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in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
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Uranium production in thorium/denatured uranium fueled PWRs

Description: Uranium-232 buildup in a thorium/denatured uranium fueled pressurized water reactor, PWR(Th), was studied using a modified version of the spectrum-dependent zero dimensional depletion code, LEOPARD. The generic Combustion Engineering System 80 reactor design was selected as the reactor model for the calculations. Reactors fueled with either enriched natural uranium and self-generated recycled uranium or uranium from a thorium breeder and self-generated recycled uranium were considered. For enri… more
Date: October 18, 1977
Creator: Arthur, W.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flow-induced vibration study in the LOFT steam generator

Description: The consequences of flow induced vibration in the LOFT steam generator were studied. Tube-baffle contact and fretting wear are expected to occur while tube-tube contact is not predicted. The LOFT steam generator is, in all probability adequate from a fluid induced viewpoint for the scheduled service of the LOFT facility at power. 37 refs., 5 figs., 3 tabs.
Date: October 18, 1977
Creator: Carmichael, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Surface radiation properties between nuclear reactor materials in contact. [LMFBR core disruptive accident]

Description: This technical report summarizes a portion of the results on surface radiation properties of reactor materials, which is part of the program on Attenuation of Radiological Consequences From Core Disruptive Accidents by Radiative Transfer. In analyzing radiant energy exchange between the fuel and coolant, it is necessary to know the reflection absorption, and emission characteristics of the fuel and its interface with coolant. Because of unavailability and great uncertainty of those radiation pr… more
Date: October 18, 1978
Creator: Chan, S.H. & Tseng, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SRS Software Verification Pre Operational and Startup Test

Description: This document defines testing for the software used to control the Sodium Removal System (SRS). The testing is conducted off-line from the. physical plant by using a simulator built-in to the software. This provides verification of proper software operation prior to performing the operational acceptance tests with the actual plant hardware.
Date: October 18, 2000
Creator: HILL, L.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A physical description of fission product behavior fuels for advanced power reactors.

Description: The Global Nuclear Energy Partnership (GNEP) is considering a list of reactors and nuclear fuels as part of its chartered initiative. Because many of the candidate materials have not been explored experimentally under the conditions of interest, and in order to economize on program costs, analytical support in the form of combined first principle and mechanistic modeling is highly desirable. The present work is a compilation of mechanistic models developed in order to describe the fission produ… more
Date: October 18, 2007
Creator: Kaganas, G. & Rest, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ORINC: a one-dimensional implicit approach to the inverse heat conduction problem. [PWR]

Description: The report develops an implicit solution technique to determine both the transient surface temperature and the transient surface heat flux of electrically heated rods given the power input and an ''indicated'' internal temperature during a simulated loss-of-coolant accident. A digital computer program ORINC (ORNL Inverse Code) is developed which solves a one-dimensional, transient, lumped parameter, implicit formulation of the conduction equation at each bundle thermocouple position in the Ther… more
Date: October 18, 1977
Creator: Ott, L. J. & Hedrick, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Inspection techniques and processes for controlling FFTF fuel quality

Description: Reliable performance of fuels for the Fast Flux Test Facility (FFTF) is of paramount importance for the FFTF program. Improved inspection techniques and processes are essential for controlling the quality of such fuels. Several considerations necessitated the development and application of improved inspection techniques and processes. These include fuel design, throughput rate, and pre-irradiation characterization requirements. Some of the more significant advances are in the areas of fuel pell… more
Date: October 18, 1978
Creator: Powers, H. G.; Kirchner, T. L.; McLemore, D. R. & Gottschalk, G. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

EXTERNAL CRITICALITY CALCULATION FOR DOE SNF CODISPOSAL WASTE PACKAGES

Description: The purpose of this document is to evaluate the potential for criticality for the fissile material that could accumulate in the near-field (invert) and in the far-field (host rock) beneath the U.S. Department of Energy (DOE) spent nuclear fuel (SNF) codisposal waste packages (WPs) as they degrade in the proposed monitored geologic repository at Yucca Mountain. The scope of this calculation is limited to the following DOE SNF types: Shippingport Pressurized Water Reactor (PWR), Enrico Fermi, Fas… more
Date: October 18, 2002
Creator: Radulescu, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A summary of high-temperature electronics research and development

Description: Current and future needs in automative, aircraft, space, military, and well logging industries require operation of electronics at higher temperatures than today's accepted limit of 395 K. Without the availability of high-temperature electronics, many systems must operate under derated conditions or must accept severe mass penalties required by coolant systems to maintain electronic temperatures below critical levels. This paper presents ongoing research and development in the electronics commu… more
Date: October 18, 1991
Creator: Thome, F. V. & King, D. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

Description: The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Repor… more
Date: October 18, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

Description: The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Repor… more
Date: October 18, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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