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in subjects: "Breeding"

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Experimental program to validate analyses of accelerator breeder concepts

The concept of using high-energy particle accelerators to produce neutrons for converting fertile material to fissile is over 25 years old. It is only relatively recently that accelerator design has progressed to a point where the operation approaches commercial viability. Critical unknowns in the concept were identified in a detailed study of specic configurations. Experiments to elucidate these unknowns in a timely manner using existing material and facilities are defined and identified. Basi… more

Date: January 1, 1977

Creator: Talbert Jr., W. L.; Russell, G. J. & Malenfant, R. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Potential effects of maternal contribution on egg and larva population dynamics of striped bass: Integrated individual-based model and directed field sampling

We have used a bioenergetically-driven, individual-based model (IBM) of striped bass as a framework for synthesizing available information on population biology and quantifying, in a relative sense, factors that potentially affect year class success. The IBM has been configured to simulate environmental conditions experienced by several striped bass populations; i.e., in the Potomac River, MD; in Hudson River, NY; in the Santee-Cooper River System, SC, and; in the San Joaquin-Sacramento River S… more

Date: January 1, 1991

Creator: Cowan, J.H., Jr. (Maryland Univ., Solomons, MD (United States). Chesapeake Biological Lab.) & Rose, K.A. (Oak Ridge National Lab., TN (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Preliminary report on the promise of accelerator-driven natural-uranium-fueled light-water-moderated breeding power reactors

A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power.… more

Date: July 1, 1977

Creator: Greenspan, E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Assessment of tritium breeding requirements for fusion power reactors

This report presents an assessment of tritium-breeding requirements for fusion power reactors. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems in operation on a steady-state mode as well as on a pulsed mode. As an example, the UWMAK-I design was analyzed and it has been found that the startup inventory requirement calculated by the present method significantly differs from those previou… more

Date: December 1, 1983

Creator: Jung, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Hybrid reactors. [Fuel cycle]

The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of /sup 233/U per year. To obtain good economics, injector efficiency times plasma gain… more

Date: September 9, 1980

Creator: Moir, Ralph W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Generic problems with Li/sub 2/O breeders and tritium control in high-temperature fusion reactors

Within the past year, major reactor design studies have been performed using Li/sub 2/O as a breeder material. These are the INTOR and STARFIRE/DEMO projects. We in our studies on fusion/synfuels are embarking on another, but our blanket will operate at significantly higher temperatures than these two. Some of the problems inherent in using this material are aggravated and some are diminished by operating at higher temperatures. For the conditions of the above two design studies many of the pro… more

Date: April 1, 1982

Creator: Hickman, R. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fusion breeder

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be mad… more

Date: April 20, 1982

Creator: Moir, Ralph W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High performance, suppressed-fission ICF hybrid

The neutronics aspects of an ICF hybrid concept are discussed. The breeding blanket consists of a beryllium neutron multiplier, metallic thorium fertile fuel and a liquid-lithium coolant. The fertile fuel fraction is 30 vol%, which is much higher than previous one-zone, suppressed-fission hybrid concepts. Fission in the bred /sup 233/U is suppressed by competition from tritium breeding reactions in /sup 6/Li. The total breeding ratio, T + F, is 2.05, and the total neutron energy deposited is 41… more

Date: December 1, 1983

Creator: Meier, W. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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IPFR: Integrated Pool Fusion Reactor concept

The IPFR (Integrated Pool Fusion Reactor) concept is to place a fusion reactor into a pool of molten Flibe. The Flibe will serve the multiple functions of breeding, cooling, shielding, and moderating. Therefore, the only structural material between the superconducting magnets and the plasma is the first wall. The first wall is a stand-alone structure with no coolant connection and is cooled by Flibe at the atmospheric pressure. There is also no need of the primary coolant loop. The design is ex… more

Date: January 1, 1986

Creator: Sze, D.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium related safety considerations for mirror upgrades

One of the primary objectives of the MFTF-B upgrades is to demonstrate the technology of tritium breeding in a reactor-like configuration. This requires use and processing of tritium, involving an inventory of several hundred grams at the plant. This paper reviews the results of a preliminary assessment of the radiation hazard associated with the handling of tritium. The radiation dose consequences due to tritium release from normal operation and due to postulated accidents on plant personnel a… more

Date: November 30, 1983

Creator: Ghose, S.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Economic implications of fusion-fission energy systems

The principal conclusions that can be made based on the estimated costs reported in this paper are twofold. First, hybrid reactors operating symbiotically with conventional fission reactors are a potentially attractive supply alternative. Estimated hybrid energy system costs are slightly greater than estimated costs of the most attractive alternatives. However, given the technological, economic, and institutional uncertainties associated with future energy supply, differences of such magnitude … more

Date: April 1, 1979

Creator: Deonigi, D.E. & Schulte, S.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fusion breeder

Date: February 22, 1982

Creator: Moir, Ralph W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tritium recovery from lithium oxide pellets

The TFTR Lithium Blanket Module is an assembly containing 650 kg of lithium oxide that will be used to test the ability of neutronics codes to model the tritium breeding characteristics of limited-coverage breeding zones in a tokamak. It is required that tritium concentrations as low as 0.1 nCi/g bred in both metallic lithium samples and lithium oxide pellets be measured with an uncertainty not exceeding +- 6%. A tritium assay technique for the metallic samples which meets this criterion has be… more

Date: January 1, 1984

Creator: Bertone, P. C. & Jassby, D. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium handling in the Mirror Fusion Hybrid Reactor

A reference design study for a Mirror Fusion Hybrid Reactor has been completed which examines the tritium handling problems. Breeding pins composed of aluminum alloys contain lithium hydride with a four-year residence time for tritium production. The slip-stream helium tritium capture system is designed to handle a 0.1 percent pin failure and will reduce environmental losses to below 3 Ci/day. The neutral beam injectors and direct converters utilize small, thin electrode tubes at 700/sup 0/C fo… more

Date: October 1, 1977

Creator: Galloway, T.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Proceedings of an information meeting on accelerator-breeding

Thirty-two papers were presented at the Conference. A separate abstract was prepared for each paper. (RCK)

Date: January 1, 1977

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Laser driven fusion fission hybrids

The role of the fusion-fission hybrid reactor (FFHR) as a fissile fuel and/or power producer is discussed. As long range options to supply the world energy needs, hybrid-fueled thermal-burner reactors are compared to liquid metal fast breeder reactors (LMFBR). A discussion of different fuel cycles (thorium, depleted uranium, and spent fuel) is presented in order to compare the energy multiplication, the production of fissile fuel, the laser efficiency and pellet gain requirements of the hybrid … more

Date: July 12, 1977

Creator: Hansen, L. F. & Maniscalco, J. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Pressure drop considerations of a lithium cooled fusion breeder tokamak reactor blanket

Liquid lithium was selected as one of the coolants for the 1983 fusion breeder blanket used on the magnetically confined tokamak fusion reactor, and as a result, the thermal-hydraulic calculations were dominated by magnetohydrodynamic (MHD) considerations. The applicable sets of MHD equations for the engineering thermal-hydraulic design were reviewed and compared. Special attention was given to the MHD calculations for the fertile material zone, a packed bed of composite beryllium and thorium b… more

Date: December 6, 1983

Creator: Wong, C. P. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Summary Report for Bureau of Fisheries Stream Habitat Surveys : Willamette River Basin, 1934-1942, Final Report.

This document contains summary reports of stream habitat-surveys, conducted in the Willamette River basin, by the Bureau of Fisheries (BOF, now National Marine Fisheries Service) from 1934-1942. These surveys were part of a larger project to survey streams in the Columbia River basin that provided, or had provided, spawning and rearing habitat for salmon and steelhead (Rich, 1948). The purpose of the survey was, as described by Rich, 'to determine the present condition of the various tributarie… more

Date: January 1, 1995

Creator: McIntosh, Bruce A.; Clark, Sharon E. & Sedell, James R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Lawrence Livermore National Laboratory Pre-project Rare Plant and Wildlife Surveys For the Pit 7 Drainage Diversion and Groundwater Extraction and Treatment Facility

In January 2007, the Department of Energy (DOE) released the final Environmental Assessment for the Proposed Environmental Remediation at the Lawrence Livermore National Laboratory (LLNL) Site 300 Pit 7 Complex. At the same time, the Department of Toxic Substances Control (DTSC) released the final Negative Declaration and Initial Study covering the Pit 7 remediation. No substantial adverse effect on wildlife species of concern was anticipated from the project. However, it was proposed that wild… more

Date: July 17, 2007

Creator: Paterson, L & Woollett, J

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Summary Report for Bureau of Fisheries Stream Habitat Surveys : Umatilla, Tucannon, Asotin, and Grande Ronde River Basins, 1934-1942, Final Report.

This document contains summary reports of stream habitat surveys, conducted in the Umatilla and Grande Ronde River basins, by the Bureau of Fisheries (BOF, now National Marine Fisheries Service) from 1938-1942. These surveys were part of a larger project to survey streams in the Columbia River basin that provided, or had provided, spawning and rearing habitat for salmon and steelhead (Rich, 1948). The purpose of the survey was, as described by Rich, 'to determine the present condition of the va… more

Date: January 1, 1995

Creator: McIntosh, Bruce A.; Clark, Sharon E. & Sedell, James R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

An experimental study of the impact of location on the effectiveness of recruitment clusters for Red-cockaded Woodpeckers at the Savannah River Site.

An experimental study of the impact of location on the effectiveness of recruitment clusters for Red-Cockaded Woodpeckers at the Savannah River Site.

Date: May 31, 2008

Creator: Walters, Jeffrey, R.; Johnston, Peter, A.; Crowder, Larry, B. & Priddy, Jeffrey, A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Thermal-hydraulic and neutronic considerations for designing a lithium-cooled tokamak blanket

A methodology for the design of lithium cooled blankets is developed. The thermal-hydraulics, neutronics and interactions between them are extensively investigated. In thermal hydraulics, two models illustrate the methodology used to obtain the acceptable ranges for a set of design parameters. The methodology can be used to identify the limiting constraints for a particular design. A complete neutronic scheme is set up for the calculations of the volumetric heating rate as a function of the dis… more

Date: December 1, 1978

Creator: Chao, J; Mikic, B & Todreas, N

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Conceptual innovations in hybrid reactors

A number of innovations in the conception of fusion-fission hybrid reactors, including the blanket, the fusion driver, the coupling of the fusion and the fission components as well as the application of hybrid reactors are described, and their feasibility assessed.

Date: January 1, 1980

Creator: Greenspan, E. & Miley, G.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Managing the fusion burn to improve symbiotic system performance

Symbiotic power systems, in which fissile fuel is produced in fusion-powered factories and burned in thermal reactors characterized by high conversion ratios, constitute an interesting near-term fusion application. It is shown that the economic feasibility of such systems depend on adroit management of the fusion burn. The economics of symbiotes is complex: reprocessing and fabrication of the fusion reactor blankets are important components of the production cost of fissile fuel, but burning fi… more

Date: January 1, 1979

Creator: Renier, J.P. & Martin, J.G.

Item Type: Article

Partner: UNT Libraries Government Documents Department