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Evaluation of strontium-90 radial concentration profiles in Peach Bottom HTGR Core 2 fuel elements. HTGR base technology program, HTGR chemistry studies (189a 01329). [483 2000]

Description: Radial concentration profiles of /sup 90/Sr were evaluated for four fuel elements of the Peach Bottom High-Temperature Gas-Cooled Reactor (HTGR) Core 2. A transport model utilizing a single effective diffusion coefficient was able to reproduce the strontium concentraion profile in graphite at temperatures above about 960/sup 0/C. Below this temperature, ''tails'' were observed in the experimental concentration profile and the profiles could not be completely reproduced. Diffusion coefficients d… more
Date: February 1, 1979
Creator: Haire, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Refinements to temperature calculations of spent fuel assemblies when in a stagnant gas environment

Description: Undesirably high temperatures are possible in irradiated fuel assemblies because of the radioactive decay of fission products formed while in the reactor. The COXPRO computer code has been used for some time to calculate temperatures in spent fuel when the fuel is suspended in a stagnant gas environment. This code assumed radiation to be the only mode of heat dissipation within the fuel pin bundle. Refinements have been made to include conduction as well as radiation heat transfer within this c… more
Date: January 1, 1984
Creator: Rhodes, C.A. & Haire, M.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ALARA Review of the Spallation Neutron Source Accumulator Ring and Transfer Lines

Description: The Spallation Neutron Source (SNS) is designed to meet the growing need for new tools that will deepen our understanding in materials science, life science, chemistry, fundamental and nuclear physics, earth and environmental sciences, and engineering sciences. The SNS is an accelerator-based neutron-scattering facility that when operational will produce an average beam power of 2 MW at a repetition rate of 60 Hz. The accelerator complex consists of the front-end systems, which will include an … more
Date: June 30, 2003
Creator: Haire, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Computation of Normal Conducting and Superconducting Linear Accelerator (LINAC) Availabilities

Description: A brief study was conducted to roughly estimate the availability of a superconducting (SC) linear accelerator (LINAC) as compared to a normal conducting (NC) one. Potentially, SC radio frequency cavities have substantial reserve capability, which allows them to compensate for failed cavities, thus increasing the availability of the overall LINAC. In the initial SC design, there is a klystron and associated equipment (e.g., power supply) for every cavity of an SC LINAC. On the other hand, a sing… more
Date: July 11, 2000
Creator: Haire, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DUF6 Materials Use Roadmap

Description: The U.S. government has {approx}500,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms stored at U.S. Department of Energy (DOE) sites across the United States. This DU, most of which is DU hexafluoride (DUF{sub 6}) resulting from uranium enrichment operations, is the largest amount of nuclear material in DOE's inventory. On July 6, 1999, DOE issued the ''Final Plan for the Conversion of Depleted Uranium Hexafluoride as required by Public Law 105-204'', in which DOE… more
Date: September 4, 2002
Creator: Haire, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]

Description: The behavior of the fission metal cesium and the fission gases krypton and xenon in the Saclay Spitfire Loop SSL-1 test has been compared to that predicted using General Atomic reference data and computer code models. This is the first in a series of analyses planned in order to provide quantitative validation of HTGR fission product design methods. In this analysis, the first attempt to rigorously verify fission product design methods, the FIPERQ code was used to model the diffusion of cesium … more
Date: February 1, 1978
Creator: Jensen, D. D.; Haire, M. J. & Ballagny, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of the joint United States/Japanese criticality data development program for the Fast Breeder fuel cycle

Description: An experimental program is described to accumulate the basic criticality data on uranium-plutonium aqueous solution systems, including pin and water systems. This experimental program, managed by the Consolidated Fuel Reprocessing Program, utilized existing critical experiment facilities. However, Japan at least for the near future, does not have a facility for conducting critical experiments where fissible solution can be treated and processed. Therefore, Japan has remoted the existing US expe… more
Date: January 1, 1987
Creator: Takeda, H.; Kishimoto, Y.; Matsumoto, T. & Haire, M.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

System availability top-down apportionment method

Description: A top-down method for apportioning overall manufacturing facility availability among systems and subsystems is presented. Characteristics which influence equipment reliability are defined. Experts, using engineering judgement, score each characteristic for each equipment system whose availability design goal is to be established. Scores for each characteristic are combined into weighting factors. A mathematical model is derived which incorporates these weighting factors. This methodology establ… more
Date: January 1, 1985
Creator: Haire, M. J.; Maltese, J. G. & Sohmer, R. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear fuel cycle costs

Description: The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel cycle costs are given for the pressurized water reactor once-through and fuel recycle systems, and for the liquid-metal fast breeder reactor system. These calculations show that fuel cycle costs are a small part of the total power costs. For breeder reactors, fuel cycle costs are about half that of the present once-t… more
Date: February 1, 1982
Creator: Burch, W.D.; Haire, M.J. & Rainey, R.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear-fuel-cycle costs. Consolidated Fuel-Reprocessing Program

Description: The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel-cycle costs are given for the pressurized-water reactor once-through and fuel-recycle systems, and for the liquid-metal fast-breeder-reactor system. These calculations show that fuel-cycle costs are a small part of the total power costs. For breeder reactors, fuel-cycle costs are about half that of the present once-t… more
Date: January 1, 1981
Creator: Burch, W.D.; Haire, M.J. & Rainey, R.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Back-end costs of alternative nuclear fuel cycles

Description: As part of its charter, the Alternate Fuel Cycle Evaluation Program (AFCEP) was directed to evaluate the back-end of the nuclear fuel cycle in support of the Nonproliferation Alternative Systems Assessment Program (NASAP). The principal conclusion from this study is that the costs for recycling a broad range of reactor fuels will not have a large impact on total fuel cycle costs. For the once-through fuel cycle, the costs of fresh fuel fabrication, irradiated fuel storage, and associated transp… more
Date: January 1, 1980
Creator: Rainey, R.H.; Burch, W.D.; Haire, M.J. & Unger, W.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fuel-cycle costs for alternative fuels

Description: This paper compares the fuel cycle cost and fresh fuel requirements for a range of nuclear reactor systems including the present day LWR without fuel recycle, an LWR modified to obtain a higher fuel burnup, an LWR using recycle uranium and plutonium fuel, an LWR using a proliferation resistant /sup 233/U-Th cycle, a heavy water reactor, a couple of HTGRs, a GCFR, and several LMFBRs. These reactor systems were selected from a set of 26 developed for the NASAP study and represent a wide range of … more
Date: January 1, 1980
Creator: Rainey, R.H.; Burch, W.D.; Haire, M.J. & Unger, W.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Spallation Neutron Source Availability Top-Down Apportionment Using Characteristic Factors and Expert Opinion

Description: Apportionment is the assignment of top-level requirements to lower tier elements of the overall facility. A method for apportioning overall facility availability requirements among systems and subsystems is presented. Characteristics that influence equipment reliability and maintainability are discussed. Experts, using engineering judgment, scored each characteristic for each system whose availability design goal is to be established. The Analytic Hierarchy Process (AHP) method is used to produ… more
Date: October 1, 1999
Creator: Haire, M.J. & Schryver, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Establishing Availability Requirements Using Characteristics Factors and Expert Opinion

Description: System design engineers must translate permitted overall facility downtime into detailed design and operating specifications for numerous systems and subsystems that make up the facility. The process of assigning reliability and maintainability requirements to individual equipment systems to attain a desired overall availability is known as availability apportionment. Apportionment is normally required early in conceptual design when little or no hardware information is available. Apportionment… more
Date: June 18, 2000
Creator: Haire, M.J. & Schryver, J.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The influence of maintenance system reliability and maintainability characteristics on overall plant availability

Description: Performance goals for complex processes are often linked with achieving high availability of plant equipment. This requires that maintenance systems, which sometimes include complex electromechanical equipment operating in a hostile environment, meet certain requirements for reliability and maintainability. This paper develops several Markov probability models to evaluate the impact of maintenance system availability on the overall plant. The models considered included the case when the mainten… more
Date: January 1, 1991
Creator: Prince, B.E. & Haire, M.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Practical risk-based decision making: Good decisions made efficiently

Description: The Robotics and Process Systems Division of the Oak Ridge National Laboratory and the Westinghouse Savannah River Company have teamed with JBF Associates, Inc. to address risk-based robotic planning. The objective of the project is to provide systematic, risk-based relative comparisons of competing alternatives for solving clean-up problems at DOE facilities. This paper presents the methodology developed, describes the software developed to efficiently apply the methodology, and discusses the … more
Date: December 1, 1995
Creator: Haire, M.J.; Guthrie, V.; Walker, D. & Singer, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Some Electrical Properties of Ion-Implanted Urania--Part II: Preprint

Description: As part of the U.S. Department of Energy's effort to evaluate the use of UO2 as a material for photovoltaic (e.g., solar cell) applications, single-crystal UO2 samples were characterized as to their electrical and electro-optical properties. Samples of UO2 were ion implanted with boron and sulfur dopants, as well as with boron and sulfur co-dopants, at the Ion Beam Materials Laboratory facility at Los Alamos National Laboratory. Activation energies for electrical conduction were measured to be … more
Date: February 1, 2003
Creator: von Roedern, B.; Meek, T. T. & Haire, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Depleted uranium oxides as spent-nuclear-fuel waste-package invert and backfill materials

Description: A new technology has been proposed in which depleted uranium, in the form of oxides or silicates, is placed around the outside of the spent nuclear fuel waste packages in the geological repository. This concept may (1) reduce the potential for repository nuclear criticality events and (2) reduce long-term release of radionuclides from the repository. As a new concept, there are significant uncertainties.
Date: July 7, 1997
Creator: Forsberg, C.W. & Haire, M.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Depleted Uranium in Repositories

Description: For uranium to be useful in most fission nuclear reactors, it must be enriched (i.e. the concentration of the fissile isotope 235U must be increased). Therefore, depleted uranium (DU)-uranium which has less than naturally occurring concentrations of 235U-is a co-product of the enrichment process. Four to six tons of DU exist for every ton of fresh light water reactor fuel. There were 407,006 MgU 407,000 metric tons (t) of DU stored on U.S. Department of Energy (DOE) sites as of July 1993. If th… more
Date: December 31, 1997
Creator: Haire, M. J. & Croff, A. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Incorporation of RAM techniques into simulation modeling

Description: This work concludes that reliability, availability, and maintainability (RAM) analytical techniques can be incorporated into computer network simulation modeling to yield an important new analytical tool. This paper describes the incorporation of failure and repair information into network simulation to build a stochastic computer model represents the RAM Performance of two vehicles being developed for the US Army: The Advanced Field Artillery System (AFAS) and the Future Armored Resupply Vehic… more
Date: July 1, 1995
Creator: Nelson, S.C. Jr.; Haire, M.J. & Schryver, J.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Beneficial Uses of Depleted Uranium

Description: Naturally occurring uranium contains 0.71 wt% {sup 235}U. In order for the uranium to be useful in most fission reactors, it must be enriched the concentration of the fissile isotope {sup 235}U must be increased. Depleted uranium (DU) is a co-product of the processing of natural uranium to produce enriched uranium, and DU has a {sup 235}U concentration of less than 0.71 wt%. In the United States, essentially all of the DU inventory is in the chemical form of uranium hexafluoride (UF{sub 6}) and… more
Date: August 1, 1997
Creator: Brown, C.; Croff, A. G. & Haire, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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