From second European conference of TRIGA reactor users; Pavia, Italy (13 Sep 1972). In TRIGA Owners' Conference. A computer program is presented for calculating the reactivity worth of control rods. Procedures for measuring the reactivity worth of FRN Reactor control rods are described. (DCC)

Since the first full power operation in September 1972 up till now (Dec. 1973) the TRIGA Mark III reactor FRN has run more than 500 MWh in steady state operation and has been pulsed for 265 times. During startup experiments, neutron- and gamma-flux mapping has been performed with special technical devices in the core and in several ...

FRN Archive 2005-2006 FRN Archive 2001-2004 FRN Archive 1996-2000 Databases Software Video Video Help NIOSH Programs NIOSH Program Portfolio National Academies Evaluation of...

The Sandia Pulsed Reactor III (SPR III) is being used as the pumping source for evaluation of energy deposition and laser physics in gas mixtures for reactor-pumped lasers. The test apparatus includes moderating and reflecting materials both near and in t...

The report presents findings and concerns resulting from a Technical Safety Appraisal of Sandia National Laboratories' Sandia Pulse Reactor III (SPR III) and the Annular Core Research Reactor (ACRR). It was conducted by an appraisal team for the Departmen...

... Author : ARMY ENGINEER REACTORS GROUP FORT ... Descriptors : *ELECTRIC POWER PRODUCTION, *REACTOR CORES, REACTOR FUELS ...

... Applications to the Processing of III-V Materials ... have been carried out in plasma reactors with and ... intensity upon addition of NO2 in the flow reactor. ...

In the last part of the article the formation of radiation damage is considered in the evaluation of the effects of reactor radiation. (tr-auth)

Fast burst reactors (FBRs), such as SPR III, and pool-type reactors, such as the University of Illinois TRIGA and the Sandia Annular Core Research Reactor, are used as sources of neutrons and/ or gamma rays in transient radiation effects in electronics (T...

TRIGA Mark-II reactor has been primarily utilized for the fundamental reactor experiments, which were offered to the junior and senior students of Seoul National University and Hanyang University for 328 hours. The annual operating time of this reactor wa...

Research and development activities are reported on EBWR, BORAX-V, ZPR- III, ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Thermal- and fast-reactor safety studies are summarized. Applied nuclear and reactor physics, reactor fuels development, reactor materials development, ...

The purpose of this project was to update the environmental impacts from the uranium fuel cycle for select advanced (GEN III+) reactor designs.

... PLANT CATEGORY III SYSTEM/COMPONENT TESTS,. ... NUCLEAR ENGINEERING, ENVIRONMENTAL TESTS), REACTOR COOLANTS, HEAT ...

This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, ...

UWMAK-III is a conceptual power reactor design study aimed at understanding the problems associated with using advanced technologies and several new or different design approaches in tokamak systems. Advanced technologies studied include the use of the mo...

Volume III of this report examines the design evolution of domestic light water reactor fuel. The fuel of each vendor is individually described. Tables and figures detail the fuel's design parameters. A data base of this nature is required for the design ...

The determination of the subcadmium flux profile (neutrons with energy between 0 and 0.4 eV approximatley) in the core of the reactor Triga Mark III in the Nuclear Center of Mexico was made. The technique used for that purpose consists in placing alternat...

Progress on reactor programs and in general engineering research and development programs is summarized. Research and development are reported on water-cooled reactors including EBWR and Borax-V, sodium-cooled reactors including ZPR-III, IV, and IX, Juggernaut, and EBR-I and II. Other work included a ...

... Most of the PISC test assemblies and structure pieces are representative of (or come from) nuclear reactor components. (Author). ...

The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with ...

... ADEQUATE SYSTEM SENSITIVITY; AND (D) HIGH BACKGROUND NOISE WAS OBSERVED WHEN ALL FOUR REACTOR COOLANT PUMPS ...

Research and development activities are reported on Borax V, ZPR- III, - VI, and -IX, EBR-I, EBR- II, and FARET. Reactor technology investigations are reported in reactor physics, reactor fuel development, viewing systems, heat engineering, and chemical separations. Research on advanced systems is reported ...

Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, ...

The updating of the instruments as the operation console of the TRIGA Mark III Salazar Reactor is based on the use of a personal computer that works as data acquisition and control device. The power changes on the reactor have been made through the insert...

For two years of 1990 and 1991, the safety of TRIGA Mk-II and III reactor has been re-evaluated. For this, domestic rules on research reactors has been reviewed, and as it was judged that standards on research reactors in USA is applicable to our ones it ...

The number of particles emitted by a fission reaction is proportional to the number of fissions generated in the reactor nucleus, what in turn are proportional to the power level of such reactor; this indicates that it is possible could measure the reacto...

The TSM (Tubular Solid Moderator) critical experiment for the HTRE-III reactor is described. The designs of the control system, moderator, diffusion barrier, matrix con figurations, and general makeup of the TSM are outlined. The specifications of TSM and HTRE-III are compared. (T.F.H.)

The current study employed a modified gambling task, in which probabilistic cues were provided to elicit positive or negative expectations. Event-related potentials (ERPs) to "final outcome" and "probabilistic cues" were analyzed. Difference waves between the negative condition and the corresponding positive condition were examined. The results confirm that feedback related negativity ...

provisions of section 401 of the Intergovernmental Cooperation Act of 1968, as amended. FRN Cite 48 FR 29340, June 24, 1983. 1204 Subpart 16 ...

Dec 7, 2008 ... FRG, FEDERAL REPUBLIC OF GERMANY (WEST GERMANY). FRGF, FLIGHT REMOVABLE GRAPPLE FIXTURE. FRN, FRAME ROUTING NETWORK ...

Feedback-related negativity (FRN) is sensitive to both monetary loss and evaluation of the correctness of a response. This study used a gambling task that required participants to choose between two cards that were unpredictably associated with monetary gains or losses. Feedback stimuli then indicated gain or loss, and the correctness of the participant's choice. Greater ...

Effectiveness of Tailored Occupational Safety and Health Information on the World Wide Web: Increasing Knowledge and Changing Behavior of Residential Building Construction...

... may be sought for its own intrinsic cultural (in ... role-playing exercises that deal with contrasting cultural values and assumptions ... Aside fr--n the value ...

Jun 16, 2011 ... Source: Forest Research Note NE-132. ... Station ID: FRN-NE-132. Description: Rhododendron (Rhododendron maximum L.) is a large shrub that ...

... 3 Page 9. abdominal aorta and vena cava. A ... performance of thoracic aorta and pulmonary artery tissue isolated frnA ::-2ts adapted to ...

Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, Treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Fast Source Reactor, EBWR, Argonne Advanced Research Reactor, ...

Progress is reported on development of liquid metal and water cooled reactors. Details are included concerning the EBWR, Borax V, ZPR-III, ZPR-VI, AFSR, EBR-I, EBR-II, and FARET. Developments in general reactor technology are reported in applied reactor physics, reactor fuel and ...

TCODE can be used for either near-term experimental reactors or for commercial reactors. The code provides options for items that may be included in a commercial reactor such as a divertor, neutral beam heating, and a breeding blanket. The code was used to calculate tritium and vacuum system parameters for the near term ...

Reactor and general engineering research progress is summarized for EBWR, BORAX-V, ZPR-III, ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Fast and thermal reactor safety studies are described. Nuclear technology investigations are discussed for applied nuclear physics, reactor fuels and materials development, heat ...

The great difficulties which have to be overcome to make the production of power by fusion possible have led to proposals to develop a nuclear reactor which will utilize fission and fusion reactions. According to this hybrid concept a fusion reactor will be placed inside a hollow fission reactor. Potential technical advantages of the ...

At present, two research reactors are operated at the Korea Atomic Research Institute, namely, one being a TRIGA Mark-II reactor of 250-kW power rating and the other a TRIGA Mark-III reactor of 2 MW, both of General Atomic design. Design characteristics and operations for the reactors are ...

Rolo Naranjo rolo@fctn.isctn.edu.cu Application to mechanical systems. NPP Research Reactor (TRIGA MARK to mechanical systems. NPP Instability case of the Nuclear Reactor #12;Research REACTOR-TRIGA MARK-III Ing. Alberto in Thermoelectrical PP - Power instability in the N.Reactor - Internal ...

Generalized plots of criticality requirements and plutonium production rates have been made for bare, homogeneous reactors, applicable to circulating and boiling types. With this information the influence of vapor within a reactor upcn the operating conditions can be determined, which will aid in the economic evaluation of boiling ...

A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are ...

, Aliens, kommersialisering och deltagande. Film: Alien I: Den �ttonde passageraren CYBORG IMAGES 23 November, kl. 17:15 � ca. 20:30 F�rel�sning:The Dawning of the Cyborg has arrived. Anna �berg fr�n KTH. CYBORG IMAGES The Dawning of the Cyborg has arrived. Anna �berg fr�n KTH talar om cyborgar

The feedback-related negativity (FRN), an event-related potentials (ERPs) component reflecting activity of the anterior cingulate cortex (ACC), has been shown to be modulated by feedback expectancy following active choices in feedback-based learning tasks. A general reduction of FRN amplitude has been described in observational feedback learning, raising ...

ARIES-III is a D-He{sub 3} reactor design study. It is found that the organic coolant is well suited for the D-He{sub 3} reactor. This paper discusses the unique features of the D-He{sub 3} reactor, and the reason that the organic coolant is compatible with those features. The problems associated with the organic ...

An efficient organic cooled low activation ferritic steel first wall and shield has been designed for the D-{sup 3}He power reactor ARIES-III. The design allows removal of the large surface heat load without exceeding temperature and stress design limits. The structure is expected to last for the whole reactor life. The major concerns ...

...site of a nuclear power reactor which does not have an...site of a nuclear power reactor that is not authorized...1986, Title III, Pub. L. 99-499 or other State...1986, Title III, Pub. L. 99-499, with respect...100, of a nuclear power reactor licensed for...

A method for improving Mg doping of Group III-N materials grown by MOCVD preventing condensation in the gas phase or on reactor surfaces of adducts of magnesocene and ammonia by suitably heating reactor surfaces between the location of mixing of the magnesocene and ammonia reactants and the Group III-nitride ...

Calculations have been made on the sensitivities of fast reactor data to changes in the capture cross section of iron. ENDF/B-III neutron data library has been used for calculations on the FRO assembly on ZPR-III/32 and on the inner core of ZPPR-2. The SPENG library has been used for the ZPR-III cores 29, ...

Sandia National Laboratories operates two reactors which fall under US Environmental Protection Agency regulations for emission of radionuclides to the ambient air. These reactors are: (1) the Annular Core Research Reactor, a pool-type reactor and (2) the Sandia Pulsed Reactor ...

Research and development activities are reported on Borax-V, ZPR-III No. 44, ZPR-VI No. 1, ZPR-IX, EBR-I, EBR-II, EBWR, Treat, Faret, Rapsodie Reactor, critical assemblies, fast reactors, Argonne Low Power Research Reactor, Topsy, Godiva, Argonaut Reactor, Argonne Advanced Research ...

By recording the feedback-related negativity (FRN) in response to gains and losses, we investigated the contribution of outcome monitoring mechanisms to age-associated differences in probabilistic reinforcement learning. Specifically, we assessed the difference of the monitoring reactions to gains and losses to investigate the monitoring of outcomes according to task-specific ...

Individuals with high-functioning autism often display deficits in social interactions and high-level cognitive functions. Such deficits may be influenced by poor ability to process feedback and rewards. The feedback-related negativity (FRN) is an event-related potential (ERP) that is more negative following losses than gains. We examined FRN amplitude in ...

A methodology has been developed to provide system reliability criteria based on an assessment of the potential radiological hazards associated with a fusion reactor design and on hazard constraints which prevent fusion reactors from being more hazardous than light water reactors. The probabilistic consequence analyses, to determine ...

Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-VII, Faret, EBR-I, EBR-II, Borax-V, Treat, Fermi Fast Breeder Reactor, magnetohydrodynamic cells, thermionic cells, rocket fuel test reactor, and HiC critical assembly. ...

A description of fast reactor types is given and the objectives of the AEC program on fast reactors are outlined. General research and development programs completed and in process on physics, fuel and materials, heat transfer, fluid flow, coolant chemistry, reactor safety, and components and systems are discussed. ...

The current development status of the sodium graphite reactor concept is described. The development history is summarized, and all important areas of development are discussed. The discussion of the SGR program is broken into three categories: (1) general research and development, dealing with reactor physics, fuels and materials, components, ...

Calculations of heat generation within the thermal shields and the vessel wall of the SPERT-III Reactor are presented. The calculations were performed to check an earlier estimate and assure adequacy of the shield design prior to installation in the reactor. The data are derived from an evaluation of the heat generated by ...

Workshop III. Scenarios for Aviation's Growth: Opportunities for. Advanced Technology: ... Battery-Powered (considered too heavy - Take-off power ... ( Reactor is cool/safe). No CO. 2 produced during reactor operation. ...

A comparison is made of water decomposition, separation factors, and contamination problenas in the cooling systems of the Vallecitos Boiling Water Deactor, the Experimental Boiling Water Reaetor, and the Boiling Reactor Experiment-III. (C.J.G.)

Currently, KAERI operates TRIGA Mark-II and TRIGA Mark-III research reactors as a general purpose research and training facility. As these are, however, situated at Seoul office site of KAERI which is scheduled to be transferred to KEPCO as well as 30 MW ...

This document is volume 3 of a three-volume set detailing a multistage research study on the comparison of various advanced fission reactors and evaluation of alternate strategies for their development in the USA through the year 2020. This volume present...

Several kinds of radioisotope were produced by neutron irradiations using TRIGA Mark II (250 KW) reactor. Owing to the shut down of TRIGA Mark III reactor it could not be used for radioisotope production during 1978. The amount of radioisotope production ...

A preliminary safety analysis of the post operational questions regarding the use of reactor power systems for an orbital space station is presented. The objective of the analysis is to provide a quantitative measure of the risk to man from the disposal o...

This report describes the optimization of the RISK III mathematical model, which provides risk assessment for the use of a plutonium-fueled, fission reactor in space systems. The report discusses possible scenarios leading to radiation releases on the gro...

Phase I will fit an existing reactor to a simplified reaction chamber to demonstrate high-growth rate (> 1m/hour) ALE of gallium arsenide. ...

Standards for the mandatory testing and inspection procedures directed towards the maintenance of critical reactor equipment at the Hanford N Reactor are presented. Volume III covers the following: boiler steam supply system, demineralized water system, p...

Organic insulators, such as polyimide, epoxy resins and fiber reinforced epoxies, (FRP), are irradiated in the fission reactor at about 5 K and their mechanical properties are measured in liquid helium without warm-up. At the very low temperature, the mat...

The amount of energy deposited by the radiation in an absorber system, in radiation dose units was established, the Reactor Triga Mark III core of the Mexican Nuclear Center was used as radiation source. The calorimetric method was used, which gives us a ...

The fatigue design curves for structural materials specified in Section III of the ASME Boiler and Pressure Vessel Code are based on tests of smooth polished specimens at room temperature in air. The effects of light water reactor (LWR) coolant environmen...

Conceptual Shielding Configuration III for the Gas-Cooled Fast Breeder Reactor (GCFR) was analyzed by performing global calculations of neutron and gamma-ray fluences and correcting the results as appropriate with bias factors from localized calculations....

... (4) Manifold reactors. (5) Catalytic... VII. Air Inlet Components. (1) Carburetor...Engine Mechanical Components. (1) Valve train... III. Air Inlet Components. (1) Air cleaner... (2) Manifold reactors. (3)...

... (4) Manifold reactors. (5) Catalytic... VII. Air Inlet Components. (1) Carburetor...Engine Mechanical Components. (1) Valve train... III. Air Inlet Components. (1) Air cleaner... (2) Manifold reactors. (3)...

...the health and safety of the public. For the purposes of this part, such equipment or devices include only: (i) Naval propulsion reactors; (ii) Military reactors and power sources that use special nuclear material; (iii) Tritium production...

The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than {+-} 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to {+-} 1.5%. The procedures are equally applicable to the Mark I, Mark II and ...

The aim of the experimental programs about to be carried out in the NESTOR and HECTOR reactors is to provide relevant experimental information on AGR III type lattices, in order that the proposed methods of neutronic calculations may be comprehensively te...

The TACT III computer code simulates the movement of radioactivity released from a reactor core as it migrates through user-defined regions (nodes) of the containment, is immobilized by filters and sprays, and leaks to the outside environment. The user's ...

The Doublet III experiment has as its primary goal the test of confinement of noncircular cross section toroidal plasmas in the regime where trapped ion effects may be operative. The importance of the experiment stems from the potential of noncircular cro...

An analysis of a Mark III reactor containment vessel subjected to a uniformly increasing internal pressure and gravity loads is carried out in order to ascertain the load carrying capacity of the structure under hydrogen burn. The analysis is conducted by...

The theoretical and measured mechanical behavior of SPR-III during pulse operation is described. The core was instrumented with noncontacting displacement transducers and the oscillations of the fuel plates and support structure were recorded. A method fo...

A method was developed for determining trace uranium in aqueous wastes from processing nuclear reactor fuels. Uranium (VI) is determined colorimetrically with the metal indicator Arsenazo III, after removing fission product interferences by solvent extrac...

Section III ASME Code Cases oriented to design and fabrication of reactor coolant pressure boundary components that are generally acceptable to the NRC staff for implementation in the licensing of LWR plants are listed.

The regulatory guide lists those Section III ASME Code Cases oriented to reactor coolant pressure boundary component materials and testing that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.

The regulatory guide lists those Section III ASME Code Cases oriented to reactor coolant pressure boundary component design and fabrication that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.

The SPR III bare cavity spectrum and integral parameters have been determined with 24 measured spectrum sensor responses and an independent, detailed, MCNP transport calculation. This environment qualifies as a benchmark field for electronic parts testing.

The document is Part III of the Institute study of the ATWS question. The frequencies of the various events which have led to a reactor scram are documented from the nuclear power plant records. Some of these events, in the absence of scram, could lead to...

To compare the theoretical results of the calculations of the shielding of the Melusine Reactor with the actual activity levels found around the reactor, some measurement results obtained during 1-Mw operation are presented. The measurements show that the activity levels do not exceed the tolerance levels and agree with the theoretical predictions ...

Two solid-metal fast burst type reactors (SPR II and SPR III) are operated at the Sandia Pulsed Reactor Facility. Since startup of the reactors, oscilloscope traces have been used to record (by camera) the pulse (power) shape while log N systems have meas...

The ARIES-3 reactor study is an extensive examination of the viability of a D-(sup 3)He-fueled commercial tokamak power reactor. Because neutrons are produced only through side reactions, the reactor has the significant advantages of reduced activation of...

Detailed descriptions of a boiling heavy water reactor plant, a gas- cooled heavy water moderated reactor plant, and a pressurized heavy water reactor plant are presented. The information is given as a part of the comparative evaluation of large nuclear electric power generating plants. (J.R.D.)

The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed...

This supplement discusses the emergency shutdown device installed on the ML-1 reactor. It is concluded that the device is not required for safe ML-1 reactor operation and that, in consideration of undesirable characteristics, it should be removed. This action is justified by the current state of knowledge of the neutronic characteristics of the ML-1 ...

... CHEMICALS, WIND, EFFICIENCY, COSTS, FUELS, SOLAR ENERGY, PLANNING, LIFE CYCLE COSTS, REACTOR FUELS, ENERGY STORAGE ...

Test results on newer stabilized fuel elements indicate that uranium ... These data indicate a choice between silicon carbide and silicon nitride. ...

... brief description of the SM-1 Nuclear Power Plant ... system setpoints and operating limits of the reactor. ... A parametric analysis is made of the thermal ...

... PART III. NUCLEAR REACTORS,. Corporate Author : RAND CORP SANTA MONICA CALIF. Personal Author(s) : Arkhipov,M. Report Date : 1935. ...

Separate abstracts were prepared for the papers presented in the area of: combustion, experiments and analysis.

... reactor vessel after each use to minimize arsenic buildup (which readily ... contact between the indium compound and the hydrides until they enter the ...

Not Available Present address: University of Missouri, Research Reactor Facility, Columbia, Missouri 65201, USA.

... rotated at different speeds. The reactor has a 1/4" inject tube made ... hydrogen during start up. The maximum operating temperature should never ...

Separate abstracts were prepared for 41 of the 56 papers included. Abstracts for the remaining papers have previously appeared in ERA.

... document. Page 32. Liquid Chlorine Dioxide Stirred Reactor Testing Battelle Summary Test Report iii TABLE OF CONTENTS ...

... by suspected events, and (iii) the fusion between events ... The concept has been extensively tested using ... 6 and 24 UTC; The reactor exploded on ...

Kinetic parameters for dynamic study of two different configurations, 8 and 9, both with standard fuel, 20% enrichment and Flip (Fuel Life Improvement Program with 70% enrichment) fuel, for TRIGA Mark-III reactor from Mexico Nuclear Center, are obtained. ...

The Berkeley Research Reactor went critical on August 10, 1966, and achieved licensed operating power of 1000 kW shortly thereafter. Since then, the reactor has operated, by and large, trouble free on a one-shift basis. The major use of the reactor is in service irradiations, and many scientific programs are accommodated, both on and ...

The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on ...

Fast-burst reactors are designed to provide intense, short-duration pulses of neutrons. The fission reaction also produces extreme time-dependent heating of the nuclear fuel. An existing transient-dynamic finite element code was modified specifically to compute the time-dependent stresses and displacements due to thermal shock loads of reactors. ...

As a part of the contract between the Atomic Energy Commission and Power Reactor Development Company, a critical experiment for the Enrico Fermi Reactor is to be carried out by Argonne National Laboratory. The experiment is to be done at the ZPR-III facility at the National Reactor Testing Station, Arco, ...

Following a number of first-generation fusion power plant design concepts and their subsequent analysis, a second generation of fusion reactor designs have emerged. These include three conceptual experimental power reactor (EPR) design studies and UWMAK-III, a noncircular Tokamak power reactor design. In this ...

Recent measurements at Sandia Laboratories demonstrated that a laser gas excited solely by fission products can be made to laser. The concept is explored of a subcritical nuclear driven laser (NDL) system excited by a fast pulse reactor of the Godiva type. A neutronics analysis, presented for a NDL system used with the SPR II/SPR III pulse ...

Descriptions are given of geometries and compositions of fast reactor designs and experiments reported in the literature. Each description is divided into these categories; location, rating, fuel description, reflector, control, coolant, and remarks. Some experimental data are included. The reactor descriptions presented are those of the ...

A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A ...

The tritium system design for the Fusion Power Demonstration Reactor (FPD-I, II, and III) is described. The device operates at 25% availability. For FPD-II, an engineering mode using tritium neutral beams is part of the design.

The aim of this work is to check the possibility of determining the U(IV)/U(III) ratio by electrochemical techniques in the fused LiF-BeF sub 2 -ThF sub 4 mixture, solvent of a fused salt breeder reactor. The electrochemical properties of uranium systems ...

RELAP-UK Mk III is the latest in a series of water reactor blowdown codes, closely related to the US LWR codes RELAP 3 and RELAP 4, developed in support of the Steam Generating Heavy Water Reactor. The major change over earlier versions is the introductio...

Standards and procedures for promoting the exchange of reactor physics codes are updated to Version-III status. Standards covering program structure, interface files, file handling subroutines, and card input format are included. The implementation status of the standards in codes and the extension of the standards to new code areas are ...

Experiments on the excitation of short-wavelength gas lasers have recently been performed in the central cavity of the Sandia fast burst reactor SPR-III. Small-signal gain coefficients approx.0.7%/cm were measured in XeF laser mixtures excited with either...

The multi-institutional ARIES study has completed a series of conceptual designs of tokamak fusion reactors that varies the assumed advances in technology and physics. The ARIES-III design uses a D- (sup 3)He fuel cycle and requires significant advances i...

The determination of minor and trace elements in the magnesium oxide, considered as possible ceramic material in thermonuclear fusion reactors, has been studied. The concentration ranges are 0.1 - 0.3 % for Ca, Si and Y, and at the ppm level for Al, Co, C...

A reference core Mark-III has been designed for the first conceptual design of Experimental Multi-purpose Very High Temperature Reactor plant planned in JAERI. In this report are described comprehensive fuel performance analyses of the fuel integrity and ...

There is renewed interest in the United States (U.S.) to construct new Generation III and III+ reactors within the next decade and Generation IV reactors in the future. Licensing by the U.S. Nuclear Regulatory Commission (NRC) is a significant considerati...

This report presents findings and concerns resulting from a Technical Safety Appraisal of Sandia National Laboratories' Sandia Pulse Reactor III (SPR III) and the Annular Core Research Reactor (ACRR). It was conducted by an appraisal team for the Department of Energy's Office of Safety Appraisals ...

... 313.22, 313.22) /*** SPACECRAFT POSITION WITH RESPECT TO CENTRAL BODY ..... `^jdrl|k`Zek\\himovbsuimh^vqgeldnaiTg__bf]igaeah[ec_frn|bdmPTd[b^]golgi`WXnZ ...

BackgroundActions of others may have immediate consequences for oneself. We probed the neural responses associated with the observation of another person's action using event-related potentials in a modified gambling task. In this task a "performer" bet either a higher or lower number and could win or lose this amount. Three different groups of "observers" were also studied. The first (neutral) ...

Jun 16, 2011 ... Source: Forest Research Note NE-68. ... Station ID: FRN-NE-68. Description: The presence of red rot (Fomes pini) in pruned white pine stands ...

Research suggests that the feedback-related negativity (FRN) is only sensitive to expectancy when the prediction violation is salient. To further examine this issue, we asked participants to guess which of two virtual doors hid 5 cents. Prior to and after making their guess, participants were asked whether or not they expected to win. We extracted four conditions based on ...

Previous studies have revealed that personal responsibility has an influence on outcome evaluation, although the way this influence works is still unclear. This study imitated the phenomenon of responsibility diffusion in a laboratory to examine the influence of the effect of responsibility diffusion on the processing of outcome evaluation using the event-related potential (ERP) technique. ...

Jun 16, 2011 ... Source: Forest Research Note NE-114. ... Station ID: FRN-NE-114. Description: An outbreak of the pine sawfly, Neodiprion pratti pratti ...

Nov 16, 2010 ... Station ID: FRN-NE-40. Description: Hybrid poplar plantations are established by planting dormant cuttings in close spacing, usually 4 x 4 ...

In this study, we examined whether the feedback-related negativity (FRN) is associated with both subjective and objective (model-estimated) reward prediction errors (RPE) per trial in a reinforcement learning task in healthy adults (n=25). The level of RPE was assessed by 1) subjective ratings per trial and by 2) a computational model of reinforcement learning. As results, ...

- STRUCTURE BUILDINGS � ENERGY USE AND EFFICIENCY INDUSTRY � ENERGY USE AND EFFICIENCY ENERGY SYSTEMS Smart The building as a system Process technologies Industrial biorefineries Energy efficiency and process production and industrial processes. Efficient batteries/energy storage and solar cells Catalysis

This Standard Engineering Installation Package(SEIP) provides information for the engineering and installation of TVOR facilities worldwide. Information provided consists of site survey data, siting criteria, installation specifications and instructions, ...

Jun 16, 2011 ... Source: Forest Research Note NE-134. ... Station ID: FRN-NE-134. Description: In the upper Coastal Plain and northward in New Jersey, ...

Jun 16, 2011 ... Source: Forest Research Note NE-76. ... Station ID: FRN-NE-76. Description: In 1951 a 30-acre mature stand of loblolly pine on Maryland's ...

Jun 16, 2011 ... Source: Forest Research Note NE-61. ... Station ID: FRN-NE-61. Description: In 1951 foresters at the Penobscot Experimental Forest near ...

Sep 1, 2011 ... Upper Darby, PA: U.S. Department of Agriculture, Forest Service, Northeastern Forest Experiment Station. 1-7. Station ID: FRN-NE-121 ...

. was supported in part by USPHS grant HL 21483 awarded to F.R.N. Gurd, and thanks the Foundation Stiftelsen

Jun 16, 2011 ... Source: Forest Research Note NE-86. ... Station ID: FRN-NE-86. Description: Forest tree seed crops in 1958 were considerably better than ...

Jun 16, 2011 ... Source: Forest Research Note NE-119. ... Station ID: FRN-NE-119. Description: When Virginia pine (Pinus virginiana Mill. ...

Jun 16, 2011 ... Source: Forest Research Note NE-126. ... Station ID: FRN-NE-126. Description: During a recent soil-site study of sweetgum in southern New ...

... financed by grants from the Swedish Natural Sciences Research Council and from FRN to H.G.S. When writing this paper H.G.S. was supported by the Swedish ... ...

... B. 5 CP and 5PP within 125 fsh 1 Frn-. M e thtod - Employ up and down method until 91CP and 5 PP tre ob- tained within a spread of 125 fps. ...

Jun 16, 2011 ... Source: Forest Research Note NE-130. ... Station ID: FRN-NE-130. Description: Polyhedral viruses have proved highly effective and very ...

and Recommendations: Reduce Injury & Musculoskeletal Disorder (MSD) Risk from Human- Machine Interaction�New> May 2005 5/27 Federal Register Notice: National Institute for...

Fire Fighter Fatality Investigation and Prevention Program (FFFIPP)�New Adobe acrobat icon PDF 12/13 Federal Register Notice: Mine Safety and Health Research...

Jun 16, 2011 ... Source: Forest Research Note NE-118. ... Station ID: FRN-NE-118. Description: For many years the lumber industry has been seeking improved ...

... fuor inccese ofe theut Che of Stf last 12 yernoeai- reae ... constradne th Batl Stf Trinn to USoeain,wihaseii enirnm n *a diet frn-ln exeinei ...

Jun 16, 2011 ... Source: Forest Research Note NE-98. ... Station ID: FRN-NE-98. Description: The first job in compiling streamflow data from streamflow ...

...information. The Operator shall inform the Commission on FCC Form 324 whenever there is a change of cable television system operator; change of legal name, change of the operator's mailing address or FCC Registration Number (FRN); or...

...requests dismissal of its short-form or long-form application, the Commission will dismiss...paid; or (4) The FCC Registration Number (FRN) has not been...pending another vanity call sign application with the same receipt...

...part 54, subpart F, of this chapter. (b)(1) When registering...Billing and Collection Agent for North American Numbering Plan Administration...Billing and Collection Agent for North American Numbering Plan...

range of air conductivity. This affordeil first, data concerning suitable openinq ra- tios with their entailed draq and coolin% performances; second, ...

This report investigates the potential for reduced-enrichment, un-moderated surface reactors. The potential programmatic advantages of a reduced safeguards classification are discussed, along with design options that could allow a Cat III inventory surface reactor. Two potential reactor Cat III ...

This report discusses the finite element method analysis which was used to refine the SPR III-M reactor fuel assembly mechanical design to withstand the stresses and strains of pulse-mode operation, which induces thermal shock loading in the fuel assembly components. The original reactor design was analyzed for its structural response ...

This work reports the different steps allowing a better comprehension of the background components of the Bugey III experiment searching for neutrino oscillations at the reactor 5 of the Bugey nuclear plant. Several means have been used in order to suppre...

Argonne's critical facility, ZPR-III, is briefly described. More than 30 different assemblies of widely varying geometries and compositions were studied in this facility, most of which were to aid in tae development of fast power breeder reactors. A description of the ZPR-III assemblies, tables of central reactivity ...

The purpose of this review is to report the operability status of the reactor control instrumentation. The status of the instruments was determined twice during the first six months of this year, April 1 and June 1. The information contained in this report is not intended to be a complete description of the control instruments, but only as they apply to ...

Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III No. 22 and 44, Z PR-VI No. 1, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Advanced Research Reactor, EBWR, magnetohydrodynamic cells, ...

This study group covered the following: delineation of the specific objectives of the overall US AEC civilian power reactor program, technical objectives of each reactor concept, preparation of a chronological development program for each reactor concept, evaluation of the economic potential of each reactor type, a ...

In Task I of this project, the current Nuclear Regulatory Commission (NRC) position-on physical security practices and procedures at research reactors were reviewed. In the second task, a sampling of the physical security plans was presented and the three actual reactor sites described in the security plans were visited. The purpose of Task ...

High-efficiency energy conversion schemes for a D-3He tokamak reactor are investigated. The loss channels for a D-3He plasma are through charged particles, neutrons, and radiation (synchrotron and bremsstrahlung), with only a few percent of the energy loss in neutrons. In contrast to D-T fusion reactors, this gives high leverage to energy-conversion ...

In order to revise safety analysis report of old TRIGA reactors, safety re-evaluation of these reactor was started for necessary parts. This report contains the first year results of the project scheduled for two years. The guide lines of safety re-evalua...

TRIGA Mark-II reactor has been primarily utilized as usual for the fundamental reactor experiments for university students. The annual operating time is 1,100 hours and the gross thermal output is 17,159 KWH, having consumed 0.88g of U-235. The reconstuct...

The reactivity control system is one of the important items in reactor design, but it is much restricted by structural design of fuel element and pressure vessel in the experimental multi-purpose, high-temperature reactor. Preceding the first conceptual d...

Progress made in the reactor development program at Argonne National Laboratory is reported. Information and data are presented on Borax-V, SL-1, ZPR- III, ZPR-VI, ZPR-VII, ZPR-IX, EBR-I, EBR-II, FARET, EBWR, Treat, nology is presented along with nuclear safety. Reactor fuel element and material development is emphasized. ...

Progress in the investigation of the release and behavior of fuel, fission products, and transuranic elements in aerosols resulting from an LMFBR hypothetical core disruptive accident (HCDA) is reported. The development and test results of a capacitor dis...

The determination of the changes in radiation level in the hairpin loops resulting from continued operation of the reactor at power were studied. The results indicate that the radiation level in the hairpin loop resulting from continued operation of the reactor at power decays to a relatively low level approximately 20 minutes after isolation of ...

-III - A Conceptual D-3He Tokamak Reactor,"in Fusion Engineering (Proc. 13th Symp., Knoxville, TN, 1989) IEEE No. 89CH,"The Effect of Pulsed Irradiation on the Swelling of 316 Stainless Steel in Fusion Reactors,"Nucl. Eng. Des. Ghoniem,"The Early Stages of Void and Interstitial Loop Evolution in Pulsed Fusion ...

Sodium stand S III was reconstructed at UJV Rez for the research of the effect of radial displacement of a side rod on the temperature field in a BN-600 fast reactor fuel assembly. A model was built of the BN-600 type fast reactor fuel assembly designated...

The types of tests performed in SPERT-I, and the tests proposed for SPERT-II and -III, are described. These reactors are described, and factors influencing their dynamic behavior are discussed. The tests are classed as static, step, ramp, and oscillatory. The correlation between the test results and the reactor dynamic ...

An engineering and economic evaluation is made of coal conversion processes that can be coupled to a very high-temperature nuclear reactor heat source. The basic system developed by General Atomic/Stone and Webster (GA/S and W) is similar to the H-coal pr...

A series of lectures on fuel elements for water-cooled power reactors are presented. Topics covered include fabrication, properties, cladding, radiation damage, design, cycling, storage and transpont, and reprocessing. Separate records have been prepared for each section.

...radioactive waste, and/or reactor-related GTCC waste for storage...high-level radioactive waste, or reactor-related GTCC waste in storage...integrity of required systems and components is maintained; (iii...the storage of spent fuel and reactor-related GTCC waste in...

Plant features and operator actions, which have been found to be important in either preventing or mitigating severe accidents in BWRs with Mark III containments (BWR Mark III's), have been identified. These features and actions were developed from insigh...

Reactions of e-aq, H-atoms, OH, (CH3)2COH, and CO-?2 radicals with V(III)picolinate and Cr(III)picolinate have been studied by the pulse radiolysis technique. The spectra of V(II)picolinate, V(IV)picolinate, Cr(II)picolinate, OH adduct of Cr(III)picolinate and Cr(IV)picolinate have been obtained and the rate constants of the reactions ...

A very brief review of radiation effects in graphite is given followed by projections of graphite behavior in four fusion reactor design concepts: the ORNL Conceptual Fusion Reactor (Version III), the University of Wisconsin Tokamak (Austin Design), the LASL Reference Theta Pinch Reactor, and the PNL Fusion-- ...

Gulf General Atomic has extensive experience in operating on a continuing basis several models of the family of TRIGA reactors; namely, a Mark I (12 years), a Mark F (10 years), a below ground Mark III (4 years), and an annular core critical facility (6 months). These reactors have been used for a variety of purposes including (a) the ...

Progress is reported on preparation of EBWR for highpower operation, development and operation of Borax-V, research and development on liquid metal reactors including ZPR-III, ZPR-VI, ZPR-DS, EBR-I, EBR-II, and FARET. Developments in general reactor technology are reported in physics, fuels, heat transfer, and chemical ...

The experimental fast reactor Joyo is the first sodium-cooled fast reactor in Japan. One of its primary missions is to perform irradiation tests of fuel and structural materials to support the development of fast reactors. The MK-III high performance core upgrade to enhance the irradiation testing capabilities was ...

BS>The observed oscillatory behavior of five ANL boiling reactors---the Borax I, II, III, IV, and the Experimental Boiling Water Reactor---are described. The amplitude, frequency, temperature, and threshold of the oscillation are recorded. The kinetic theory of oscillations is illustrated by a simplified model using a ...

The Advanced CANDU Reactor{sup TM} (ACR{sup TM}) is a Generation III+ pressure tube type reactor using light water coolant and heavy water moderator. The ACR-1000 reactor design is an evolutionary extension of the proven CANDU reactor design. The ACR-1000 incorporates multiple and diverse ...

BS>Data from examination of blade-type control rods which were used in BORAX are discussed. Operation and maintenance of EBWR is outlined. In work on Borax V, modifications for easier installation of reactor and components is outlined followed by discussion of superheat fuel element development, and fabrication of various reactor ...

The principal effluent from the operating TRIGA reactors in our facility is argon-41. As monitored by a recording gas and particulate stack monitor, the values shown in the table, the Mark III operating 24 hours per day for very long periods produced the largest amount of radioactive argon. The quantity of 23.7 Ci A-41 when diluted by the normal ...

The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel ...

The status of a program to develop a thermal breeder power reactor which is based on the Th-U/sup 233/ cycle is discussed. The general characteristics of two-region power breeder reactors which are either solution-core slurryblanket or slurry-core slurry-blanket are described. A review of studies on corrosion, physical properties, and ...

Nuclear energy's public acceptance, and hence its development, depends on its safety. As a reactor designer, we will first briefly remind the basic safety principles of nuclear reactors' design. We will then show how the industry, and in particular Areva with its EPR, made design evolution in the wake of the Three Miles Island accident in ...

Nuclear energy's public acceptance, and hence its development, depends on its safety. As a reactor designer, we will first briefly remind the basic safety principles of nuclear reactors' design. We will then show how the industry, and in particular Areva with its EPR, made design evolution in the wake of the Three Miles Island accident in 1979. In ...

In the future, Mediated Electrochemical Oxidation (MEO) may be used for the ambient temperature destruction of hazardous waste and for the conversion of mixed waste to low-level radioactive waste. We have studies the complete MEO of ethylene glycol, a surrogate waste, by Co(III) and Fe(III). The reactor had a rotating-cylinder anode ...

The positive temperature coefficient of reactivity which a British type reactor obtains over a certain irradiation level of its natural uranium fuel, has presented a new problem to the inherent safety of this type of reactors. An analysis is described of the dynamic characteristics of three British type reactors with positive ...

Bacterial reductive dissolution of synthetic crystalline Fe(III) oxide-coated sand was studied in continuous-flow column reactors in comparison with parallel batch cultures. The cumulative amount of aqueous Fe(II) exported from the columns over a 6-month incubation period corresponded to (95.0 {+-} 3.7)% (n = 3) of their original ...

Bacterial reductive dissolution of synthetic crystalline Fe(III) oxide-coated sand was studied in continuous-flow column reactors in comparison with parallel batch cultures. The cumulative amount of aqueous Fe(II) exported from the columns over a 6-month incubation period corresponded to (95.0 � 3.7)% (n = 3) of their original ...