republic of)

2001-05-15T23:59:59.000Z

320

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect (OSTI)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Annual Report School of Engineering  

E-Print Network [OSTI]

Annual Report 1999-2000 School of Engineering University of Connecticut #12;#12;University of Connecticut School of Engineering Annual Report 1999-2000 Table of Contents School of Engineering Annual Report Summary................................................................................... 3

Alpay, S. Pamir

322

University of Lethbridge Annual Report  

E-Print Network [OSTI]

University of Lethbridge Annual Report 2011/12 #12; i University of Lethbridge 2011/12 Annual Report ACCOUNTABILITY STATEMENT The University of Lethbridge Annual Report for the year ended March 31, 2012 was prepared

Seldin, Jonathan P.

323

Radiation Exposure Information Reporting System (REIRS) Update, 2012, Presented at the 32nd Annual International Dosimetry and Records Symposium, June 2-6, 2013  

SciTech Connect (OSTI)

A series of graphs gives data through the year 2012 for annual collective doses, collective dose per reactor, number of individuals with measurable doses both in total and per reactor, number of reactors, electricity generated, measurable doses per individual and per megawatt-year, and collective outage hours. Reactors considered include BWR, PWR, and LWR. Also, the total effective dose equivalent for the period 2010-2012 is tabulated for each nuclear power plant considered, and the change over 2009-2011.

none,

2013-01-01T23:59:59.000Z

324

Infrastructure for thulium-170 isotope power systems for autonomous underwater vehicle fleets  

SciTech Connect (OSTI)

The radioisotope thulium-170 is a safe and environmentally benign heat source for providing the high endurance and energy densities needed by advanced power systems for autonomous underwater vehicles (AUV). Thulium Isotope Power (TIP) systems have an endurance of {approximately}3000 h, and gravimetric and volumetric energy densities of 3 {times} 10{sup 4} Wh/kg and 3 {times} 10{sup 8} Wh/m{sup 3}, respectively. These energy densities are more than 200 times higher than those currently provided by Ag-Zn battery technology. In order to capitalize on these performance levels with about one hundred AUVs in continuous use, it will be necessary to establish an infrastructure for isotope production and heat-source refurbishment. The infrastructure cost is not trivial, and studies are needed to determine its optimum configuration. The major component of the projected infrastructure is the nuclear reactor used to produce Tm- 170 by neutron absorption in Tm-169. The reactor design should ideally be optimized for TM-170 production. Using the byproduct waste'' heat beneficially would help defray the cost of isotope production. However, generating electric power with the reactor would compromise both the cost of electricity and the isotope production capacity. A coastal location for the reactor would be most convenient from end-use considerations, and the waste'' heat could be used to desalinate seawater in water-thirsty states. 13 refs., 6 figs., 2 tabs.

Walter, C.E.

1991-07-01T23:59:59.000Z

325

2005 TEPP Annual Report  

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

Transportation Emergency Transportation Emergency Preparedness Program 2005 Annual Report Special thanks to participants in the Haralson County, Georgia and Leigh Valley International Airport, Pennsylvania exercises who are featured on the front cover of this report. Transportation Emergency Preparedness Program 2005 Annual Report Table of Contents Executive Summary ..................................................................................................1 I. Transportation Emergency Preparedness Program Purpose ......................3 II. Training ............................................................................................................3 III. TEPP Central Operations .................................................................................5

326

2004 TEPP Annual Report  

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

Transportation Transportation Transportation Emergency Preparedness Program 2004 Annual Report United States Department of Energy Transportation Emergency Preparedness Program (TEPP) 2004 Annual Report Table of Contents Executive Summary..................................................................................... 1 I. Transportation Emergency Preparedness Program Purpose ...... 3 II. Training.............................................................................................. 3 III. Outreach and Conferences ............................................................... 5 IV. Go-Kits ............................................................................................... 5 V. TEPP Exercise and Tabletop Activities ..........................................

327

Annual Fire Safety Report  

E-Print Network [OSTI]

2010 Annual Fire Safety Report University of California, Irvine HIGHER EDUCATION OPPORTUNITY to the Fire Safety in Student Housing Buildings of current or perspective students and employees be reported publish an annual fire safety report, keep a fire log, and report fire statistics to the Secretary

Loudon, Catherine

328

Information Annual Report  

E-Print Network [OSTI]

Information Technology Services 2012­13 Annual Report #12;#12;Contents Administrative Information ______117 Telecommunications and Networking Services __151 #12;#12;5 ITS 2012-13 Administrative Information Services INFORMATION TECHNOLOGY SERVICES Administrative Information Services 2012­13 Annual Report

Maroncelli, Mark

329

Annual Energy Review, 2008  

SciTech Connect (OSTI)

The Annual Energy Review (AER) is the Energy Information Administration's (EIA) primary report of annual historical energy statistics. For many series, data begin with the year 1949. Included are statistics on total energy production, consumption, trade, and energy prices; overviews of petroleum, natural gas, coal, electricity, nuclear energy, renewable energy, and international energy; financial and environment indicators; and data unit conversions.

None

2009-06-01T23:59:59.000Z

330

Advanced Neutron Source Reactor thermal analysis of fuel plate defects  

SciTech Connect (OSTI)

The Advanced Neutron Source Reactor (ANSR) is a research reactor designed to provide the highest continuous neutron beam intensity of any reactor in the world. The present technology for determining safe operations were developed for the High Flux Isotope Reactor (HFIR). These techniques are conservative and provide confidence in the safe operation of HFIR. However, the more intense requirements of ANSR necessitate the development of more accurate, but still conservative, techniques. This report details the development of a Local Analysis Technique (LAT) that provides an appropriate approach. Application of the LAT to two ANSR core designs are presented. New theories of the thermal and nuclear behavior of the U{sub 3}Si{sub 2} fuel are utilized. The implications of lower fuel enrichment and of modifying the inspection procedures are also discussed. Development of the computer codes that enable the automate execution of the LAT is included.

Giles, G.E.

1995-08-01T23:59:59.000Z

331

ANNUAL SECURITY FIRE SAFETY REPORT  

E-Print Network [OSTI]

ANNUAL SECURITY AND FIRE SAFETY REPORT OCTOBER 1, 2013 DARTMOUTH COLLEGE http................................................................................................................................................................... 7 ANNUAL SECURITY REPORT........................................................................................................................9 PREPARATION OF THE REPORT AND DISCLOSURE OF CRIME STATISTICS

332

2013 Uranium Marketing Annual Report  

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

Industry Annual, Tables 10, 11 and 16. 2003-2013-Form EIA-858, "Uranium Marketing Annual Survey". million pounds U 3 O 8 equivalent 1 Includes purchases between...

333

Attrition reactor system  

DOE Patents [OSTI]

A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.

Scott, C.D.; Davison, B.H.

1993-09-28T23:59:59.000Z

334

Elementary Reactor Physics  

Science Journals Connector (OSTI)

... THERE are few subjects which have developed at the rate at which reactor physics and ... physics and reactor theory have done. This, of course, is largely due to the circumstances in ...

J. F. HILL

1962-02-10T23:59:59.000Z

335

Colliding Beam Fusion Reactors  

Science Journals Connector (OSTI)

The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the Fokker–Planck equation. The reactors involve non-Maxwellian plasmas. The calculations are ... the rec...

Norman Rostoker; Artan Qerushi; Michl Binderbauer

2003-06-01T23:59:59.000Z

336

Historical Natural Gas Annual  

Gasoline and Diesel Fuel Update (EIA)

6 6 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at selected points in the flow of gas from the wellhead to the burner-tip. Data include production, transmission within the United States, imports and exports of natural gas, underground storage activities, and deliveries to consumers. The publication presents historical data at the national level for 1930-1996 and detailed annual historical information by State for 1967-1996. The Historical Natural Gas Annual tables are available as self-extracting executable files in ASCII TXT or CDF file formats. Tables 1-3 present annual historical data at the national level for 1930-1996. The remaining tables contain detailed annual historical information, by State, for 1967-1996. Please read the file entitled READMEV2 for a description and documentation of information included in this file.

337

Historical Natural Gas Annual  

Gasoline and Diesel Fuel Update (EIA)

7 7 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at selected points in the flow of gas from the wellhead to the burner-tip. Data include production, transmission within the United States, imports and exports of natural gas, underground storage activities, and deliveries to consumers. The publication presents historical data at the national level for 1930-1997 and detailed annual historical information by State for 1967-1997. The Historical Natural Gas Annual tables are available as self-extracting executable files in ASCII TXT or CDF file formats. Tables 1-3 present annual historical data at the national level for 1930-1997. The remaining tables contain detailed annual historical information, by State, for 1967-1997. Please read the file entitled READMEV2 for a description and documentation of information included in this file.

338

Historical Natural Gas Annual  

Gasoline and Diesel Fuel Update (EIA)

8 8 The Historical Natural Gas Annual contains historical information on supply and disposition of natural gas at the national, regional, and State level as well as prices at selected points in the flow of gas from the wellhead to the burner-tip. Data include production, transmission within the United States, imports and exports of natural gas, underground storage activities, and deliveries to consumers. The publication presents historical data at the national level for 1930-1998 and detailed annual historical information by State for 1967-1998. The Historical Natural Gas Annual tables are available as self-extracting executable files in ASCII TXT or CDF file formats. Tables 1-3 present annual historical data at the national level for 1930-1998. The remaining tables contain detailed annual historical information, by State, for 1967-1998. Please read the file entitled READMEV2 for a description and documentation of information included in this file.

339

Prospects for spheromak fusion reactors  

Science Journals Connector (OSTI)

The reactor study of Hagenson and Krakowski demonstrated the attractiveness of the spheromak as a compact fusion reactor, based on...

T. K. Fowler; D. D. Hua

1995-06-01T23:59:59.000Z

340

Soil Studies with Isotopes  

Science Journals Connector (OSTI)

... reference are even strained to include the use of steam from nuclear reactors for the desalination of water. The proceedings are divided into five sections dealing respectively with equipment and ... moisture profile; soil water movement ; the interaction between soil, vegetation and water; and desalination of water for agriculture. Among the most valuable contributions are comparisons between the performance ...

E. C. CHILDS

1968-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Advanced Test Reactor Tour  

SciTech Connect (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2011-01-01T23:59:59.000Z

342

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

1995-01-01T23:59:59.000Z

343

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

Miley, Don

2013-05-28T23:59:59.000Z

344

Radiation effects on reactor pressure vessel supports  

SciTech Connect (OSTI)

The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, further tests designed to evaluate the applicability of the HFIR data to reactor RPV supports under operating conditions led to the conclusion that RPV supports could be evaluated using traditional method. It was found that the unique HFIR radiation environment allowed the gamma radiation to contribute significantly to the embrittlement. The shielding provided by the thick steel RPV shell ensures that degradation of RPV supports from gamma irradiation is improbable or minimal. The findings reported herein were used, in part, as the basis for technical resolution of the issue.

Johnson, R.E. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Lipinski, R.E. [Idaho National Engineering Lab., Rockville, MD (United States)

1996-05-01T23:59:59.000Z

345

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

346

Two-billion-year-old nuclear reactors: Nature goes fission  

SciTech Connect (OSTI)

Once it was thought that the isotopic composition of natural uranium was invariant. It was thus surprising in 1972 when French scientists observed small but significant deficiencies of the minor isotope {sup 235}U in uranium ore. Subsequent investigations traced the isotopically anomalous material to the Oklo mine in the African Republic of Gabon. In the mine, cubic-dekametre-sized pods of rock were found to contain extraordinary concentrations of uranium, as much as 65%, with as little as half the normal isotopic abundance of {sup 235}U. In these rocks, neodymium was found to be deficient in the premordial isotope {sup 142}Nd and enriched in the fission-produced isotopes {sup 143-150}Nd. The presence of fission products was unambiguous evidence that the {sup 235}U deficiencies were the result of sustained nuclear fission. Within the heart of the natural reactors, the fission densities were on the order of 10{sup 20} fissions/cm{sup 3}, producing hundreds of megajoules of energy and tens of microwatts of power per gram of rock. Nature had forestalled man`s great discovery of energy production by nuclear fission.

Curtis, D.B. [Los Alamos National Lab., NM (US)

1992-12-31T23:59:59.000Z

347

Comparisons between stable isotope tr  

Science Journals Connector (OSTI)

Nitrogen spiraling in streams: Comparisons between stable isotope tracer and nutrient addition experiments. Abstract—A common method to quantify stream.

2007-05-31T23:59:59.000Z

348

Natural Gas Annual 2006  

Gasoline and Diesel Fuel Update (EIA)

6 6 Released: October 31, 2007 The Natural Gas Annual 2006 Summary Highlights provides an overview of the supply and disposition of natural gas in 2006 and is intended as a supplement to the Natural Gas Annual 2006. The Natural Gas Annual 2006 Summary Highlights provides an overview of the supply and disposition of natural gas in 2006 and is intended as a supplement to the Natural Gas Annual 2006. Natural Gas Annual --- Full report in PDF (5 MB) Special Files --- All CSV files contained in a self-extracting executable file. Respondent/Company Level Natural Gas Data Files Annual Natural and Supplemental Gas Supply and Disposition Company level data (1996 to 2007) as reported on Form EIA-176 are provided in the EIA-176 Query System and selected data files. EIA-191A Field Level Underground Natural Gas Storage Data: Detailed annual data (2006 and 2007) of storage field capacity, field type, and maximum deliverability as of December 31st of the report year, as reported by operators of all U.S. underground natural gas storage fields.

349

Reactor vessel support system  

DOE Patents [OSTI]

A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

1982-01-01T23:59:59.000Z

350

Analyzing Nuclear Fuel Cycles from Isotopic Ratios of Waste Products Applicable to Measurement by Accelerator Mass Spectrometry  

SciTech Connect (OSTI)

An extensive study was conducted to determine isotopic ratios of nuclides in spent fuel that may be utilized to reveal historical characteristics of a nuclear reactor cycle. This forensic information is important to determine the origin of unknown nuclear waste. The distribution of isotopes in waste products provides information about a nuclear fuel cycle, even when the isotopes of uranium and plutonium are removed through chemical processing. Several different reactor cycles of the PWR, BWR, CANDU, and LMFBR were simulated for this work with the ORIGEN-ARP and ORIGEN 2.2 codes. The spent fuel nuclide concentrations of these reactors were analyzed to find the most informative isotopic ratios indicative of irradiation cycle length and reactor design. Special focus was given to long-lived and stable fission products that would be present many years after their creation. For such nuclides, mass spectrometry analysis methods often have better detection limits than classic gamma-ray spectroscopy. The isotopic ratios {sup 151}Sm/{sup 146}Sm, {sup 149}Sm/{sup 146}Sm, and {sup 244}Cm/{sup 246}Cm were found to be good indicators of fuel cycle length and are well suited for analysis by accelerator mass spectroscopy.

Biegalski, S R; Whitney, S M; Buchholz, B

2005-08-24T23:59:59.000Z

351

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling.

Gluntz, Douglas M. (San Jose, CA); Taft, William E. (Los Gatos, CA)

1994-01-01T23:59:59.000Z

352

Reactor water cleanup system  

DOE Patents [OSTI]

A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

Gluntz, D.M.; Taft, W.E.

1994-12-20T23:59:59.000Z

353

RADIOCHEMICAL STUDIES OF NEUTRON DEFICIENT ACTINIDE ISOTOPES  

E-Print Network [OSTI]

Isotope Targets and Foils, AERE-R 5097, Paper 10 (1965). V.Isotope Targets and Foils, AERE-R 5097 Paper 12 (1965). K.M.Isotope Targets and Foils, AERE-R-5097 Paper 11 (1965). M.

Williams, Kimberly Eve

2011-01-01T23:59:59.000Z

354

School of Engineering Annual Report  

E-Print Network [OSTI]

School of Engineering 1 9 9 9 Annual Report #12;University of ConnecticutUniversity of Connecticut School of EngineeringSchool of Engineering Annual ReportAnnual Report 1998-19991998-1999 TTable of Contentsable of Contents SCHOOL OF ENGINEERING Annual Report Summary

Alpay, S. Pamir

355

Preliminary Notice of Violation, MAC Isotopes, LLC - EA- 1998-05 |  

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

MAC Isotopes, LLC - EA- 1998-05 MAC Isotopes, LLC - EA- 1998-05 Preliminary Notice of Violation, MAC Isotopes, LLC - EA- 1998-05 June 4, 1998 Preliminary Notice of Violation issued to MAC Isotopes, LLC, related to a Radioactive Material Release at the Idaho National Engineering and Environmental Laboratory, (1998-05) This letter refers to the Department of Energy's (DOE) investigation of the facts and circumstances concerning the release of radioactive material at the Idaho National Engineering and Environmental Laboratory (INEEL). Specifically, on September 17, 1997, radioactive [material] was uncontrollably released to Test Reactor Area [building] from [material] processing activities taking place in [a Hot Cell]. The result of this release was contamination of the entire interior of [the building] and the

356

Advanced isotope separation  

SciTech Connect (OSTI)

The Study Group briefly reviewed the technical status of the three Advanced Isotope Separation (AIS) processes. It also reviewed the evaluation work that has been carried out by DOE's Process Evaluation Board (PEB) and the Union Carbide Corporation-Nuclear Division (UCCND). The Study Group briefly reviewed a recent draft assessment made for DOE staff of the nonproliferation implications of the AIS technologies. The staff also very briefly summarized the status of GCEP and Advanced Centrifuge development. The Study Group concluded that: (1) there has not been sufficient progress to provide a firm scientific, technical or economic basis on which to select one of the three competing AIS processes for full-scale engineering development at this time; and (2) however, should budgetary restraints or other factors force such a selection, we believe that the evaluation process that is being carried out by the PEB provides the best basis available for making a decision. The Study Group recommended that: (1) any decisions on AIS processes should include a comparison with gas centrifuge processes, and should not be made independently from the plutonium isotope program; (2) in evaluating the various enrichment processes, all applicable costs (including R and D and sales overhead) and an appropriate discounting approach should be included in order to make comparisons on a private industry basis; (3) if the three AIS programs continue with limited resources, the work should be reoriented to focus only on the most pressing technical problems; and (4) if a decision is made to develop the Atomic Vapor Laser Isotope Separation process, the solid collector option should be pursued in parallel to alleviate the potential program impact of liquid collector thermal control problems.

Not Available

1982-05-04T23:59:59.000Z

357

R-Area Reactor 1993 annual groundwater monitoring report  

SciTech Connect (OSTI)

Groundwater was sampled and analyzed during 1993 from wells monitoring the following locations in R Area: Well cluster P20 east of R Area (one well each in the water table and the McBean formation), the R-Area Acid/Caustic Basin (the four water-table wells of the RAC series), the R-Area Ash Basin/Coal Pile (one well of the RCP series in the Congaree formation and one in the water table), the R-Area Disassembly Basin (the three water-table wells of the RDB series), the R-Area Burning/Rubble Pits (the four water-table wells of the RRP series), and the R-Area Seepage Basins (numerous water-table wells in the RSA, RSB, RSC, RSD, RSE, and RSF series). Lead was the only constituent detected above its 50{mu}g/L standard in any but the seepage basin wells; it exceeded that level in one B well and in 23 of the seepage basin wells. Cadmium exceeded its drinking water standard (DWS) in 30 of the seepage basin wells, as did mercury in 10. Nitrate-nitrite was above DWS once each in two seepage basin wells. Tritium was above DWS in six seepage basin wells, as was gross alpha activity in 22. Nonvolatile beta exceeded its screening standard in 29 wells. Extensive radionuclide analyses were requested during 1993 for the RCP series and most of the seepage basin wells. Strontium-90 in eight wells was the only specific radionuclide other than tritium detected above DWS; it appeared about one-half of the nonvolatile beta activity in those wells.

Not Available

1994-09-01T23:59:59.000Z

358

P-Area Reactor 1993 annual groundwater monitoring report  

SciTech Connect (OSTI)

Groundwater was sampled and analyzed during 1993 from wells monitoring the water table at the following locations in P Area: well P 24A in the eastern section of P Area, the P-Area Acid/Caustic Basin, the P-Area Coal Pile Runoff Containment Basin, the P-Area Disassembly Basin, the P-Area Burning/Rubble Pit, and the P-Area Seepage Basins. During 1993, pH was above its alkaline standard in well P 24A. Specific conductance was above its standard in one well each from the PAC and PCB series. Lead exceeded its 50 {mu}g/L standard in one well of the PDB series during one quarter. Tetrachloroethylene and trichloroethylene were detected above their final primary drinking water standards in one well of the PRP well series. Tritium was consistently above its DWS in the PDB and PSB series. Also during 1993, radium-228 exceeded the DWS for total radium in three wells of the PAC series and one well of the PCB series; total alpha-emitting radium exceeded the same standard in a different PCB well. These results are fairly consistent with those from previous years. Unlike results from past years, however, no halogenated volatiles other than trichloroethylene and tetrachloroethylene exceeded DWS in the PRP well series although gas chromatographic volatile organic analyses were performed throughout the year. Some of the regulated units in P Area appear to need additional monitoring by new wells because there are insufficient downgradient wells, sometimes because the original well network, installed prior to regulation, included sidegradient rather than downgradient wells. No monitoring wells had been installed through 1993 at one of the RCRA/CERCLA units named in the Federal Facilities Agreement, the Bingham Pump Outage Pits.

NONE

1994-11-01T23:59:59.000Z

359

L-Area Reactor - 1993 annual - groundwater monitoring report  

SciTech Connect (OSTI)

Groundwater was sampled and analyzed during 1993 from wells monitoring the water table at the following locations in L Area: the L-Area Acid/Caustic Basin (four LAC wells), L-Area Research Wells in the southern portion of the area (outside the fence; three LAW wells), the L-Area Oil and Chemical Basin (four LCO wells), the L-Area Disassembly Basin (two LDB wells), the L-Area Burning/Rubble Pit (four LRP wells), and the L-Area Seepage Basin (four LSB wells). During 1993, tetrachloroethylene was detected above its drinking water standard (DWS) in the LAC, LAW, LCO, and LDB well series. Lead exceeded its 50 {mu}g/L standard in the LAW, LDB, and LRP series, and tritium was above its DWS in the LAW, LCO, and LSB series. Apparently anomalous elevated levels of the common laboratory contaminant bis(2-ethylhexyl)phthalate were reported during first quarter in one well each in the LAC series and LCO series, and during third quarter in a different LCO well. Extensive radionuclide analyses were performed during 1993 in the LAC, LAW, and LCO well series. No radionuclides other than tritium were reported above DWS or Flag 2 criteria.

Chase, J.A.

1994-09-01T23:59:59.000Z

360

Annual Reports | Department of Energy  

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

Services » Annual Reports Services » Annual Reports Annual Reports Annual Reports December 28, 2012 Southeastern Power Administration 2012 Annual Report This report reflects our agency's programs,accomplishments, operational, and financial activities for the 12-month period beginning October 1, 2011, and ending September 30, 2012. December 31, 2011 Southeastern Power Administration 2011 Annual Report This report reflects our agency's programs, accomplishments, operational, and financial activities for the 12-month period beginning October 1, 2010, and ending September 31, 2011. December 27, 2010 Southeastern Power Administration 2010 Annual Report This report reflects our agency's programs, accomplishments, operational, and financial activities for the 12-month period beginning October 1, 2009,

Note: This page contains sample records for the topic "isotope reactor annual" 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

Annual Reports | Department of Energy  

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

Annual Reports Annual Reports Annual Reports OHA Annual Reports Available for Download January 1, 2013 OHA 2012 ANNUAL REPORT Report on the FY 2011 operations of the Office of Hearings and Appeals (OHA). Here are highlights for the past year: September 30, 2011 OHA 2011 ANNUAL REPORT Report on the FY 2011 operations of the Office of Hearings and Appeals (OHA) September 30, 2010 OHA 2010 ANNUAL REPORT Report on the FY 2010 operations of the Office of Hearings and Appeals (OHA) September 8, 2009 OHA 2009 ANNUAL REPORT Report on the FY 2009 operations of the Office of Hearings and Appeals (OHA) September 30, 2008 OHA 2008 ANNUAL REPORT Report on the FY 2008 operations of the Office of Hearings and Appeals (OHA) September 30, 2007 OHA 2007 ANNUAL REPORT Report on the FY 2007 operations of the Office of Hearings and Appeals

362

Proliferation resistant fuel for pebble bed modular reactors  

SciTech Connect (OSTI)

We show that it is possible to denature the Plutonium produced in Pebble Bed Modular Reactors (PBMR) by doping the nuclear fuel with either 3050 ppm of {sup 237}Np or 2100 ppm of Am vector. A correct choice of these isotopes concentration yields denatured Plutonium with isotopic ratio {sup 238}Pu/Pu {>=} 6%, for the entire fuel burnup cycle. The penalty for introducing these isotopes into the nuclear fuel is a subsequent shortening of the fuel burnup cycle, with respect to a non-doped reference fuel, by 41.2 Full Power Days (FPDs) and 19.9 FPDs, respectively, which correspond to 4070 MWd/ton and 1965 MWd/ton reduction in fuel discharge burnup. (authors)

Ronen, Y.; Aboudy, M.; Regev, D.; Gilad, E. [Dept. of Nuclear Engineering, Ben-Gurion Univ. of the Negev, Beer-Sheva 84105 (Israel)

2012-07-01T23:59:59.000Z

363

Natural Gas Annual, 2004  

Gasoline and Diesel Fuel Update (EIA)

4 4 EIA Home > Natural Gas > Natural Gas Data Publications Natural Gas Annual, 2004 Natural Gas Annual 2004 Release date: December 19, 2005 Next release date: January 2007 The Natural Gas Annual, 2004 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2004. Summary data are presented for each State for 2000 to 2004. The data that appear in the tables of the Natural Gas Annual, 2004 is available as self-extracting executable file or CSV file format. This volume emphasizes information for 2004, although some tables show a five-year history. Please read the file entitled README.V1 for a description and documentation of information included in this file.

364

Petroleum Marketing Annual  

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

5 Entire . The entire report as a single file. PDF 2.9MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights ....

365

Petroleum Marketing Annual 2007  

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

7 Released: August 29, 2008 Petroleum Marketing Annual --- Full report in PDF (1.2 MB) Summary Statistics Summary Statistics Tables PDF 1 Crude Oil Prices PDF TXT 1A Refiner...

366

Petroleum Marketing Annual  

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

9 Entire . The entire report as a single file. PDF 1.2MB . Front Matter . Petroleum Marketing Annual Cover Page, Preface, and Table of Contents PDF . Highlights . Petroleum...

367

Petroleum Marketing Annual 1997  

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

7 Entire . The entire report as a single file. PDF 1.2MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights ....

368

Petroleum Marketing Annual 2008  

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

8 Released: August 27, 2009 Petroleum Marketing Annual --- Full report in PDF (1.2 MB) Summary Statistics Summary Statistics Tables PDF 1 Crude Oil Prices PDF TXT 1A Refiner...

369

Petroleum Marketing Annual  

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

6 Entire . The entire report as a single file. PDF 2.9MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights ....

370

Petroleum Marketing Annual  

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

8 Entire . The entire report as a single file. PDF 1.2MB . Front Matter . Petroleum Marketing Annual Cover Page, Preface, and Table of Contents PDF . Highlights . Petroleum...

371

2009 Annual Report  

SciTech Connect (OSTI)

This annual report includes: a brief overview of Western; some of our major achievements in FY 2009; FY 2009 customer Integrated Resource Planning, or IRP, survey; and financial data.

none,

2009-01-01T23:59:59.000Z

372

2010 Annual Report  

SciTech Connect (OSTI)

This annual report includes: an overview of Western; approaches for future hydropower and transmission service; major achievements in FY 2010; FY 2010 customer Integrated Resource Planning, or IRP, survey; and financial data.

none,

2010-01-01T23:59:59.000Z

373

RAS ANNUAL REPORT 2002:  

Science Journals Connector (OSTI)

......ESO; the PPARC Science Committee funding...replacement. 11. Education Committee The Mary...video tapes, posters or optical equipment...Association for Science Education's annual meeting...good support. Science Year 2001. The......

The RAS Annual General Meeting

2002-10-01T23:59:59.000Z

374

Annual Energy Outlook 2013  

Gasoline and Diesel Fuel Update (EIA)

Mayer Brown Annual Global Energy Conference May 15, 2014 | Houston, TX By Adam Sieminski, EIA Administrator The U.S. has experienced a rapid increase in natural gas and oil...

375

Annual Report Directory2009  

E-Print Network [OSTI]

09 Annual Report #12;Directory2009 Chancellor Rex Williams, BE(Hons) Pro-Chancellor L John Wood-Chancellor Ian Town, MBChB(Otago), DM(Soton) University Registrar Jeff Field, JP, MA, DipJ, Dip

Hickman, Mark

376

Annual Reports - Hanford Site  

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

the 200 East Area April 2014 0 SGW-54165 2012 Groundwater Annual Report August 2013 0 DOERL-2013-22 The Regulatory Basis and Implementation of a Graded Approach to Evaluation...

377

NARUC Annual Meeting  

Broader source: Energy.gov [DOE]

The National Association of Regulatory Utility Commissioneers (NARUC) is hosting its annual meeting in San Fransisco, CA, from Nov. 16-19, 2014. Registration and housing begins Aug. 27. 

378

Isotopic Analysis- Fluid | Open Energy Information  

Open Energy Info (EERE)

Isotopic Analysis- Fluid Isotopic Analysis- Fluid Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotopic Analysis- Fluid Details Activities (61) Areas (32) Regions (6) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Fluid Lab Analysis Parent Exploration Technique: Fluid Lab Analysis Information Provided by Technique Lithology: Water rock interaction Stratigraphic/Structural: Hydrological: Origin of hydrothermal fluids; Mixing of hydrothermal fluids Thermal: Isotopic ratios can be used to characterize and locate subsurface thermal anomalies. Dictionary.png Isotopic Analysis- Fluid: Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in

379

Isotope Development & Production | Nuclear Science | ORNL  

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

of the "Calutrons" (electromagnetic enrichment devices) were converted by ORNL to the separation and enrichment of stable isotopes and some actinide isotopes. Until 1998 when...

380

Natural gas annual 1994  

SciTech Connect (OSTI)

The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1994 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1990 to 1994 for each Census Division and each State. Annual historical data are shown at the national level.

NONE

1995-11-17T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Natural gas annual 1995  

SciTech Connect (OSTI)

The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1995 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1991 to 1995 for each Census Division and each State. Annual historical data are shown at the national level.

NONE

1996-11-01T23:59:59.000Z

382

Natural Gas Annual 2007  

Gasoline and Diesel Fuel Update (EIA)

7 7 Released: January 28, 2009 The Natural Gas Annual 2007 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2007. Summary data are presented for each State for 2003 to 2007. The Natural Gas Annual 2007 Summary Highlights provides an overview of the supply and disposition of natural gas in 2007 and is intended as a supplement to the Natural Gas Annual 2007. Natural Gas Annual --- Full report in PDF (5 MB) Special Files --- All CSV files contained in a self-extracting executable file. Respondent/Company Level Natural Gas Data Files Annual Natural and Supplemental Gas Supply and Disposition Company level data (1996 to 2007) as reported on Form EIA-176 are provided in the EIA-176 Query System and selected data files. EIA-191A Field Level Underground Natural Gas Storage Data: Detailed annual data (2005 to 2007) of storage field capacity, field type, and maximum deliverability as of December 31st of the report year, as reported by operators of all U.S. underground natural gas storage fields.

383

Natural Gas Annual 2009  

Gasoline and Diesel Fuel Update (EIA)

9 9 Released: December 28, 2010 The Natural Gas Annual 2009 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2009. Summary data are presented for each State for 2005 to 2009. The Natural Gas Annual 2009 Summary Highlights provides an overview of the supply and disposition of natural gas in 2009 and is intended as a supplement to the Natural Gas Annual 2009. Natural Gas Annual --- Full report in PDF (5 MB) Special Files --- All CSV files contained in a self-extracting executable file. Respondent/Company Level Natural Gas Data Files Annual Natural and Supplemental Gas Supply and Disposition Company level data (1996 to 2009) as reported on Form EIA-176 are provided in the EIA-176 Query System and selected data files. EIA-191A Field Level Underground Natural Gas Storage Data: Detailed annual data (2005 to 2009) of storage field capacity, field type, and maximum deliverability as of December 31st of the report year, as reported by operators of all U.S. underground natural gas storage fields.

384

Natural Gas Annual 2008  

Gasoline and Diesel Fuel Update (EIA)

8 8 Released: March 2, 2010 The Natural Gas Annual 2008 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2008. Summary data are presented for each State for 2004 to 2008. The Natural Gas Annual 2008 Summary Highlights provides an overview of the supply and disposition of natural gas in 2008 and is intended as a supplement to the Natural Gas Annual 2008. Natural Gas Annual --- Full report in PDF (5 MB) Special Files --- All CSV files contained in a self-extracting executable file. Respondent/Company Level Natural Gas Data Files Annual Natural and Supplemental Gas Supply and Disposition Company level data (1996 to 2008) as reported on Form EIA-176 are provided in the EIA-176 Query System and selected data files. EIA-191A Field Level Underground Natural Gas Storage Data: Detailed annual data (2005 to 2008) of storage field capacity, field type, and maximum deliverability as of December 31st of the report year, as reported by operators of all U.S. underground natural gas storage fields.

385

annual maximum extent: Topics by E-print Network  

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

Report 2010Annual Report Engineering Websites Summary: 2010Annual Report 2010Annual Report 2010Annual Report 2010 Annual Report Technology Transfer Office Assistant Vice...

386

Generation -IV Reactor Concepts  

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

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

387

Implications of Plutonium isotopic separation on closed fuel cycles and repository design  

SciTech Connect (OSTI)

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation. This would have large impacts on LWR closed fuel cycles and waste management. If Pu-240 is removed before recycling plutonium as mixed oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, Americium, and Curium. Pu-240 is a fertile material and thus can be replaced by U-238. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Eliminating fertile Pu-240 and Pu-242 reduces the plutonium content in MOX fuel and simplifies fabrication. Reducing production of Pu-241 reduces production of Am-241 - the primary heat generator in spent nuclear fuels after several decades. Reducing heat generating Am-241 would reduce repository cost and waste toxicity. Avoiding Am- 241 avoids its decay product Np-237, a nuclide that partly controls long-term oxidizing repository performance. Most of these benefits also apply to LWR plutonium recycled into fast reactors. There are benefits for plutonium isotopic separation in fast reactor fuel cycles (particularly removal of Pu-242) but the benefits are less. (author)

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 20129 (United States)

2013-07-01T23:59:59.000Z

388

Abstract Variation in the carbon isotopic composition of ecosystem respiration (13CR) was studied for 3 years  

E-Print Network [OSTI]

coast to the eastern side of the Cascade Mountains (a 250-km transect). Mean annual precipita- tion of gas exchange and associated changes in photosynthetic carbon isotope discrimination. Recent freeze). The extent to which and 13CR vary could po- tentially alter conclusions about the timing and nature

Ehleringer, Jim

389

ISOTOPE FRACTIONATION Isotopes are atoms whose nuclei contain the same number of protons but a different number of neutrons. The  

E-Print Network [OSTI]

the most abundant isotope appears in the denominator: b R = b E / a E (stable boron isotopes = , [ ] [ ] [ ] [ ]OOCOOC2 OOCOOC2 O 16181616 16181818 CO 18 2 + + = . The isotopic composition, , of a sample, determined____________________________ ISOTOPE FRACTIONATION ____________________________ Isotopes are atoms

Zeebe, Richard E.

390

Annual DOE Occupational Radiation Exposure Reports | Department...  

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

Annual DOE Occupational Radiation Exposure Reports Annual DOE Occupational Radiation Exposure Reports September 24, 2013 Annual DOE Occupational Radiation Exposure | 2012 Report...

391

Annual Progress Reports | Department of Energy  

Energy Savers [EERE]

Annual Progress Reports Annual Progress Reports This page contains annual progress reports for the Fuel Cell Technologies Office and the Transportation Fuel Cell Power...

392

Geothermal Technologies Office Annual Report 2012 | Department...  

Office of Environmental Management (EM)

Geothermal Technologies Office Annual Report 2012 Geothermal Technologies Office Annual Report 2012 This annual report for the U.S. Department of Energys Geothermal Technologies...

393

Stanford Geothermal Workshop 2012 Annual Meeting | Department...  

Energy Savers [EERE]

2012 Annual Meeting Stanford Geothermal Workshop 2012 Annual Meeting Presentation slides for the Stanford Geothermal Workshop Annual Meeting presentation by Doug Hollett,...

394

Waste Processing Annual Technology Development Report 2007 |...  

Office of Environmental Management (EM)

Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007...

395

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

396

Improved vortex reactor system  

DOE Patents [OSTI]

An improved vortex reactor system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor. 12 figs.

Diebold, J.P.; Scahill, J.W.

1995-05-09T23:59:59.000Z

397

Uranium Marketing Annual Report -  

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

8. Contracts signed in 2013 by owners and operators of U.S. civilian nuclear power reactors by contract type thousand pounds U3O8 equivalent; dollars per pound U3O8 equivalent...

398

Uranium Marketing Annual Report -  

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

1. Foreign sales of uranium from U.S. suppliers and owners and operators of U.S. civilian nuclear power reactors by origin and delivery year, 2009-13 thousands pounds U3O8...

399

Uranium Marketing Annual Report  

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

a. Uranium purchased by owners and operators of U.S. civilian nuclear power reactors, 1994-2013 million pounds U3O8 equivalent Delivery year Total purchased Purchased from U.S....

400

Uranium Marketing Annual Report -  

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

9. Contracted purchases of uranium by owners and operators of U.S. civilian nuclear power reactors, signed in 2013, by delivery year, 2014-23 thousand pounds U3O8 equivalent Year...

Note: This page contains sample records for the topic "isotope reactor annual" 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

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

the public. 15 These values represent the energy obtained from uranium when it is used in light water reactors. The total energy content of uranium is much larger, but alternative...

402

Annual Energy Outlook 2012  

Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

waste coal. 2 These values represent the energy obtained from uranium when it is used in light water reactors. The total energy content of uranium is much larger, but alternative...

403

Combined Fiscal Year (FY) 2014 Annual Performance Results and FYs 2015 and 2016 Annual Performance Plan  

Broader source: Energy.gov [DOE]

Combined Fiscal Year (FY) 2014 Annual Performance Results and FYs 2015 and 2016 Annual Performance Plan

404

AEC Pushes Fusion Reactors  

Science Journals Connector (OSTI)

AEC Pushes Fusion Reactors ... Project Sherwood, as the study program is called, began in 1951-52 soon after the first successful thermonuclear explosion in the Pacific. ...

1955-10-10T23:59:59.000Z

405

Tokamak reactor first wall  

DOE Patents [OSTI]

This invention relates to an improved first wall construction for a tokamak fusion reactor vessel, or other vessels subjected to similar pressure and thermal stresses.

Creedon, R.L.; Levine, H.E.; Wong, C.; Battaglia, J.

1984-11-20T23:59:59.000Z

406

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

407

Natural Gas Annual, 2003  

Gasoline and Diesel Fuel Update (EIA)

3 3 EIA Home > Natural Gas > Natural Gas Data Publications Natural Gas Annual, 2003 Natural Gas Annual 2003 Release date: December 22, 2004 Next release date: January 2006 The Natural Gas Annual, 2003 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2003. Summary data are presented for each State for 1999 to 2003. “The Natural Gas Industry and Markets in 2003” is a special report that provides an overview of the supply and disposition of natural gas in 2003 and is intended as a supplement to the Natural Gas Annual 2003. The data that appear in the tables of the Natural Gas Annual, 2003 is available as self-extracting executable file or CSV file format. This volume emphasizes information for 2003, although some tables show a five-year history. Please read the file entitled README.V1 for a description and documentation of information included in this file.

408

Natural Gas Annual, 2002  

Gasoline and Diesel Fuel Update (EIA)

2 2 EIA Home > Natural Gas > Natural Gas Data Publications Natural Gas Annual, 2002 Natural Gas Annual 2002 Release date: January 29, 2004 Next release date: January 2005 The Natural Gas Annual, 2002 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2002. Summary data are presented for each State for 1998 to 2002. “The Natural Gas Industry and Markets in 2002” is a special report that provides an overview of the supply and disposition of natural gas in 2002 and is intended as a supplement to the Natural Gas Annual 2002. Changes to data sources for this Natural Gas Annual, as a result of ongoing data quality efforts, have resulted in revisions to several data series. Production volumes have been revised for the Federal offshore and several States. Several data series based on the Form EIA-176, including deliveries to end-users in several States, were also revised. Additionally, revisions have been made to include updates to the electric power and vehicle fuel end-use sectors.

409

Benchmark Evaluation of the NRAD Reactor LEU Core Startup Measurements  

SciTech Connect (OSTI)

The Neutron Radiography (NRAD) reactor is a 250-kW TRIGA-(Training, Research, Isotope Production, General Atomics)-conversion-type reactor at the Idaho National Laboratory; it is primarily used for neutron radiography analysis of irradiated and unirradiated fuels and materials. The NRAD reactor was converted from HEU to LEU fuel with 60 fuel elements and brought critical on March 31, 2010. This configuration of the NRAD reactor has been evaluated as an acceptable benchmark experiment and is available in the 2011 editions of the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook) and the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). Significant effort went into precisely characterizing all aspects of the reactor core dimensions and material properties; detailed analyses of reactor parameters minimized experimental uncertainties. The largest contributors to the total benchmark uncertainty were the 234U, 236U, Er, and Hf content in the fuel; the manganese content in the stainless steel cladding; and the unknown level of water saturation in the graphite reflector blocks. A simplified benchmark model of the NRAD reactor was prepared with a keff of 1.0012 {+-} 0.0029 (1s). Monte Carlo calculations with MCNP5 and KENO-VI and various neutron cross section libraries were performed and compared with the benchmark eigenvalue for the 60-fuel-element core configuration; all calculated eigenvalues are between 0.3 and 0.8% greater than the benchmark value. Benchmark evaluations of the NRAD reactor are beneficial in understanding biases and uncertainties affecting criticality safety analyses of storage, handling, or transportation applications with LEU-Er-Zr-H fuel.

J. D. Bess; T. L. Maddock; M. A. Marshall

2011-09-01T23:59:59.000Z

410

STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 2009/109/109/109/10 Annual Delivery Report  

E-Print Network [OSTI]

STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 2009/109/109/109/10 0 Annual Delivery Report 2009/10 August 2010 #12;STFC Annual Delivery Plan Report 200STFC Annual Delivery Plan Report 200STFC Annual Delivery

411

Apparatus and process for separating hydrogen isotopes  

DOE Patents [OSTI]

The apparatus and process for separating hydrogen isotopes is provided using dual columns, each column having an opposite hydrogen isotopic effect such that when a hydrogen isotope mixture feedstock is cycled between the two respective columns, two different hydrogen isotopes are separated from the feedstock.

Heung, Leung K; Sessions, Henry T; Xiao, Xin

2013-06-25T23:59:59.000Z

412

Annual Report Curtin University of Technology Annual Report 2006  

E-Print Network [OSTI]

Annual Report 2006 #12;#12;Curtin University of Technology Annual Report 2006 Chancellor's Foreword ........................................................................................................................ 2 Vice-Chancellor's Report ................................................................................................... 25 Report on Operations 28 Governance of the University

413

Annual Report GreenTouch 20102011 Annual Report  

E-Print Network [OSTI]

2010­2011 Annual Report #12;1 GreenTouch 2010­2011 Annual Report Contents Chairman's Letter............................................................ 30 Service Energy Aware Sustainable Optical Networks (SEASON............................................................................................ 43 Beyond Cellular Green Generation (BCG2

Lefèvre, Laurent

414

Oklo reactors and implications for nuclear science  

E-Print Network [OSTI]

We summarize the nuclear physics interests in the Oklo natural nuclear reactors, focusing particularly on developments over the past two decades. Modeling of the reactors has become increasingly sophisticated, employing Monte Carlo simulations with realistic geometries and materials that can generate both the thermal and epithermal fractions. The water content and the temperatures of the reactors have been uncertain parameters. We discuss recent work pointing to lower temperatures than earlier assumed. Nuclear cross sections are input to all Oklo modeling and we discuss a parameter, the $^{175}$Lu ground state cross section for thermal neutron capture leading to the isomer $^{176\\mathrm{m}}$ Lu, that warrants further investigation. Studies of the time dependence of dimensionless fundamental constants have been a driver for much of the recent work on Oklo. We critically review neutron resonance energy shifts and their dependence on the fine structure constant $\\alpha$ and the ratio $X_q=m_q/\\Lambda$ (where $m_q$ is the average of the $u$ and $d$ current quark masses and $\\Lambda$ is the mass scale of quantum chromodynamics). We suggest a formula for the combined sensitivity to $\\alpha$ and $X_q$ that exhibits the dependence on proton number $Z$ and mass number $A$, potentially allowing quantum electrodynamic and quantum chromodynamic effects to be disentangled if a broader range of isotopic abundance data becomes available.

E. D. Davis; C. R. Gould; E. I. Sharapov

2014-04-19T23:59:59.000Z

415

Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes  

SciTech Connect (OSTI)

The US Department of Energy (DOE) plans to establish a medical isotope project that would ensure a reliable domestic supply of molybdenum-99 ({sup 99}Mo) and related medical isotopes (Iodine-125, Iodine-131, and Xenon-133). The Department`s plan for production will modify the Annular Core Research Reactor (ACRR) and associated hot cell facility at Sandia National Laboratories (SNL)/New Mexico and the Chemistry and Metallurgy Research facility at Los Alamos National Laboratory (LANL). Transportation activities associated with such production is discussed.

Trennel, A.J.

1997-11-01T23:59:59.000Z

416

NEUTRON RADIOGRAPHY (NRAD) REACTOR 64-ELEMENT CORE UPGRADE  

SciTech Connect (OSTI)

The neutron radiography (NRAD) reactor is a 250 kW TRIGA (registered) (Training, Research, Isotopes, General Atomics) Mark II , tank-type research reactor currently located in the basement, below the main hot cell, of the Hot Fuel Examination Facility (HFEF) at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components. The interim critical configuration developed during the core upgrade, which contains only 62 fuel elements, has been evaluated as an acceptable benchmark experiment. The final 64-fuel-element operational core configuration of the NRAD LEU TRIGA reactor has also been evaluated as an acceptable benchmark experiment. Calculated eigenvalues differ significantly (approximately +/-1%) from the benchmark eigenvalue and have demonstrated sensitivity to the thermal scattering treatment of hydrogen in the U-Er-Zr-H fuel.

John D. Bess

2014-03-01T23:59:59.000Z

417

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....

418

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

419

Risk management at the Oak Ridge National Laboratory research reactors  

SciTech Connect (OSTI)

In November of 1986, the High Flux Isotope Reactor (HFIR) was shut down by Oak Ridge National Laboratory (ORNL) due to a concern regarding embrittlement of the reactor vessel. A massive review effort was undertaken by ORNL and the Department of Energy (DOE). This review resulted in an extensive list of analyses and design modifications to be completed before restart could take place. The review also focused on the improvement of management practices including implementation of several of the Institute of Nuclear Power Operations (INPO) requirements. One of the early items identified was the need to perform a Probabilistic Risk Assessment (PRA) on the reactor. It was decided by ORNL management that this PRA would not be just an exercise to assess the ``bottom`` line in order to restart, but would be used to improve the overall safety of the reactor, especially since resources (both manpower and dollars) were severely limited. The PRA would become a basic safety tool to be used instead of a more standard deterministic approach to safety used in commercial reactor power plants. This approach was further reinforced, because the reactor was nearly 25 years old at this time, and the design standards and regulations had changed significantly since the original design, and many of the safety issues could not be addressed by compliance to codes and standards.

Flanagan, G.F.; Linn, M.A.; Proctor, L.D.; Cook, D.H.

1994-12-31T23:59:59.000Z

420

Isotopic Analysis- Rock | Open Energy Information  

Open Energy Info (EERE)

Isotopic Analysis- Rock Isotopic Analysis- Rock Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Isotopic Analysis- Rock Details Activities (13) Areas (11) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Rock Lab Analysis Parent Exploration Technique: Rock Lab Analysis Information Provided by Technique Lithology: Water rock interaction Stratigraphic/Structural: Hydrological: Thermal: Dictionary.png Isotopic Analysis- Rock: Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable.

Note: This page contains sample records for the topic "isotope reactor annual" 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

EIS-0380: Annual Mitigation Action Plan Annual Report  

Broader source: Energy.gov [DOE]

Los Alamos National Laboratory Site-Wide Environmental Impact Statement Fiscal Year 2013 Mitigation Action Plan Annual Report

422

Annual Coal Report 2012  

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

Annual Coal Report 2012 Annual Coal Report 2012 December 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. iii U.S. Energy Information Administration | Annual Coal Report 2012 Contacts This publication was prepared by the U.S. Energy Information Administration (EIA). General information about the data in this report can be obtained from:

423

Natural Gas Annual, 2001  

Gasoline and Diesel Fuel Update (EIA)

1 1 EIA Home > Natural Gas > Natural Gas Data Publications Natural Gas Annual, 2001 The Natural Gas Annual, 2001 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 2001. Summary data are presented for each State for 1997 to 2001. The data that appear in the tables of the Natural Gas Annual, 2001 are available as self-extracting executable files in ASCII TXT or CSV file format. This volume emphasizes information for 2001, although some tables show a five-year history. Please read the file entitled README.V1 for a description and documentation of information included in this file. Also available are files containing the following data: Summary Statistics - Natural Gas in the United States, 1997-2001 (Table 1) ASCII TXT, and Natural Gas Supply and Disposition by State, 2001 (Table 2) ASCII TXT.

424

Annual2.vp  

Gasoline and Diesel Fuel Update (EIA)

9 9 October 2000 Energy Information Administration Office of Oil and Gas U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy of the Department of Energy or any other organization. DOE/EIA-E-0110(99) Distribution Category/UC-960 ii Energy Information Administration / Historical Natural Gas Annual 1930 Through 1999 Contacts The Historical Natural Gas Annual is prepared by the Energy Information Administration, Office of Oil and Gas, Natural Gas Division, under the direction of Joan E. Heinkel. General questions and comments concerning the contents of the Historical Natural Gas Annual may be obtained from the National Energy Information

425

Annual Energy Review 1995  

Gasoline and Diesel Fuel Update (EIA)

4(95) 4(95) Distribution Category UC-950 Annual Energy Review 1995 July 1996 Energy Information Administration Office of Energy Markets and End Use U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. Annual Energy Review 1995 The Annual Energy Review (AER) presents the Energy Information Ad- ministration's historical energy statistics. For most series, statistics are given for every year from 1949 through 1995. The statistics, expressed in either physical units or British thermal units, cover all major energy activities, including consumption, production, trade,

426

Annual2.vp  

Gasoline and Diesel Fuel Update (EIA)

8 8 November 1999 Energy Information Administration Office of Oil and Gas U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy of the Department of Energy or any other organization. DOE/EIA-E-0110(98) Distribution Category/UC-960 ii Energy Information Administration / Historical Natural Gas Annual 1930 Through 1998 Contacts The Historical Natural Gas Annual is prepared by the En- ergy Information Administration, Office of Oil and Gas, Natural Gas Division, under the direction of Joan E. Heinkel. General questions and comments concerning the contents of the Historical Natural Gas Annual may be obtained from the National Energy Information

427

Petroleum Marketing Annual 2009  

Gasoline and Diesel Fuel Update (EIA)

Petroleum Marketing Annual 2009 Petroleum Marketing Annual 2009 Released: August 6, 2010 Monthly price and volume statistics on crude oil and petroleum products at a national, regional and state level. Notice: Changes to EIA Petroleum Data Program Petroleum Marketing Annual --- Full report in PDF (1.2 MB) Previous Issues --- Previous reports are available on the historical page. Summary Statistics Summary Statistics Tables PDF 1 Crude Oil Prices PDF TXT 1A Refiner Acquisition Cost of Crude Oil by PAD Districts HTML PDF TXT 2 U.S. Refiner Prices of Petroleum Products to End Users HTML PDF TXT 3 U.S. Refiner Volumes of Petroleum Products to End Users PDF TXT Motor Gasoline to End Users HTML Residual Fuel Oil and No. 4 Fuel to End Users HTML Other Petroleum Products to End Users HTML

428

ANNUAL FUNDING NOTICE for  

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

HRD-BEN-2012-0038 HRD-BEN-2012-0038 Date: April 30, 2012 To: All Plan Participants From: SRNS Benefits Administration Re: Savannah River Nuclear Solutions, LLC Multiple Employer Pension Plan Funding Notices Attached are three pension plan notices of which the wording is very closely regulated by the federal government. Therefore, we are providing a quick overview of the notices here. 2011 Annual Funding Notice: The government previously required the distribution of an abbreviated form of this information and called it the Summary Annual Report (SAR). You may have seen SARs from previous years posted on the SRS Intranet "InSite". The enhanced version of that SAR is called the Annual Funding Notice. This particular notice covers the plan year 2011 and is issued after the

429

Handbook of Reactor Physics  

Science Journals Connector (OSTI)

... THIS handbook is one volume in a series sponsored by the United States Atomic Energy Commission with ... data and reference information in the field of reactors. The volume is devoted to reactor physics and radiation shielding, the latter subject occupying approximately a quarter of the book.

PETER W. MUMMERY

1956-08-25T23:59:59.000Z

430

Fast reactor safety  

Science Journals Connector (OSTI)

... SIR, - In his article on fast reactor safety (26 July, page 270) Norman Dombey claims to introduce to non-specialists ... , page 270) Norman Dombey claims to introduce to non-specialists some features of fast reactors that are not available outside the technical literature. The non-specialist would do well ...

R.D. SMITH

1979-08-23T23:59:59.000Z

431

Instrumentation of Nuclear Reactors  

Science Journals Connector (OSTI)

... s Lecture Theatre on January 8, a symposium of papers on the instrumentation of nuclear reactors was organized, at which about five hundred members and visitors attended, including guests from ... the Institution, took the chair and introduced Sir John Cockcroft, whose lecture on "Nuclear Reactors and their Applications" provided a general background for the three specialized papers which followed. ...

1953-03-07T23:59:59.000Z

432

ANNUAL FUNDING NOTICE for  

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

HRD-BEN-2013-0029 HRD-BEN-2013-0029 Date: April 30, 2013 To: All Plan Participants From: SRNS Benefits Administration Re: Savannah River Nuclear Solutions, LLC Multiple Employer Pension Plan Funding Notices Attached is the pension plan notice of which the wording is very closely regulated by the federal government. Therefore, we are providing a quick overview of the notice here. 2012 Annual Funding Notice: The government previously required the distribution of an abbreviated form of this information and called it the Summary Annual Report (SAR). You may have seen SARs from previous years posted on the SRS Intranet "InSite". The enhanced version of that

433

Natural gas annual 1997  

SciTech Connect (OSTI)

The Natural Gas Annual provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and educational institutions. The 1997 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production to its end use. This is followed by tables summarizing natural gas supply and disposition from 1993 to 1997 for each Census Division and each State. Annual historical data are shown at the national level. 27 figs., 109 tabs.

NONE

1998-10-01T23:59:59.000Z

434

2007 Annual Peer Review  

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

2007 Annual Peer Review 2007 Annual Peer Review September 27, 2007 San Francisco, California Welcoming Remarks Imre Gyuk US Dept. of Energy DOE / ESS Program Overview (View .pdf) John Boyes Sandia National Laboratories PRESENTATIONS\ ECONOMICS - BENEFIT STUDIES Evaluating Value Propositions for Four Modular Electricity Storage Demonstrations in California (View .pdf) Jim Eyer (Distributed Utility Assoc.) Update on Benefit and Cost Comparison of Modular Energy Storage Technologies for Four Viable Value Propositions (View .pdf) Susan Schoenung (Longitude 122 West, Inc.) ECONOMICS - ENVIRONMENT BENEFITS STUDIES Emissions from Traditional & Flywheel Plants for Regulation Services (View .pdf) Rick Fioravanti (KEMA, Inc.) UTILITY & COMMERCIAL APPLICATIONS OF ADVANCED ENERGY STORAGE SYSTEMS

435

Vehicle Technologies Office: Annual Progress Reports  

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

Annual Progress Reports Annual Progress Reports to someone by E-mail Share Vehicle Technologies Office: Annual Progress Reports on Facebook Tweet about Vehicle Technologies Office: Annual Progress Reports on Twitter Bookmark Vehicle Technologies Office: Annual Progress Reports on Google Bookmark Vehicle Technologies Office: Annual Progress Reports on Delicious Rank Vehicle Technologies Office: Annual Progress Reports on Digg Find More places to share Vehicle Technologies Office: Annual Progress Reports on AddThis.com... Publications Key Publications Plans & Roadmaps Partnership Documents Annual Progress Reports Success Stories Conferences Proceedings Newsletters Analysis Software Tools Awards & Patents Glossary Annual Progress Reports 2013 DOE Vehicle Technologies Office Annual Merit Review

436

Novel hybrid isotope separation scheme and apparatus  

DOE Patents [OSTI]

A method is described for yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which the specific isotope is to be isolated, radiating the gas with frequencies characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photoionization reaction of the desired isotope, and collecting the specific isotope ion by suitable ion collection means. 3 figures.

Maya, J.

1991-06-18T23:59:59.000Z

437

Novel hybrid isotope separation scheme and apparatus  

DOE Patents [OSTI]

A method of yielding selectively a desired enrichment in a specific isotope including the steps of inputting into a spinning chamber a gas from which the specific isotope is to be isolated, radiating the gas with frequencies characteristic of the absorption of a particular isotope of the atomic or molecular gas, thereby inducing a photoionization reaction of the desired isotope, and collecting the specific isotope ion by suitable ion collection means.

Maya, Jakob (Brookline, MA)

1991-01-01T23:59:59.000Z

438

2013 Uranium Marketing Annual Report  

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

Industry Annual, Tables 28, 29, 30 and 31. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". Notes: Totals may not equal sum of components because of independent...

439

2013 Uranium Marketing Annual Report  

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

Industry Annual, Tables 10, 11 and 16. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". dollars per pound U 3 O 8 equivalent dollars per pound U 3 O 8...

440

2013 Uranium Marketing Annual Report  

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

Industry Annual, Tables 28, 29, 30 and 31. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". million pounds U 3 O 8 equivalent million pounds U 3 O 8 equivalent...

Note: This page contains sample records for the topic "isotope reactor annual" 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

2013 Uranium Marketing Annual Report  

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

Industry Annual, Tables 22, 23, 25, and 27. 2003-13-Form EIA-858, "Uranium Marketing Annual Survey". - No data reported. 0 10 20 30 40 50 60 70 1994 1995 1996 1997...

442

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

443

2011 Quality Council Annual Report  

Broader source: Energy.gov [DOE]

DEPARTMENT OF ENERGY QUALITY COUNCIL ANNUAL REPORT For Calendar Year 2011 Office of Health Safety and Security

444

NCAI 71st Annual Convention  

Broader source: Energy.gov [DOE]

Save the date for the National Congress of American Indians (NCAI) 71st Annual Convention at the Hyatt Regency Atlanta.

445

OHA 2012 ANNUAL REPORT DRAFT....  

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

Annual Report Annual Report O H A ffice of earin s ppeals & g Doe/hg-0024 U.S. DEPARTMENT OF ENERGY Office of Hearings Appeals & FY 2012 Annual Report Message from the Director . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ntroduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I. Areas of JURISDICTION II. Working with Others . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V. General Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 5 A. Personnel Security B. Whistleblower C. 11 D. 14 17 18 I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

446

Annual Report CMS Spring Assembly  

E-Print Network [OSTI]

Annual Report 2007-2008 CMS Spring Assembly & Length of Service Awards March 9, 2012 #12;Annual Report 2007-2008 News & Events: Alumni David Mearns (CMS MS `86) Selected as co-recipient of USF's Distinguished Alumni Award, Fall 2011 #12;Annual Report 2007-2008 News & Events: Faculty Dr. Robert Byrne

Meyers, Steven D.

447

Oak Ridge Reservation Annual Site  

E-Print Network [OSTI]

Oak Ridge Reservation Annual Site Environmental Report DOE/ORO/2445 2012 #12;Cover Image Jeff Riggs Logistical Services Design Creative Media Communications Oak Ridge National Laboratory Oak Ridge Reservation Annual Site Environmental Report 2012 #12;DOE/ORO/2445 Oak Ridge Reservation Annual Site Environmental

Pennycook, Steve

448

Oak Ridge Reservation Annual Site  

E-Print Network [OSTI]

Oak Ridge Reservation Annual Site Environmental Report DOE/ORO-2473 2013 #12;Cover Image & Design Creative Media Communications Oak Ridge National Laboratory Oak Ridge Reservation Annual Site Environmental Report 2013 #12;DOE/ORO/2473 Oak Ridge Reservation Annual Site Environmental Report for 2013 on the World

Pennycook, Steve

449

Ethics Center Annual Report III  

E-Print Network [OSTI]

#12;Ethics Center Annual Report III 2012-2013 TEXAS TECH UNIVERSITY #12;#12;TEXAS TECH UNIVERSITY August 31, 2013 Prepared by the TTU Ethics Center Annual Report III 2012-2013 #12;1 AnnualReportIII|8 proposed a university ethics center to provide the campus with ethics education resources. Since its

Rock, Chris

450

Annual Report University of Lethbridge  

E-Print Network [OSTI]

Annual Report 2012-13 University of Lethbridge #12;i University of Lethbridge 2012-13 Annual Report ACCOUNTABILITY STATEMENT The University of Lethbridge Annual Report for the year ended March 31, 2013, or fiscal implications of which we are aware have been considered in preparing this report. Original signed

Morris, Joy

451

Data Management Group Annual Report  

E-Print Network [OSTI]

Data Management Group Annual Report 1997 #12;Data Management Group Annual Report 1997 A co-operative project that is jointly funded by members of the Toronto Area Transportation Planning Data Collection: (416) 978-3941 #12;Data Management Group 1997 Annual Report Table of Contents 1 INTRODUCTION

Toronto, University of

452

Role of organic matter in the Proterozoic Oklo natural fission reactors, Gabon, Africa  

SciTech Connect (OSTI)

Of the sixteen known Oklo and the Bangombe natural fission reactors (hydrothermally altered elastic sedimentary rocks that contain abundant uraninite and authigenic clay minerals), reactors 1 to 6 at Oklo contain only traces of organic matter, but the others are rich in organic substances. Reactors 7 to 9 are the subjects of this study. These organic-rich reactors may serve as time-tested analogues for anthropogenic nuclear-waste containment strategies. Organic matter helped to concentrate quantities of uranium sufficient to initiate the nuclear chain reactions. Liquid bitumen was generated from organic matter by hydrothermal reactions during nuclear criticality. The bitumen soon became a solid, consisting of polycyclic aromatic hydrocarbons and an intimate mixture of cryptocrystalline graphite, which enclosed and immobilized uraninite and the fission-generated isotopes entrapped in uraninite. This mechanism prevented major loss of uranium and fission products from the natural nuclear reactors for 1.2 b.y. 24 refs., 4 figs.

Nagy, B.; Rigali, M.J. [Univ. of Arizona, Tucson (United States)] [Univ. of Arizona, Tucson (United States); Gauthier-Lafaye, F. [Centre de Geochemie de la Surface, Strasbourg (France)] [Centre de Geochemie de la Surface, Strasbourg (France); Holliger, P. [Centre d`Etudes Nucleaires de Cadarache (France)] [Centre d`Etudes Nucleaires de Cadarache (France); Mossman, D.J. [Mount Allison Univ., Sackville, New Brunswick (Canada)] [Mount Allison Univ., Sackville, New Brunswick (Canada); Leventhal, J.S. [Geological Survey, Denver, CO (United States)] [Geological Survey, Denver, CO (United States)

1993-07-01T23:59:59.000Z

453

Neutronic Study of Slightly Modified Water Reactors and Application to Transition Scenarios  

SciTech Connect (OSTI)

In this paper we have studied slightly modified water reactors and their applications to transition scenarios. The PWR and CANDU reactors have been considered. New fuels based on Thorium have been tested: Thorium/Plutonium and Thorium/Uranium- 233, with different fissile isotope contents. Changes in the geometry of the assemblies were also explored to modify the moderation ratio, and consequently the neutron flux spectrum. A core equivalent assembly methodology was introduced as an exploratory approach and to reduce the computation time. Several basic safety analyses were also performed. We have finally developed a new scenario code, named OSCAR (Optimized Scenario Code for Advanced Reactors), to study the efficiency of these modified reactors in transition to Gen IV reactors or in symbiotic fleet. (authors)

Chambon, Richard; Guillemin, Perrine; Nuttin, Alexis; Bidaud, A. [LPSC, Universite Joseph Fourier Grenoble 1, CNRS/IN2P3, Institut National Polytechnique de Grenoble 53 Av. Des Martyrs, 38000 Grenoble (France); Capellan, N.; David, S.; Meplan, O.; Wilson, J. [Institut de Physique Nucleaire - IPN, 15 rue Georges Clemenceau 91406 Orsay (France)

2007-07-01T23:59:59.000Z

454

2014 Annual AFN Convention  

Broader source: Energy.gov [DOE]

The AFN Convention is the largest representative annual gathering in the United States of any Native peoples. In addition to the memorable keynote speeches, the expert panels and special reports, the Convention features several evenings of cultural performances known as Quyana Alaska.

455

Uranium industry annual 1998  

SciTech Connect (OSTI)

The Uranium Industry Annual 1998 (UIA 1998) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. It contains data for the period 1989 through 2008 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data provides a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Data on uranium raw materials activities for 1989 through 1998, including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment, are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2008, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, and uranium inventories, are shown in Chapter 2. The methodology used in the 1998 survey, including data edit and analysis, is described in Appendix A. The methodologies for estimation of resources and reserves are described in Appendix B. A list of respondents to the ``Uranium Industry Annual Survey`` is provided in Appendix C. The Form EIA-858 ``Uranium Industry Annual Survey`` is shown in Appendix D. For the readers convenience, metric versions of selected tables from Chapters 1 and 2 are presented in Appendix E along with the standard conversion factors used. A glossary of technical terms is at the end of the report. 24 figs., 56 tabs.

NONE

1999-04-22T23:59:59.000Z

456

ENVIRONMENT 2006 Annual Report  

E-Print Network [OSTI]

ENVIRONMENT 2006 Annual Report IBM AND THE #12;Table of Contents Global Environmental Management and Management 13 International Performance Measures 13 Water Conservation 15 Climate Protection 16 on environmental protection in 1971. The policy is supported by a comprehensive global environmental management

457

TRANSPORTATION Annual Report  

E-Print Network [OSTI]

2003 CENTER FOR TRANSPORTATION STUDIES Annual Report #12;Center for Transportation Studies University of Minnesota 200 Transportation and Safety Building 511 Washington Avenue S.E. Minneapolis, MN publication is a report of transportation research, education, and outreach activities for the period July

Minnesota, University of

458

Annual Report Directory2010  

E-Print Network [OSTI]

Annual Report 10 #12;Directory2010 Chancellor Rex Williams, BE(Hons) Pro-Chancellor L John Wood(Soton) University Registrar Jeff Field, JP, MA, DipJ, DipTColl(ChCh.TColl.), DipTchg(DeptEd), APR, MFINZ Assistant

Hickman, Mark

459

Annual Report. Directory2011  

E-Print Network [OSTI]

UC2011 Annual Report. #12;Directory2011 Chancellor Rex Williams, BE(Hons) Pro-Chancellor L John(Soton) University Registrar Jeff Field, JP, MA, DipJ, DipTColl(ChCh.TColl.), DipTchg(DeptEd), APR, MFINZ Assistant

Hickman, Mark

460

International Energy Annual, 1992  

SciTech Connect (OSTI)

This report is prepared annually and presents the latest information and trends on world energy production and consumption for petroleum, natural gas, coal, and electricity. Trade and reserves are shown for petroleum, natural gas, and coal. Prices are included for selected petroleum products. Production and consumption data are reported in standard units as well as British thermal units (Btu) and joules.

Not Available

1994-01-14T23:59:59.000Z

Note: This page contains sample records for the topic "isotope reactor annual" 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

Information Annual Report  

E-Print Network [OSTI]

PENN STATE Information Technology Services 2010­2011 Annual Report SUMMARY October 19, 2011 #12 ......................................................Community i. 17 ........................................Climate and Diversity i. 19 #12;#12;Information Technology Services 2010­2011 i.1 Vast amounts of information are essential to function in the contemporary

Maroncelli, Mark

462

Information Annual Report  

E-Print Network [OSTI]

PENN STATE Information Technology Services 2010­2011 Annual Report COMPILATION October 19, 2011 #12 ____________________Administrative Information Services ii ______________________Consulting and Support Services iii;#12;Information Technology Services 2010­2011 i.1 Vast amounts of information are essential to function

Maroncelli, Mark

463

48th Annual Distinguished  

E-Print Network [OSTI]

Electrical Engineering Technology » 1993 Wade Smith Mechanical Engineering » 1989 Presentation respected international energy consultancy. Baker & O'Brien, Inc. currently has offices in Dallas, Houston48th Annual Distinguished Engineer Awards Luncheon Friday, April 11, 2014 11:15 a.m. Sunset

Gelfond, Michael

464

Automated data extraction from in situ protein stable isotope...  

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

data extraction from in situ protein stable isotope probing studies. Automated data extraction from in situ protein stable isotope probing studies. Abstract: Protein stable isotope...

465

Copper isotope fractionation in acid mine drainage. | EMSL  

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

Copper isotope fractionation in acid mine drainage. Copper isotope fractionation in acid mine drainage. Abstract: We surveyed the Cu isotopic composition of primary minerals and...

466

Isotope production facility produces cancer-fighting actinium  

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

Cancer therapy gets a boost from new isotope Isotope production facility produces cancer-fighting actinium A new medical isotope project shows promise for rapidly producing major...

467

Annual report to Congress, FY 1992  

SciTech Connect (OSTI)

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for disposing of the Nation`s spent nuclear fuel from civilian nuclear power reactors and high-level radioactive waste from its defense activities in a cost-effective manner that protects the health and safety of the public and workers and the quality of the environment. To accomplish this mission OCRWM is developing a waste management system consisting of a geologic repository, a facility for monitored retrievable storage, and a system for transporting the waste. This is the ninth annual report submitted by the OCRWM to Congress. The OCRWM submits this report to inform Congress of its activities and expenditures during fiscal year 1992 (October 1, 1991 through September 30, 1992).

NONE

1993-07-01T23:59:59.000Z

468

Nuclear reactor control column  

DOE Patents [OSTI]

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

469

Reactor Safety Research Programs  

SciTech Connect (OSTI)

This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

Edler, S. K.

1981-07-01T23:59:59.000Z

470

Process for preparing a chemical compound enriched in isotope content  

DOE Patents [OSTI]

A process to prepare a chemical enriched in isotope content which includes: (a) A chemical exchange reaction between a first and second compound which yields an isotopically enriched first compound and an isotopically depleted second compound; (b) the removal of a portion of the first compound as product and the removal of a portion of the second compound as spent material; (c) the conversion of the remainder of the first compound to the second compound for reflux at the product end of the chemical exchange reaction region; (d) the conversion of the remainder of the second compound to the first compound for reflux at the spent material end of the chemical exchange region; and the cycling of the additional chemicals produced by one conversion reaction to the other conversion reaction, for consumption therein. One of the conversion reactions is an oxidation reaction, and the energy that it yields is used to drive the other conversion reaction, a reduction. The reduction reaction is carried out in a solid polymer electrolyte electrolytic reactor. The overall process is energy efficient and yields no waste by-products.

Michaels, Edward D. (Spring Valley, OH)

1982-01-01T23:59:59.000Z

471

RERTR 2009 (Reduced Enrichment for Research and Test Reactors)  

SciTech Connect (OSTI)

The U.S. Department of Energy/National Nuclear Security Administration's Office of Global Threat Reduction in cooperation with the China Atomic Energy Authority and International Atomic Energy Agency hosted the 'RERTR 2009 International Meeting on Reduced Enrichment for Research and Test Reactors.' The meeting was organized by Argonne National Laboratory, China Institute of Atomic Energy and Idaho National Laboratory and was held in Beijing, China from November 1-5, 2009. This was the 31st annual meeting in a series on the same general subject regarding the conversion of reactors within the Global Threat Reduction Initiative (GTRI). The Reduced Enrichment for Research and Test Reactors (RERTR) Program develops technology necessary to enable the conversion of civilian facilities using high enriched uranium (HEU) to low enriched uranium (LEU) fuels and targets.

Totev, T.; Stevens, J.; Kim, Y. S.; Hofman, G.; Matos, J.; Hanan, N.; Garner, P.; Dionne, B.; Olson, A.; Feldman, E.; Dunn, F.; Nuclear Engineering Division; Atomic Research Center; Inst. of Nuclear Physics; LLNL; INL; Korea Atomic Energy Research Inst.; Comisi?n Nacional de Energ?a At?mica; Nuclear Reactor Lab.; Inst. of Atomic Energy-Poland; AECL-Canada; Hungarian Academy of Sciences KFKI Atomic Energy Research Inst.; Japan Atomic Energy Agency; Nuclear Power Inst. of China; Kyoto Univ. Research Reactor Inst.

2010-03-01T23:59:59.000Z

472

Definition: Isotopic Analysis- Fluid | Open Energy Information  

Open Energy Info (EERE)

Definition Definition Edit with form History Facebook icon Twitter icon » Definition: Isotopic Analysis- Fluid Jump to: navigation, search Dictionary.png Isotopic Analysis- Fluid Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable. Fluid isotopes are used to characterize a fluids origin, age, and/or interaction with rocks or other fluids based on unique isotopic ratios or concentrations.[1] View on Wikipedia Wikipedia Definition Isotope geochemistry is an aspect of geology based upon study of the relative and absolute concentrations of the elements and their isotopes in

473

Definition: Isotopic Analysis | Open Energy Information  

Open Energy Info (EERE)

Analysis Analysis Jump to: navigation, search Dictionary.png Isotopic Analysis Isotopes are atoms of the same element that have different numbers of neutrons. An isotopic analysis looks at a particular isotopic element(s) in a given system, while the conditions which increase/decrease the number of neutrons are well understood and measurable.[1] View on Wikipedia Wikipedia Definition Isotope analysis is the identification of isotopic signature, the distribution of certain stable isotopes and chemical elements within chemical compounds. This can be applied to a food web to make it possible to draw direct inferences regarding diet, trophic level, and subsistence. Isotope ratios are measured using mass spectrometry, which separates the different isotopes of an element on the basis of their mass-to-charge

474

Nuclear reactor reflector  

DOE Patents [OSTI]

A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

Hopkins, Ronald J. (Pensacola, FL); Land, John T. (Pensacola, FL); Misvel, Michael C. (Pensacola, FL)

1994-01-01T23:59:59.000Z

475

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

476

2013 Annual DOE-NE Materials Research Coordination Meeting | Department of  

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

2013 Annual DOE-NE Materials Research Coordination Meeting 2013 Annual DOE-NE Materials Research Coordination Meeting 2013 Annual DOE-NE Materials Research Coordination Meeting The Reactor Materials element of the Nuclear Energy Enabling Technologies (NEET) program conducted its FY 2013 coordination meeting as a series of four web-conferences to act as a forum for the nuclear materials research community. The purpose of this meeting was to report on current and planned nuclear materials research, identify new areas of collaboration and promote greater coordination among the various Office of Nuclear Energy (NE) programs. Currently, materials research is performed in several NE programs, including NE Advanced Modeling and Simulation (NEAMS), Fuel Cycle Research and Development (FCRD), Advanced Reactor Technologies

477

2013 Annual DOE-NE Materials Research Coordination Meeting | Department of  

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

2013 Annual DOE-NE Materials Research Coordination Meeting 2013 Annual DOE-NE Materials Research Coordination Meeting 2013 Annual DOE-NE Materials Research Coordination Meeting The Reactor Materials element of the Nuclear Energy Enabling Technologies (NEET) program conducted its FY 2013 coordination meeting as a series of four web-conferences to act as a forum for the nuclear materials research community. The purpose of this meeting was to report on current and planned nuclear materials research, identify new areas of collaboration and promote greater coordination among the various Office of Nuclear Energy (NE) programs. Currently, materials research is performed in several NE programs, including NE Advanced Modeling and Simulation (NEAMS), Fuel Cycle Research and Development (FCRD), Advanced Reactor Technologies

478

Reactor Thermal-Hydraulics  

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

Thermal-Hydraulics Thermal-Hydraulics Dr. Tanju Sofu, Argonne National Laboratory In a power reactor, the energy produced in fission reaction manifests itself as heat to be removed by a coolant and utilized in a thermodynamic energy conversion cycle to produce electricity. A simplified schematic of a typical nuclear power plant is shown in the diagram below. Primary coolant loop Steam Reactor Heat exchanger Primary pump Secondary pump Condenser Turbine Water Although this process is essentially the same as in any other steam plant configuration, the power density in a nuclear reactor core is typically four orders of magnitude higher than a fossil fueled plant and therefore it poses significant heat transfer challenges. Maximum power that can be obtained from a nuclear reactor is often limited by the

479

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

480

Uranium Marketing Annual Report - Release Date: May 31, 2011  

Gasoline and Diesel Fuel Update (EIA)

1. Unfilled uranium market requirements of owners and operators of U.S. civilian nuclear power reactors, 2012-2022 1. Unfilled uranium market requirements of owners and operators of U.S. civilian nuclear power reactors, 2012-2022 thousand pounds U3O8 equivalent As of December 31, 2011 As of December 31, 2012 Year Annual Cumulative Annual Cumulative 2012 2,096 2,096 - - - 2013 6,740 8,836 1,153 1,153 2014 8,765 17,601 7,494 8,647 2015 19,528 37,128 15,029 23,675 2016 24,059 61,187 16,607 40,282 2017 28,225 89,442 24,316 64,597 2018 35,266 124,708 30,310 94,908 2019 40,901 165,608 33,296 128,204 2020 44,668 210,277 39,442 167,645 2021 44,803 255,080 45,780 213,425 2022 - -- 41,720 255,145 - = No data reported. -- = Not applicable. Note: Totals may not equal sum of components because of independent rounding. Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual Survey" (2011-

Note: This page contains sample records for the topic "isotope reactor annual" 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.


481

Molten metal reactors  

DOE Patents [OSTI]

A molten metal reactor for converting a carbon material and steam into a gas comprising hydrogen, carbon monoxide, and carbon dioxide is disclosed. The reactor includes an interior crucible having a portion contained within an exterior crucible. The interior crucible includes an inlet and an outlet; the outlet leads to the exterior crucible and may comprise a diffuser. The exterior crucible may contain a molten alkaline metal compound. Contained between the exterior crucible and the interior crucible is at least one baffle.

Bingham, Dennis N; Klingler, Kerry M; Turner, Terry D; Wilding, Bruce M

2013-11-05T23:59:59.000Z

482

F Reactor Inspection  

ScienceCinema (OSTI)

Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-11-24T23:59:59.000Z

483

F Reactor Inspection  

SciTech Connect (OSTI)

Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-10-29T23:59:59.000Z

484

Petroleum Marketing Annual 1997  

Gasoline and Diesel Fuel Update (EIA)

7 7 Entire . The entire report as a single file. PDF 1.2MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights . Petroleum Marketing Annual Highlights PDF . . Summary Statistics . Summary Statistics Tables PDF 1 Crude Oil Prices PDF TXT 2 U.S. Refiner Prices of Petroleum Products to End Users PDF TXT 3 U.S. Refiner Volumes of Petroleum Products to End Users PDF TXT 4 U.S. Refiner Prices of Petroleum Products for Resale PDF TXT 5 U.S. Refiner Volumes of Petroleum Products for Resale PDF TXT 6 U.S. Refiner Motor Gasoline Prices by Grade and Sales Type PDF TXT 7 U.S. Refiner Motor Gasoline Volumes by Grade and Sales Type PDF TXT 8 U.S. Refiner Conventional Motor Gasoline Prices by Grade and Sales Type PDF TXT

485

Uranium Marketing Annual Report  

Gasoline and Diesel Fuel Update (EIA)

Uranium Marketing Uranium Marketing Annual Report May 2011 www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. U.S. Energy Information Administration | 2010 Uranium Marketing Annual Report ii Contacts This report was prepared by the staff of the Renewables and Uranium Statistics Team, Office of Electricity, Renewables, and Uranium Statistics. Questions about the preparation and content of this report may be directed to Michele Simmons, Team Leader,

486

BCP Annual Rate Process  

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

2013 BCP Annual Rate Process 2013 BCP Annual Rate Process Informal Process Rate Activity Schedule (doc) Informal Customer Meeting Thursday March 6, 2013 at 10:30 A.M. Conf Rms 3&4 Informal Customer Meeting Presentation (Pdf) PRS Executive Summary (Mar 07, 2013) (Pdf) FY2014 Final Ten Year Operating Plan PRS Executive Summary (PDF) FORM for Foreign Visits (doc) Formal Process Initial Federal Register Notice (pdf) Public Information Forum March 27,2013 at 10:30 A.M. Conf Rms3&4 Customer Meeting Presentation PIF Presentation (PPT) Presentation Details (pdf) Reclamation Fund Status Report PIF PRS Executive Summary (pdf) PIF Transcripts (PDF) Visitor Center Cost Analysis Questions - Responses Public Comment Forum April 10, 2013 at 10:30 A.M. Conf Rms3&4 PCF Transcripts Customer Letters

487

Annual Energy Outlook 1999  

Gasoline and Diesel Fuel Update (EIA)

9) 9) Annual Energy Outlook 1999 With Projections to 2020 December 1998 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. For Further Information . . . The Annual Energy Outlook 1999 (AEO99) was prepared by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting, under the direction of Mary J. Hutzler (mhutzler@eia.doe.gov, 202/586-2222).

488

Annual Energy Outlook 1998  

Gasoline and Diesel Fuel Update (EIA)

8) 8) Distribution Category UC-950 Annual Energy Outlook 1998 With Projections to 2020 December 1997 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the U.S. Department of Energy. The information contained herein should be attributed to the Energy Information Administra- tion and should not be construed as advocating or reflecting any policy position of the Department of Energy or any other or- ganization. The Annual Energy Outlook 1998 (AEO98) presents midterm forecasts of energy supply, demand, and prices through 2020 prepared by the Energy Informa- tion Administration (EIA). The projections are based on results from EIA's National Energy Modeling

489

Annual Energy Outlook 2002  

Gasoline and Diesel Fuel Update (EIA)

2) 2) December 2001 Annual Energy Outlook 2002 With Projections to 2020 December 2001 For Further Information . . . The Annual Energy Outlook 2002 (AEO2002) was prepared by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting, under the direction of Mary J. Hutzler (mhutzler@ eia.doe.gov, 202/586-2222), Director, Office of Integrated Analysis and Forecasting; Scott Sitzer (ssitzer@ eia.doe.gov, 202/586-2308), Director, Coal and Electric Power Division; Susan H. Holte (sholte@eia.doe.gov, 202/586-4838), Director, Demand and Integration Division; James M. Kendell (jkendell@eia.doe.gov, 202/586-9646), Director, Oil and Gas Division; and Andy S. Kydes (akydes@eia.doe.gov, 202/586-2222), Senior Technical Advisor. For ordering information and questions on other energy statistics available from EIA, please contact EIA's National

490

Petroleum Marketing Annual  

Gasoline and Diesel Fuel Update (EIA)

9 9 Entire . The entire report as a single file. PDF 1.2MB . Front Matter . Petroleum Marketing Annual Cover Page, Preface, and Table of Contents PDF . Highlights . Petroleum Marketing Annual Highlights PDF . . Summary Statistics . Summary Statistics Tables PDF 1 Crude Oil Prices PDF TXT 2 U.S. Refiner Prices of Petroleum Products to End Users PDF TXT 3 U.S. Refiner Volumes of Petroleum Products to End Users PDF TXT 4 U.S. Refiner Prices of Petroleum Products for Resale PDF TXT 5 U.S. Refiner Volumes of Petroleum Products for Resale PDF TXT 6 U.S. Refiner Motor Gasoline Prices by Grade and Sales Type PDF TXT 7 U.S. Refiner Motor Gasoline Volumes by Grade and Sales Type PDF TXT 8 U.S. Refiner Conventional Motor Gasoline Prices by Grade and Sales Type PDF TXT

491

Natural Gas Annual, 1998  

Gasoline and Diesel Fuel Update (EIA)

8 8 Historical The Natural Gas Annual, 1998 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 1998. Summary data are presented for each Census Division and State for 1994 to 1998. A section of historical data at the National level shows industry activities back to the 1930's. The data that appear in the tables of the Natural Gas Annual, 1998 are available as self-extracting executable files in ASCII TXT or CDF file formats. This volume emphasizes information for 1998, although some tables show a five-year history. Please read the file entitled README.V1 for a description and documentation of information included in this file.

492

Annual Energy Review 1997  

Gasoline and Diesel Fuel Update (EIA)

7 7 Exported Energy Coal Other NGPL Other Adjustments Total Consumption Total Supply Nucle ar Rene wable s Crude Oil and Products Fossil Fuels Renewables Domestic Production Industrial Use Transportation Use Residential and Commercial Use Coal Natural Gas Petroleum Nuclear Imported Energy Fossil Fuels Coal Crude Oil Natural Gas Energy Information Administration July 1998 DOE/EIA-0384(97) Annual Energy Review 1997 The Annual Energy Review (AER) presents the Energy Information Admin- istration's historical energy statistics. For many series, statistics are given for every year from 1949 through 1997. The statistics, expressed in either physical units or British thermal units, cover all major energy activities, in- cluding consumption, production, trade, stocks, and prices, for all major energy commodities, including fossil fuels, electricity, and renewable en-

493

Natural Gas Annual 1995  

Gasoline and Diesel Fuel Update (EIA)

Annual Annual 1995 Energy Information Administration DOE/EIA-0131(95) November 1996 NGA NGA This publication and other Energy Information Administration (EIA) publications may be purchased from the Superin- tendent of Documents, U.S. Government Printing Office. Telephone orders may be directed to: Superintendent of Documents U.S. Government Printing Office Main Order Desk (202) 512-1800 FAX: (202) 512-2250 8 a.m. to 4:30 p.m., eastern time, M-F All mail orders should be directed to: U.S. Government Printing Office P.O. Box 371954 Pittsburgh, PA 15250-7954 Complimentary subscriptions and single issues are available to certain groups of subscribers, such as public and academic libraries, Federal, State, local and foreign governments, EIA survey respondents, and the media. For further information and for answers to questions on energy statistics, please

494

Petroleum Marketing Annual  

Gasoline and Diesel Fuel Update (EIA)

5 5 Entire . The entire report as a single file. PDF 2.9MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights . Petroleum Marketing Annual Highlights PDF . . Summary Statistics . Summary Statistics Tables PDF 1 Crude Oil Prices PDF 2 U.S. Refiner Prices of Petroleum Products to End Users PDF 3 U.S. Refiner Volumes of Petroleum Products to End Users PDF 4 U.S. Refiner Prices of Petroleum Products for Resale PDF 5 U.S. Refiner Volumes of Petroleum Products for Resale PDF 6 U.S. Refiner Motor Gasoline Prices by Grade and Sales Type PDF 7 U.S. Refiner Motor Gasoline Volumes by Grade and Sales Type PDF 8 U.S. Refiner Conventional Motor Gasoline Prices by Grade and Sales Type PDF 9 U.S. Refiner Conventional Motor Gasoline Volumes by Grade and Sales Type PDF

495

Annual Energy Outlook 1996  

Gasoline and Diesel Fuel Update (EIA)

96) 96) Distribution Category UC-950 Annual Energy Outlook 1996 With Projections to 2015 January 1996 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or any other organization. For Further Information . . . The Annual Energy Outlook (AEO) is prepared by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting, under the direction of Mary J. Hutzler (mhutzler@eia.doe.gov, 202/586-2222). General questions may be addressed to Arthur T. Andersen (aanderse@eia.doe.gov, 202/ 586-1130),

496

Annual Energy Outlook 2001  

Gasoline and Diesel Fuel Update (EIA)

Homepage Homepage Annual Energy Outlook 2001 With Projections to 2020 Preface The Annual Energy Outlook 2001 (AEO2001) presents midterm forecasts of energy supply, demand, and prices through 2020 prepared by the Energy Information Administration (EIA). The projections are based on results from EIA’s National Energy Modeling System (NEMS). The report begins with an “Overview” summarizing the AEO2001 reference case. The next section, “Legislation and Regulations,” discusses evolving legislative and regulatory issues. “Issues in Focus” discusses the macroeconomic projections, world oil and natural gas markets, oxygenates in gasoline, distributed electricity generation, electricity industry restructuring, and carbon dioxide emissions. It is followed by the analysis of energy market trends.

497

Annual Energy Outlook 2012  

Gasoline and Diesel Fuel Update (EIA)

2 2 Source: U.S. Energy Information Administration, Office of Energy Analysis. U.S. Energy Information Administration / Annual Energy Outlook 2010 213 Appendix F Regional Maps Figure F1. United States Census Divisions Pacific East South Central South Atlantic Middle Atlantic New England West South Central West North Central East North Central Mountain AK WA MT WY ID NV UT CO AZ NM TX OK IA KS MO IL IN KY TN MS AL FL GA SC NC WV PA NJ MD DE NY CT VT ME RI MA NH VA WI MI OH NE SD MN ND AR LA OR CA HI Middle Atlantic New England East North Central West North Central Pacific West South Central East South Central South Atlantic Mountain Source: U.S. Energy Information Administration, Office of Integrated Analysis and Forecasting. Appendix F Regional Maps Figure F1. United States Census Divisions U.S. Energy Information Administration | Annual Energy Outlook 2012

498

Natural Gas Annual, 1997  

Gasoline and Diesel Fuel Update (EIA)

7 7 Historical The Natural Gas Annual, 1997 provides information on the supply and disposition of natural gas in the United States. Production, transmission, storage, deliveries, and price data are published by State for 1997. Summary data are presented for each Census Division and State for 1993 to 1997. A section of historical data at the National level shows industry activities back to the 1930's. The data that appear in the tables of the Natural Gas Annual, 1997 are available as self-extracting executable files in ASCII TXT or CDF file formats. This volume emphasizes information for 1997, although some tables show a five-year history. Please read the file entitled README.V1 for a description and documentation of information included in this file.

499

Petroleum Marketing Annual  

Gasoline and Diesel Fuel Update (EIA)

6 6 Entire . The entire report as a single file. PDF 2.9MB . . Front Matter . Petroleum Marketing Annual Cover Page, Contacts, Preface, and Table of Contents PDF . . Highlights . Petroleum Marketing Annual Highlights PDF . . Summary Statistics . Summary Statistics Tables PDF 1 Crude Oil Prices PDF 2 U.S. Refiner Prices of Petroleum Products to End Users PDF 3 U.S. Refiner Volumes of Petroleum Products to End Users PDF 4 U.S. Refiner Prices of Petroleum Products for Resale PDF 5 U.S. Refiner Volumes of Petroleum Products for Resale PDF 6 U.S. Refiner Motor Gasoline Prices by Grade and Sales Type PDF 7 U.S. Refiner Motor Gasoline Volumes by Grade and Sales Type PDF 8 U.S. Refiner Conventional Motor Gasoline Prices by Grade and Sales Type PDF 9 U.S. Refiner Conventional Motor Gasoline Volumes by Grade and Sales Type PDF

500

Annual Energy Review 2000  

Gasoline and Diesel Fuel Update (EIA)

Review Review 2000 www.eia.doe.gov On the Web at: www.eia.doe.gov/aer Energy Information Administration DOE/EIA-0384(2000) August 2001 Annual Energy Review 2000 The Annual Energy Review (AER) presents the Energy Information Admin- istration's historical energy statistics. For many series, statistics are given for every year from 1949 through 2000. The statistics, expressed in either physical units or British thermal units, cover all major energy activities, in- cluding consumption, production, trade, stocks, and prices, for all major energy commodities, including fossil fuels, electricity, and renewable en- ergy sources. Publication of this report is required under Public Law 95-91 (Department of Energy Organization Act), Section 205(c), and is in keeping with re- sponsibilities given to the Energy Information Administration under Sec- tion 205(a)(2), which