Topics: DTIC Archive, BELL, HOWARD, CALIFORNIA UNIV BERKELEY MATERIALS RESEARCH LAB, *BISMUTH, *LIQUID...
A description of the design and operation is given of an ion exchange-based desalting plant designed to treat artesian water for use in the VVR-M reactor.
Topics: DTIC Archive, DEPARTMENT OF THE NAVY WASHINGTON DC, *LIGHT WATER REACTORS, *DESALINATION, WATER...
The paper is a review of the primary investigations of the use of high boiling organic fluids as coolants and moderators in nuclear reactors. Results of radio-chemical, thermo-physical, corrosive, and neutron-physical investigations are discussed. The paper furnishes data covering the use of destructive hydrogenation for the regeneration of products of radiolysis of organic coolants.
Topics: DTIC Archive, Aleksenko, Yu N, DEPARTMENT OF THE NAVY WASHINGTON DC, *REACTOR COOLANTS, *REACTOR...
Contents: TASK 2 - Liquid metal tubing - converter bond General approach Alumina coatings Brazing studies Conclusions TASK 3 - Thermal transport analysis Heat rejection Reactor characteristics TASK 4 - Series unit loop test General loop configuration Main heater Heat sink Surge tank Thermionic generators
Topics: DTIC Archive, AEROJET-GENERAL NUCLEONICS SAN RAMON CA, *ELECTRIC POWER PRODUCTION, MATERIALS, HEAT...
When a liquid containing dissolved gas is subjected to the oscillating pressure of an acoustic wave, gas bubbles can form by the process of rectified diffusion. It is shown that the rate of rectified diffusion can be determined even when the diffusivity of the dissolved gas is not known since the diffusion coefficient can be related to the coefficient of viscosity of the liquid. The rate of rectified diffusion of argon in liquid sodium is evaluated in this way.
Topics: DTIC Archive, Plesset, Milton S, CALIFORNIA INST OF TECH PASADENA DIV OF ENGINEERING AND APPLIED...
Topics: DTIC Archive, Bolwell, Harry J, COMBUSTION ENGINEERING INC NEW YORK, *NUCLEAR POWER PLANTS,...
The Modular Modeling System (MMS) was developed for the study of the thermal hydraulic performance of pressurized water reactor plants at steady state and during some slowly varying transients. To determine the limits of transient severity this code can endure, two experiments conducted at the Loss of Fluid Test (LOFT) facility were simulated using the IBM/CMS computer. These experiments are a small break loss of coolant accident (Experiment L3-5) and an excessive steam generator load increase...
Topics: DTIC Archive, Doty,Charles V, PENNSYLVANIA STATE UNIV UNIVERSITY PARK COLL OF ENGINEERING,...
A method of determining pressure changes in a two-phase water system is presented. Two applications are given which pertain to the design of nuclear reactor systems. The method utilizes information obtained from sample calculations to enter a chart from which the pressure can be readily determined. In addition, an analytical approach is taken and an equation derived which describes pressure changes also, but less accurately than the graphical method.
Topics: DTIC Archive, Comtois, W. H., COMBUSTION ENGINEERING INC WINDSOR CT, *PRESSURE MEASUREMENT, *TWO...
The unusual operating conditions of nuclear power reactors necessitate the use of unusual coolants. Thus, one desires a coolant which possess a low cross section for absorbing neutrons, good heat-transfer efficiency, a low melting point and a high boiling point. The element gallium possesses some of the requisite properties. It is a unique material, having a very low melting point, and a very high boiling point. Being a liquid metal, the heat transfer characteristics would be good, though not...
Topics: DTIC Archive, Jaffee, R. I., TECHNICAL INFORMATION SERVICE (AEC) OAK RIDGE TN, *GALLIUM, *REACTOR...
It is well known that any neutron-producing device generates induced radioactivity as a by-product of its operation. In the case of nuclear reactors, the induced radioactivity includes fission and activation products. The overall focus of this study is the build up of induced radioactivity in the coolant of metal cooled reactors as well as the evaluation of other physical and chemical properties of such coolants. The objectives of the thesis are two fold. The first objective is to independently...
Topics: DTIC Archive, Can, Levent, NAVAL POSTGRADUATE SCHOOL MONTEREY CA, *CHEMICAL PROPERTIES, *PHYSICAL...
Analyses of a postulated loss of coolant accident (LOCA) for the MH- 1A Nuclear Power Plant are presented for large and intermediate size breaks in the primary system. Methods and assumptions consistent with AEC Interim Acceptance Criteria were used in evaluating the performance of the Emergency Core Cooling System (ECCS). The computer codes RELAP-3 for reactor system blowdown and THETAl-B for fuel element heatup were used to perform these calculations at a core power of 49.5 MW(t). The results...
Topics: DTIC Archive, Gignilliat, Henry C, ARMY ENGINEER REACTORS GROUP FORT BELVOIR VA ENGINEERING DIV,...
Recently, attention has been drawn to the viability of using S-CO(2) as a working fluid in modern reactor designs. Near the critical point, CO2 has a rapid rise in density allowing a significant reduction in the compressor work of a closed Brayton Cycle. Therefore, 45% efficiency can be achieved at much more moderate temperatures than is optimal for the helium Brayton cycles. An additional benefit of the S-CO2 system is its universal applicability as an indirect secondary Power Conversion...
Topics: DTIC Archive, Freas, Rosemary M, MASSACHUSETTS INST OF TECH CAMBRIDGE, *NUCLEAR REACTORS,...
The PM-3A Type 1 Serial 2 core was removed from the reactor because of increasing fission product levels in the primary coolant. This increase in level was believed associated with defects in the 347 stainless steel fuel cladding. This examination was to locate defects and determine their cause. Cracks were found to penetrate the outer clad of the tubular elements in high- performance regions. All cracks were longitudinal and intergranular, generally starting at the outer tube surface and...
Topics: DTIC Archive, Brown, John B, BATTELLE MEMORIAL INST COLUMBUS OH COLUMBUS LABS, *ELECTRIC POWER...
The AF NETF, a 10 MW water-cooled research reactor, monitors the conductivity of its coolant to detect erosion/corrosion of its structural systems and fuel element failure. When a gradual increase in this conductivity sent it above the defined limit, a study was initiated to identify the contaminants and examine the source and removal processes. The major contaminant, Na23, was traced to an in-leakage from the secondary to the primary coolant systems through the heat exchanger interface. Minor...
Topics: DTIC Archive, Baker, J W, AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OH SCHOOL OF ENGINEERING,...
This report presents designs of two compact, unattended nuclear power utilizing H-Rho reactor control. One plant is a 100-kilowat(e) system with Stirling cycle conversion; the other is a conduction-cooled 10-kilowatt(e) thermoelectric system. The conduction system is based upon current technology, while the Stirling system requires an extended life Stirling engine for optimal performance. In addition to the performance the results of parametric studies of system operation at other power levels...
Topics: DTIC Archive, Magladry, R, ISOTOPES INC MIDDLE RIVER MD NUCLEAR SYSTEMS DIV, *NUCLEAR POWER PLANTS,...
IN CONNECTION WITH THE KNOWN PRESENCE OF Na2O in liquid sodium, which is often employed as a heat carrier, the possibility of electrolytic transfer of oxygen in the medium arises. This article describes an experimental check on this phenomenon conducted by the dc polarization method; the experiments were run at 300 C. An accumulation of transferred oxygen was actually determined in the anodic part of the molten metal. The findings confirmed the initial assumption that transfer is caused by...
Topics: DTIC Archive, LIBRARY OF CONGRESS WASHINGTON DC AEROSPACE TECHNOLOGY DIV, *SODIUM, *OXYGEN,...
The pile utilizes a graphite core containing U(233) suspended in an intermetallic compound of lead and tin. This combination is assumed to contain uranium, lead, and tin, in atom percents of 3.75, 83.25, and 13, respectively. Through the core and heat exchanger is circulated a coolant solution of Th(232) and liquid Bi, in 4 and 96 atom percents respectively, part of which is diverted into a blanket area, where the thorium is utilized for breeding. Of course, breeding will take place in the...
Topics: DTIC Archive, Fleck, J., BROOKHAVEN NATIONAL LAB UPTON NY, *NUCLEAR ENGINEERING, *BREEDER REACTORS,...
This study uses the RELAP4/MOD5 Computer Code to analyze the effects of critical flow modeling on the thermal-hydraulic transient response of a General Electric boiling water reactor to a major primary coolant line rupture. Included is a presentation of the equations, assumptions, and limitations of the critical flow models available for use in RFLAP4. Additionally, an evaluation of a temporary solution to a RELAP4 coding error associated with stagnation properties calculation is presented.
Topics: DTIC Archive, Carle,Mark Vearil, NAVAL POSTGRADUATE SCHOOL MONTEREY CA, *COMPUTERIZED SIMULATION,...
Partial Contents: Literature Reviews of: Tilting pad and turbulent hydrostatic journal bearings for nuclear main coolant pumps, and of Vibrations and stability of mechanical systems: Part 3; Book reviews; and Abstracts from the current literature.
Topics: DTIC Archive, Nagle-Eshleman, J, NAVAL RESEARCH LAB WASHINGTON DC SHOCK AND VIBRATION INFORMATION...
Partial contents: Squeeze-film Damping of Rotor-dynamic Systems; Literature review--Leakage flow-induced vibrations of reactor components; and Abstracts from the Current Literature.
Topics: DTIC Archive, Nagle-Eshleman, J, NAVAL RESEARCH LAB WASHINGTON DC SHOCK AND VIBRATION INFORMATION...
The growing interest in controlled nuclear energy has been accompanied by a requirement for increased knowledge of the behavior of materials under high energy density conditions. The efficiency of fission reactors can be improved with coolant fluids capable of maintaining large molecular densities at high temperatures and moderate pressures. The high melting points of most of metals place the liquid state at temperatures too high for easy experimental investigation. A relatively complete...
Topics: DTIC Archive, Hodgson, William Mark, LAWRENCE LIVERMORE NATIONAL LAB CA, *THERMODYNAMICS,...
Corrosion product activation and transport in Light Water Reactors is a well recognized, but poorly understood phenomenon, despite studies conducted world-wide for the past 20 years. In an effort to determine the mechanistic parameters which produce, release the transport activated corrosion products throughout a typical Pressurized Water Reactor (PWR), MIT has undertaken the construction of a model pressurized water loop to simulate the thermal hydraulic characteristics of a representative...
Topics: DTIC Archive, Wicks, James H , Jr, MASSACHUSETTS INST OF TECH CAMBRIDGE DEPT OF OCEAN ENGINEERING,...
An investigation was made of the transformations which can occur with reactor materials exposed to biphenyl and evaluated the effect of such factors as the presence of admixtures and the degree of pyrolytic decomposition. The hydride mechanism of corrosion was investigated first with respect to uranium and its alloys with molybdenum. The corrosion tests with biphenyl were carried out in containers made of 1Kh18N9T stainless steel. The changes undergone by a variety of metals, alloys and oxides...
Topics: DTIC Archive, Bychkov, Yu F, FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OH, *CORROSION, *REACTOR...
Topaz II is a Russian made nuclear powered satellite purchased by the
Topics: DTIC Archive, Raney, Elisa A., NAVAL POSTGRADUATE SCHOOL MONTEREY CA, *NUCLEAR POWER PLANTS,...
INFORMATION (based on foreign sources) on the properties of liquid metals used as coolants in nuclear reactors is presented. The topics discussed are: (1) heat transfer (in the liquid phase or during boiling and condensation) ; (2) the interaction of liquid metals with structural materials; (3) methods for removing impurities from liquid metals; and (4) the peculiarities of design and operation of systems with liquidmetal coolants. Requirements to be met by heattransfer media used in nuclear...
Topics: DTIC Archive, ANDREYEV, P A, FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OH, *NUCLEAR POWER PLANTS,...
Models based on the TDS thermionic diode model were developed for TOPAZ II and SPACER nuclear power systems. Several parameter studies were conducted with the TOPAZ II model. These determined system performance and efficiency while varying the following: (1) Coolant flow inlet temperatures. (2) Rate of coolant temperature change. (3) Power profile of the core. (4) Cesium reservoir temperature. Analysis of results indicate the model accurately represented the TOPAZ II system, underestimating...
Topics: DTIC Archive, Habedank, Otto D, AIR FORCE INST OF TECH WRIGHT-PATTERSONAFB OH SCHOOL OF...
A detailed program of analytical and experimental investigation into the technical feasibility of the H-Rho nuclear reactor control system and tetraphosphorous trisulfide (P4S3) as a reactor coolant are presented in this study. The H-Rho control system investigation includes determinations of hydrogen transport (permeability) through porous bodies of zirconium hydride and uranium zirconium hydride as well as the absorption-desorption of hydrogen within the hydride bodies. The effects of...
Topics: DTIC Archive, Magladry, R, MARTIN MARIETTA AEROSPACE BALTIMORE MD NUCLEAR DIV, *REACTOR SYSTEM...
The McMaster Nuclear Reactor is a conventional pool-type research reactor. The reactor is currently licensed to operate at a maximum power level of one megawatt. The design power level is five megawatts. However, cooling capacity has been installed for only one megawatt. The reactor is fueled with 18 plate MTR type fuel elements. Each standard fuel element contains approximately 196 grams of U235 at 93% by weight enrichment.
Topics: DTIC Archive, Fleming, W. H., MCMASTER UNIV HAMILTON (ONTARIO), *REACTOR OPERATION, *RESEARCH...
Topics: Radio Program, Nuclear reactor coolants
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