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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

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

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

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
open access

Centralized Reliability Data Organization (CREDO) assessment of critical component unavailability in liquid metal reactors

Description: The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Dept. of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 20,000 components and approximately 1500 event records. A conservative estimation is that the total component operating hours is approaching 2.… more
Date: January 1, 1988
Creator: Koger, K. H.; Haire, M. J.; Humphrys, B. L.; Manneschmidt, J. F.; Setoguchi, K. & Nakai, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS

Description: The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and atte… more
Date: October 3, 2004
Creator: Haire, M. J.; Forsberg, C. W.; Matveev, V. Z. & Shapovalov, V. I.
Item Type: Refine your search to only Article
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

Criticality safety aspects of K-25 Building uranium deposit removal

Description: The K-25 Building of the Oak Ridge Gaseous Diffusion Plant (now the K-25 Site) went into operation during World War II as the first large scale production plant to separate {sup 235}U from uranium by the gaseous diffusion process. It operated successfully until 1964, when it was placed in a stand-by mode. The Department of Energy has initiated a decontamination and decommissioning program. The primary objective of the Deposit Removal (DR) Project is to improve the nuclear criticality safety of … more
Date: December 31, 1995
Creator: Haire, M. J.; Jordan, W. C.; Ingram, J. C., III & Stinnett, E. C., Jr.
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

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

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

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

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

An examination of reliability critical items in liquid metal reactors: An analysis by the Centralized Reliability Data Organization (CREDO)

Description: The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Department of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 21,000 components and approximately 1300 event records. A conservative estimation is that the total component operating hours is approachi… more
Date: January 1, 1987
Creator: Humphrys, B. L.; Haire, M. J.; Koger, K. H.; Manneschmidt, J. F.; Setoguchi, K.; Nakai, R. et al.
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

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

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

Nuclear criticality safety calculations for a K-25 site vacuum cleaner

Description: A modified Nilfisk model GSJ dry vacuum cleaner is used throughout the K-25 Site to collect dry forms of highly enriched uranium (HEU). When vacuuming, solids are collected in a cyclone-type separator vacuum cleaner body. Calculations were done with the SCALE (KENO V.a) computer code to establish conditions at which a nuclear criticality event might occur if the vacuum cleaner was filled with fissile solution. Conditions evaluated included full (12-in. water) reflection and nominal (1-in. water… more
Date: February 1, 1997
Creator: Shor, J. T. & Haire, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear criticality safety controls for uranium deposits during D and D at the Oak Ridge Gaseous Diffusion Plant

Description: The US Department of Energy (DOE) Deputy Assistant Secretary of Energy for Environmental Management has issued a challenge to complete DOE environmental cleanup within a decade. The response for Oak Ridge facilities is in accordance with the DOE ten-year plan which calls for completion of > 95% of environmental management work by the year 2006. This will result in a 99% risk reduction and in a significant savings in base line costs in waste management (legacy waste); remedial action (groundwate… more
Date: February 1, 1997
Creator: Haire, M. J.; Jordan, W. C.; Jollay, L. J., III & Dahl, T. L., Sr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear criticality safety modeling of an LEU deposit

Description: The construction of the Oak Ridge Gaseous Diffusion Plant (now known as the K-25 Site) began during World War H and eventually consisted of five major process buildings: K-25, K-27, K-29, K-31, and K-33. The plant took natural (0.711% {sup 231}U) uranium as feed and processed it into both low-enriched uranium (LEU) and high-enriched uranium (HEU) with concentrations up to {approximately}93% {sup 231}U. The K-25 and K-27 buildings were shut down in 1964, but the rest of the plant produced LEU un… more
Date: November 1996
Creator: Haire, M. J.; Elam, K. R.; Jordan, W. C. & Dahl, T. L.
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
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