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Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

Description: The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the… more
Date: March 21, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Qualification of tribological materials and coatings for use in sodium. [LMFBR]

Description: This paper describes some of the essential performance measures used to qualify materials for tribological applications in liquid sodium environments and summarizes relative properties of some of the newer tribological materials now qualified for use in sodium systems.
Date: April 21, 1980
Creator: Johnson, R. N. & Farwick, D. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Pump, sodium, inducer, intermediate size (ISIP) (impeller/inducer/diffuser retrofit)

Description: This specification defines the requirements for the Intermediate-Size Inducer Pump (ISIP), which is to be made by replacing the impeller of the FFTF Prototype Pump with a new inducer, impeller, diffuser, seal, and necessary adapter hardware. Subsequent testing requirements of the complete pump assembly are included.
Date: April 21, 1978
Creator: Paradise, D.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal insulation system design and fabrication specification (nuclear) for the Clinch River Breeder Reactor plant

Description: This specification defines the design, analysis, fabrication, testing, shipping, and quality requirements of the Insulation System for the Clinch River Breeder Reactor Plant (CRBRP), near Oak Ridge, Tennessee. The Insulation System includes all supports, convection barriers, jacketing, insulation, penetrations, fasteners, or other insulation support material or devices required to insulate the piping and equipment cryogenic and other special applications excluded. Site storage, handling and ins… more
Date: July 21, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Actinide recycle in LMFBRs as a waste management alternative

Description: A strategy of actinide burnup in fast reactor systems has been investigated as an approach for reducing the long term hazards and storage requirements of the actinide waste elements and their decay daughters. The actinide recycle studies also included plutonium burnup studies in the event that plutonium is no longer required as a fuel. Particular emphasis was placed upon the timing of the recycle program, the requirements for separability of the waste materials, and the impact of the actinides … more
Date: August 21, 1979
Creator: Beaman, S.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Forced-convection boiling tests performed in parallel simulated LMR fuel assemblies

Description: Forced-convection tests have been carried out using parallel simulated Liquid Metal Reactor fuel assemblies in an engineering-scale sodium loop, the Thermal-Hydraulic Out-of-Reactor Safety facility. The tests, performed under single- and two-phase conditions, have shown that for low forced-convection flow there is significant flow augmentation by thermal convection, an important phenomenon under degraded shutdown heat removal conditions in an LMR. The power and flows required for boiling and dr… more
Date: April 21, 1985
Creator: Rose, S. D.; Carbajo, J. J.; Levin, A. E.; Lloyd, D. B.; Montgomery, B. H. & Wantland, J. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

Description: This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up … more
Date: March 21, 1977
Creator: Buchanan, J. R. & Keilholtz, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Physics of transmutation systems : system capabilities and performances.

Description: This document is complementary to a document produced by Prof. Salvatores on ''The Physics of Transmutation in Critical or Subcritical Reactors and the Impact on the Fuel Cycle''. In that document, Salvatores describes the fundamental of transmutation, through basic physics properties and general parametric studies. In the present document we try to go one step further towards practical implementation (while recognizing that the practical issues such as technology development and demonstration,… more
Date: August 21, 2002
Creator: Finck, P. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Degraded Mode

Description: The objective of this calculation is to characterize the nuclear criticality safety concerns associated with the codisposal of the Department of Energy's (DOE) Enrico Fermi (EF) Spent Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP) and placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for the degraded mode internal configurations of the codispos… more
Date: July 21, 2000
Creator: Moscalu, D.R.; Angers, L.; Monroe-Rammsey, J. & Radulesca, H.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

R-Matrix Evaluation of 16O Neutron Cross Sections up to 6.3 MeV

Description: In this paper we describe an evaluation of {sup 16}O neutron cross sections in the resolved resonance region with the multilevel Reich-Moore R-matrix formalism. Resonance analyses were performed with the computer code SAMMY [LA98] which utilizes Bayes method, a generalized least squares technique. Over the years the nuclear community has developed a collection of evaluated nuclear data for applications in thermal, fast reactor, and fusion systems. However, typical neutron spectra in criticality… more
Date: August 21, 2000
Creator: Sayer, R.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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