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Nuclear power in the Soviet Bloc

Description: The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nu… more
Date: March 1, 1982
Creator: Davey, W.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Characterization of solids in the Three Mile Island Unit 2 Reactor defueling water: Addendum

Description: Shortly after ORNL/TM-10362 was issued, it was discovered that a series of 31 figures had been inadvertently omitted. These figures, which consist of scanning electron microscope (SEM) photographs and energy-dispersive X-ray fluorescence scans, provide significant information about the results obtained in the tests performed with water sample W3. This Addendum includes these figures. Details of and comments on the SEM photographs may be found in ORNL/TM-10362.
Date: March 1, 1988
Creator: Campbell, D.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seismic Safety Margins Research Program. Phase 1. Project V. Structural sub-system response: subsystem response review. [PWR; BWR]

Description: This project is directed toward a portion of the Seismic Safety Margins Research Program which includes one link in the seismic methodology chain. The link addressed here is the structural subsystem dynamic response which consists of those components and systems whose behavior is often determined decoupled from the major structural response. Typically the mathematical model utilized for the major structural response will include only the mass effects of the subsystem and the main model is used … more
Date: March 1, 1980
Creator: Fogelquist, J.; Kaul, M.K.; Koppe, R.; Tagart, S.W. Jr.; Thailer, H. & Uffer, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 103

Description: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 103, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system.
Date: March 7, 1978
Creator: Clemons, V. D.; White, M. D.; Moore, P. A. & Hedrick, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fatigue and environmentally assisted cracking in light water reactors

Description: Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specime… more
Date: March 1, 1992
Creator: Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental investigations of uncovered-bundle heat transfer and two-phase mixture-level swell under high-pressure low heat-flux conditions. [PWR]

Description: Results are reported from a series of uncovered-bundle heat transfer and mixture-level swell tests. Experimental testing was performed at Oak Ridge National Laboratory in the Thermal Hydraulic Test Facility (THTF). The THTF is an electrically heated bundle test loop configured to produce conditions similar to those in a small-break loss-of-coolant accident. The objective of heat transfer testing was to acquire heat transfer coefficients and fluid conditions in a partially uncovered bundle. Test… more
Date: March 1, 1982
Creator: Anklam, T. M.; Miller, R. J. & White, M. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT differential pressure uncertainty analysis

Description: A performance analysis of the LOFT differential pressure (..delta..P) measurement is presented. Along with completed descriptions of test programs and theoretical studies that have been conducted on the ..delta..P, specific sources of measurement uncertainty are identified, quantified, and combined to provide an assessment of the ability of this measurement to satisfy the SDD 1.4.1C (June 1975) requirement of measurement of differential pressure.
Date: March 1, 1977
Creator: Evans, R.P.; Biladeau, G.L. & Quinn, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel performance annual report for 1986

Description: This annual report, the ninth in a series, provides a brief description of fuel performance during 1986 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related U.S. Nuclear Regulatory Commission evaluations are included. 550 refs., 12 figs., 31 tabs.
Date: March 1, 1988
Creator: Bailey, W.J. & Wu, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status report on LWR spent fuel IAEA leach tests

Description: Spent light-water-reactor (LWR) fuel with an average burnup of 28,000 MWd/MTU was leach-tested at 25/sup 0/C using a modified version of the International Atomic Energy Agency procedure. Leach rates were determined from tests conducted in five different solutions: deionized water, sodium chloride (NaCl), sodium bicarbonate (NaHCO/sub 3/), calcium chloride (CaCl/sub 2/) and Waste Isolation Pilot Plant B brine solutions. Elemental leach rates are reported based on the release of /sup 90/Sr + /sup… more
Date: March 1, 1980
Creator: Katayama, Y.B.; Bradley, D.J. & Harvey, C.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review of the PASNY systems interaction study

Description: The objective of this review is to evaluate and make recommendations on the Systems Interaction (SI) methodology proposed by the Power Authority of the State of New York (PASNY) for application to Indian Point No. 3 (IP-3).
Date: March 1, 1982
Creator: Alesso, H.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flow measurement by pulsed-neutron activation techniques at the PKL facility at Erlangen (Germany). [PWR]

Description: Flow velocities in the downcomer at the PKL facility (in Erlangen, Germany) were measured by the Pulsed-Neutron Activation (PNA) techniques. This was the first time that a fully automated PNA system, incorporating a dedicated computer for on-line data reduction, was used for flow measurements. A prototype of a portable, pulsed, high-output neutron source, developed by the Sandia National Laboratories for the US Nuclear Regulatory Commission, was also successfully demonstrated during this test. … more
Date: March 1, 1982
Creator: Kehler, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PHEBUS on-line aerosol monitor development test program

Description: EG G Idaho, Inc. developed an on-line aerosol monitor (OLAM) for the French PHEBUS Fission Product Project. Part of the development was to manufacture and test an OLAM prototype. This report presents the results of the testing which determined the mechanical integrity of the monitor at operating temperature and pressure and performed a preliminary test of the optical system. A series of twenty different tests was conducted during the prototype testing sequence. Since no leaks were detected, the… more
Date: March 1, 1992
Creator: Sprenger, M. H. & Pentecost, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons. [PWR; BWR]

Description: Assessment of six film boiling correlations and one single-phase vapor correlation has been made using data from 22 steady state upflow rod bundle tests (series 3.07.9). Bundle fluid conditions were calculated using energy and mass conservation considerations. Results of the steady state film boiling tests support the conclusions reached in the analysis of prior transient tests 3.03.6AR, 3.06.6B, and 3.08.6C. Comparisons between experimentally determined and correlation-predicted heat transfer … more
Date: March 1, 1982
Creator: Yoder, G. L.; Morris, D. G.; Mullins, C. B.; Ott, L. J. & Reed, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of aging degradation of structural components

Description: Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport reactor, as well as thermal embrittlement of CF-8 cast stainless steel components from the Shippingport and KRB reactors, has been characterized. Increases in Charpy transition temperature (CTT), yield stress, and hardness of the NST material in the low-temperature low-flux environment are consistent with the test reactor data for irradiations at < 232{degrees}C. The shift in CTT is not as severe… more
Date: March 1, 1992
Creator: Chopra, O. K. & Shack, W. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Remote characterization of spent LWR fuel for geologic disposal demonstrations

Description: State-of-the-art hot cell examination techniques are being used to evaluate spent fuel performance during exposure to simulated geologic repository environments. Forty-five pressurized light water reactor fuel rods were examined prior to emplacement in geologic disposal tests. Sufficient data were collected on both cladding and fuel to provide a basis, along with post-test examination data, for assessing the ability of the spent fuel to retain radionuclides.
Date: March 1, 1980
Creator: Davis, R. B.; Fish, R. L.; Pasupathi, V. & Stellrecht, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reactor-specific spent fuel discharge projections, 1987-2020

Description: The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by… more
Date: March 1, 1988
Creator: Walling, R. C.; Heeb, C. M. & Purcell, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mixed oxide conversion facility alternative conceptual designs. [Coprecipitation-direct calcination (COPRECAL)]

Description: Allied-General Nuclear Services recently performed studies to evaluate alternative proliferation-resistant flowsheets of the uranium-based LWR fuel cycle. The alternatives evaluated consist of coprocessing schemes with either a gamma or a heat spike added. A literature search and evaluation were performed to select a process technology for mixed oxide coconversion. The COPRECAL process was chosen as the most suitable conversion process technology. Three alternative mixed oxide conversion facili… more
Date: March 1, 1980
Creator: Thomas, L. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radioactive materials released from nuclear power plants. Annual report 1978

Description: Releases of radioactive materials in airborne and liquid effluents from commerical light water reactors during 1978 have been compiled and reported. Data on soild waste shipments as well as selected operating information have been included. This report supplements earlier annual reports by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1978 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized.
Date: March 1, 1981
Creator: Tichler, J. & Benkovitz, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRDM Reliability Study. [Control Rod Drive Monitors (CRDM)]

Description: During the checkout of the Control Rod Assembly (CRA) control system, a fault occurred which could potentially drive all four CRA's at speeds >2''/min. Subsequent experimental tests were performed to purposely identify attainable rod speeds as a function of supplied voltage. Results indicated a rod speed of up to 29.7''/min was attainable at 100 volts. The LOFT Technical Specifications (Section 3.10.3.1) limit the voltage at the stators of the CRDMs to a maximum of 90 volts which will preclude … more
Date: March 1, 1978
Creator: Close, J. A.; Cooper, C. H.; Hunt, G. L. & Atkinson, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical heat-flux experiments under low-flow conditions in a vertical annulus. [PWR; BWR; LMFBR]

Description: An experimental study was performed on critical heat flux (CHF) at low flow conditions for low pressure steam-water upward flow in an annulus. The test section was transparent, therefore, visual observations of dryout as well as various instrumentations were made. The data indicated that a premature CHF occurred due to flow regime transition from churn-turbulent to annular flow. It is shown that the critical heat flux observed in the experiment is essentially similar to a flooding-limited burno… more
Date: March 1, 1982
Creator: Mishima, K. & Ishii, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mitigation of biofouling using coatings, year 2. Quarterly progress report No. 2. [PWR; BWR]

Description: Objectives of this project are to evaluate benefits associated with control of the surface energetic properties of materials used in heat exchangers; and to identify preferred ranges of these surface conditions that minimize deposits of biological fouling known to deteriorate heat exchange efficiencies in cooling water systems. The technical approach employed uses special diagnostic plates in novel flow cells where fluid flow conditions can be well-controlled, modifying the surface chemistry an… more
Date: March 15, 1982
Creator: Meyer, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel performance annual report for 1983. Volume 1

Description: This annual report, the sixth in a series, provides a brief description of fuel performance during 1983 in commercial nuclear power plants. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to additional, more detailed information and related NRC evaluations are included.
Date: March 1, 1985
Creator: Bailey, W.J. & Dunenfeld, M.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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