Relevant bibliographies by topics / Advanced Reactors

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Advanced Reactors'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Advanced Reactors.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Advanced Reactors"

1

Cabet, C., J. Jang, J. Konys, and P. F. Tortorelli. "Environmental Degradation of Materials in Advanced Reactors." MRS Bulletin 34, no. 1 (January 2009): 35–39. http://dx.doi.org/10.1557/mrs2009.10.

Full text
Abstract:
AbstractAdvanced fission-based reactors challenge our ability to fully understand environment–materials reactions in terms of fundamental stability and kinetics, including the influences of composition, microstructure, and system design, and to predict associated long-term performance. This article briefly describes corrosion reactions and the processes by which such are managed for several elevated-temperature environments associated with advanced reactor concepts: helium, molten Pb–Bi, fluorides, and supercritical water. For most of the subject environments, corrosion resistance critically depends on the ability to form and maintain protective surface layers. Effects of corrosion on mechanical behavior can be from thermally and chemically induced changes in microstructures or from environmental effects on cracking susceptibility. In most cases, the simultaneous effects of chemical reactivity and radiation have not been fully addressed, nor has much attention been paid to newly emerging alloy compositions or the effects of substantially increased operating temperatures.
APA, Harvard, Vancouver, ISO, and other styles
2

Allen, T., H. Burlet, R. K. Nanstad, M. Samaras, and S. Ukai. "Advanced Structural Materials and Cladding." MRS Bulletin 34, no. 1 (January 2009): 20–27. http://dx.doi.org/10.1557/mrs2009.8.

Full text
Abstract:
AbstractAdvanced nuclear energy systems, both fission- and fusion-based, aim to operate at higher temperatures and greater radiation exposure levels than experienced in current light water reactors. Additionally, they are envisioned to operate in coolants such as helium and sodium that allow for higher operating temperatures. Because of these unique environments, different requirements and challenges are presented for both structural materials and fuel cladding. For core and cladding applications in intermediate-temperature reactors (400–650°C), the primary candidates are 9–12Cr ferritic–martensitic steels (where the numbers represent the weight percentage of Cr in the material, i.e., 9–12 wt%) and advanced austenitic steels, adapted to maximize high-temperature strength without compromising lower temperature toughness. For very high temperature reactors (>650°C), strength and oxidation resistance are more critical. In such conditions, high-temperature metals as well as ceramics and ceramic composites are candidates. For all advanced systems operating at high pressures, performance of the pressure boundary materials (i.e., those components responsible for containing the high-pressure liquids or gases that cool the reactor) is critical to reactor safety. For some reactors, pressure vessels are anticipated to be significantly larger and thicker than those used in light water reactors. The properties through the entire thickness of these components, including the effects of radiation damage as a function of damage rate, are important. For all of these advanced systems, optimizing the microstructures of candidate materials will allow for improved radiation and high-temperature performance in nuclear applications, and advanced modeling tools provide a basis for developing optimized microstructures.
APA, Harvard, Vancouver, ISO, and other styles
3

Albagnac, G. "Biomass Retention in Advanced Anaerobic Reactors." Water Science and Technology 22, no. 1-2 (January 1, 1990): 17–24. http://dx.doi.org/10.2166/wst.1990.0132.

Full text
Abstract:
Recognition of the advantages of anaerobic wastewater treatment induced the development of high rate processes, i.e. reactors designed to allow an efficient treatment of even diluted streams. The performance of these advanced reactors is mainly dependent on the retention within the reactor of high bacterial concentrations. The prevailing mechanism is either the formation of bacterial aggregates with good settling characteristics, the development of methanogenic biolayers at the surface of inert carriers or both. During the past decade information on the biology of methanogenic ecosystems became available at an increasing rate. From a practical point of view it can be stated that the biological conversion of organic compounds to methane is reasonably well understood. However the current knowledge on the aggregation and adhesion of methanogenic consortia remains very limited. In most cases reactor start-up procedures are rather long and appear to be more empirical than rational. This paper is a brief presentation on the current knowledge of methanogenic aggregates and biofilms. The fundamental aspects of bacterial adhesion and the modelling of anaerobic biofilms growth are presented elsewhere.
APA, Harvard, Vancouver, ISO, and other styles
4

Sozzi, A., and F. Taghipour. "The importance of hydrodynamics in UV advanced oxidation reactors." Water Science and Technology 55, no. 12 (June 1, 2007): 53–58. http://dx.doi.org/10.2166/wst.2007.378.

Full text
Abstract:
The flow field of UV reactors was characterised experimentally using particle image velocimetry (PIV) and modelled with computational fluid dynamics (CFD). The reactor flow was integrated with the radiation fluence rate and photolysis kinetics to calculate the overall conversion of photo-reactant components in annular UV reactors with an inlet parallel and perpendicular to the reactor axis. The results indicated that the fluid flow distribution within the reactor volume affects photo-reactor performance.
APA, Harvard, Vancouver, ISO, and other styles
5

Golay, Michael W., and Neil E. Todreas. "Advanced Light-Water Reactors." Scientific American 262, no. 4 (April 1990): 82–89. http://dx.doi.org/10.1038/scientificamerican0490-82.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Golay, M. W. "Advanced Fission Power Reactors." Annual Review of Nuclear and Particle Science 43, no. 1 (December 1993): 297–332. http://dx.doi.org/10.1146/annurev.ns.43.120193.001501.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

KATO, Yasuyoshi, Masaya OHTSUKA, Koji FUJIMURA, Hideaki HEKI, Kouji HIRAIWA, Masanori ARITOMI, Yoshiaki MAKIHARA, et al. "Development of Advanced Small Reactors." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 43, no. 11 (2001): 1054–99. http://dx.doi.org/10.3327/jaesj.43.1054.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Riznic, Jovica, Carsten Schroer, and Yassin Hassan. "Material challenges for advanced reactors." Nuclear Engineering and Design 280 (December 2014): 651. http://dx.doi.org/10.1016/j.nucengdes.2014.06.002.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Carmack, W. J., D. L. Porter, Y. I. Chang, S. L. Hayes, M. K. Meyer, D. E. Burkes, C. B. Lee, T. Mizuno, F. Delage, and J. Somers. "Metallic fuels for advanced reactors." Journal of Nuclear Materials 392, no. 2 (July 2009): 139–50. http://dx.doi.org/10.1016/j.jnucmat.2009.03.007.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Dutton, R., E. O. Moeck, N. J. Spinks, C. E. Coleman, B. A. Cheadle, A. D. Lane, A. I. Miller, R. A. Judd, and L. R. Lupton. "Advanced technologies for CANDU reactors." Nuclear Engineering and Design 144, no. 2 (October 1993): 269–81. http://dx.doi.org/10.1016/0029-5493(93)90143-w.

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Advanced Reactors"

1

Sommer, Christopher. "Fuel cycle design and analysis of SABR subrcritical advanced burner reactor /." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24720.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Bopp, Andrew T. "The calculation of fuel bowing reactivity coefficients in a subcritical advanced burner reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50295.

Full text
Abstract:
The United States' fleet of Light Water Reactors (LWRs) produces a large amount of spent fuel each year; all of which is presently intended to be stored in a fuel repository for disposal. As these LWRs continue to operate and more are built to match the increasing demand for electricity, the required capacity for these repositories grows. Georgia Tech's Subcritical Advanced Burner Reactor (SABR) has been designed to reduce the capacity requirements for these repositories and thereby help close the back end of the nuclear fuel cycle by burning the long-lived transuranics in spent nuclear fuel. SABR's design is based heavily off of the Integral Fast Reactor (IFR). It is important to understand whether the SABR design retains the passive safety characteristics of the IFR. A full safety analysis of SABR's transient response to various possible accident scenarios needs to be performed to determine this. However, before this safety analysis can be performed, it is imperative to model all components of the reactivity feedback mechanism in SABR. The purpose of this work is to develop a calculational model for the fuel bowing reactivity coefficients that can be used in SABR's future safety analysis. This thesis discusses background on fuel bowing and other reactivity coefficients, the history of the IFR, the design of SABR, describes the method that was developed for calculating fuel bowing reactivity coefficients and its validation, and presents an example of a fuel bowing reactivity calculation for SABR.
APA, Harvard, Vancouver, ISO, and other styles
3

Zakova, Jitka. "Advanced fuels for thermal spectrum reactors." Doctoral thesis, KTH, Reaktorfysik, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-103085.

Full text
Abstract:
The advanced fuels investigated in this thesis comprise fuels non− conventional in their design/form (TRISO), their composition (high content of plutonium and minor actinides) or their use in a reactor type, in which they have not been used before (e.g. nitride fuel in BWR). These fuels come with a promise of improved characteristics such as safe, high temperature operation, spent fuel transmutation or fuel cycle extension, for which reasons their potentialis worth assessment and investigation. Their possible use also brings about various challenges, out of which some were addressed in this thesis. TRISO particle fuels with their superior retention abilities enable safe, high−temperature operation. Their combination with molten salt in the Advanced High Temperature Reactor (AHTR) concept moreover promises high operating temperature at low pressure, but it requires a careful selection of the cooling salt and the TRISO dimensions to achieve adequate safety characteristic, incl. a negative feedback to voiding. We show that an AHTR cooled with FLiBe may safely operate with both Pu oxide and enriched U oxide fuels. Pu and Minor Actinides (MA) bearing fuels may be used in BWR for transmutation through multirecycling; however, the allowable amounts of Pu and MA are limited due to the degraded feedback to voiding or low reactivity.We showed that the main positive contribution to the void effect in the fuelswith Pu and MA content of around 11 to 15% consist of the decreased thermalcapture probability in Pu-240, Pu-239 and Am-241 and increased fast and resonance fission probability of U-238, Pu239 and Pu-240. The total void worthmoreover increases during multirecycling, limiting the allowable amount ofMA to 2.45% in uranium−based fuels. An alternative, thorium−based fuel allows for 3.45% MA without entering the positive voiding regime at any point of the multirecycling. The increased alpha−heating associated with the use of transmutation fuels, is at level 24−31 W/kgFUEL in the uranium based fuels and 32−37 W/kgFUEL in the thorium−based configurations. The maximum value of the neutron emission, reached in the last cycle, is 1.7·106 n/s/g and 2·106 n/s/g for uranium and for thorium−based fuels, respectively. Replacing the standard UO2 fuel with higher−uranium density UN orUNZrO2 fuels in BWR shows potential for an increase of the in-core fuelresidence time by about 1.4 year. This implies 1.4% higher availability of the plant. With the nitride fuels, the total void worth increases and the efficiency of the control rods and burnable poison deteriorates, but no major neutronics issue has been identified. The use of nitride fuels in the BWR environment is conditioned by their stability in hot steam. Possible methods for stabilizing nitride fuels in water and steam at 300◦ C were suggested in a recent patentapplication.

QC 20121004

APA, Harvard, Vancouver, ISO, and other styles
4

Chand, Rashmi. "Advanced oxidative wastewater treatment using cavitational reactors." Thesis, Abertay University, 2008. https://rke.abertay.ac.uk/en/studentTheses/fdce9629-7b22-43c6-9162-d03848e5df3b.

Full text
Abstract:
This thesis explores various novel ways of treatment of wastewater contaminated by toxic organic pollutants using single and combined advanced oxidative wastewater treatment technologies in conjunction with a variety of acoustic and hydrodynamic cavitational reactors. There have been many reports in the literature on the use of hydroxyl radicals as the core part of AOPs and hence, as the first objective, the amount of hydroxyl radical generation from different acoustic and hydrodynamic cavitational reactors was studied using the potassium iodide dosimeter. The results reveal that optimum concentrations of less toxic chloroalkanes (chloroform and dichloromethane) could be efficient alternatives to carbon tetrachloride for enhancement of hydroxyl radical generation in cavitational reactors. Increasing ultrasonic amplitudes and operating hydrodynamic cavitational pressures lead to higher rates of hydroxyl radical production. Having explored the efficiency of generation of hydroxyl radicals the capacity of the reactors to degrade the model pollutant phenol, via a modified classic Fenton reaction which uses zero valent iron catalysts (instead of iron salts) and hydrogen peroxide under acidic conditions was studied. This process, named the advanced Fenton process (AFP), is the main foundation of the phenolic wastewater treatment reported in this thesis. Phenol degradation was assessed using different frequencies of ultrasound where a comparison between 20, 300 and 520 kHz ultrasonic reactors showed that 300 kHz was by far the most efficient US reactor resulting in 100% phenol removal and 37% total organic carbon (TOC) mineralization in 25 min. The concept of Latent Remediation (LR) was discovered during investigations into innovative approaches towards development of cost/energy-effective methods to treat phenolic wastewater. LR consists of inputting only 15 min of either ultrasound or stirring to the reaction medium, which contains optimised amounts of hydrogen peroxide and iron catalyst, and then the silent-dark AFP phenol degradation was studied over 24 h. The excellent results revealed that >80% TOC mineralization was achieved after this time. It was also found that zero valent copper catalysts were effective for phenol degradation and offered an excellent alternative to iron in the AFP, however toxicity analysis on the 24, 48 and 72 h samples showed that zero valent iron exhibited decreased toxicity when compared to zero valent copper. Conventional granular/powdered activated carbons were replaced with activated carbon cloth and investigations on the potential use of this material for phenol removal/decomposition was studied in detail at different operating pHs (3, 5.5 and 9), temperatures (20, 40 and 80 °C), oxidants (H2O2/O3) in various reactors (pump, shaker and US bath). Another aspect of the AOP application, disinfection of natural waters, was studied employing hydrodynamic cavitation and ozonation in a novel Liquid Whistle Reactor system. Model markers of faecal coliforms, Escherichia coli, were chosen for the study and the combined technologies of hydrodynamic cavitation and stepwise ozonation proved be highly beneficial, resulting in ~ 6 log bacterial reduction revealing 99.9999% disinfection efficiency of the process.
APA, Harvard, Vancouver, ISO, and other styles
5

Elshahat, Ayah Elsayed. "Enhancing nuclear energy sustainability using advanced nuclear reactors." Thesis, University of Manchester, 2015. https://www.research.manchester.ac.uk/portal/en/theses/enhancing-nuclear-energy-sustainability-using-advanced-nuclear-reactors(2c39b9ca-86a9-446f-8832-ae9469485a2d).html.

Full text
Abstract:
The safety performance of nuclear power reactors is a very important factor in evaluating nuclear energy sustainability. Improving the safety performance of nuclear reactors can enhance nuclear energy sustainability as it will improve the environmental indicator used to evaluate the overall sustainability of nuclear energy. Great interest is given now to advanced nuclear reactors especially those using passive safety components. Investigation of the improvement in nuclear safety using advanced reactors was done by comparing the safety performance of a conventional reactor which uses active safety systems, such as Pressurized Water Reactor (PWR), with an advanced reactor which uses passive safety systems, such as AP1000, during a design basis accident, such as Loss of Coolant Accident (LOCA), using the PCTran as a simulation code. To assess the safety performance of PWR and AP1000, the “Global Safety Index” GSI model was developed by introducing three indicators: probability of accident occurrence, performance of safety system in case of an accident occurrence, and the consequences of the accident. Only the second indicator was considered in this work. A more detailed model for studying the performance of passive safety systems in AP1000 was developed. That was done using SCDAPSIM/RELAP5 code as it is capable of modelling design basis accidents (DBAs) in advanced nuclear reactors.
APA, Harvard, Vancouver, ISO, and other styles
6

Lange, Carsten. "Advanced nonlinear stability analysis of boiling water nuclear reactors." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2009. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-24954.

Full text
Abstract:
This thesis is concerned with nonlinear analyses of BWR stability behaviour, contributing to a deeper understanding in this field. Despite negative feedback-coefficients of a BWR, there are operational points (OP) at which oscillatory instabilities occur. So far, a comprehensive and an in-depth understanding of the nonlinear BWR stability behaviour are missing, even though the impact of the significant physical parameters is well known. In particular, this concerns parameter regions in which linear stability indicators, like the asymptotic decay ratio, lose their meaning. Nonlinear stability analyses are usually carried out using integral (system) codes, describing the dynamical system by a system of nonlinear partial differential equations (PDE). One aspect of nonlinear BWR stability analyses is to get an overview about different types of nonlinear stability behaviour and to examine the conditions of their occurrence. For these studies the application of system codes alone is inappropriate. Hence, in the context of this thesis, a novel approach to nonlinear BWR stability analyses, called RAM-ROM method, is developed. In the framework of this approach, system codes and reduced order models (ROM) are used as complementary tools to examine the stability characteristics of fixed points and periodic solutions of the system of nonlinear differential equations, describing the stability behaviour of a BWR loop. The main advantage of a ROM, which is a system of ordinary differential equations (ODE), is the possible coupling with specific methods of the nonlinear dynamics. This method reveals nonlinear phenomena in certain regions of system parameters without the need for solving the system of ROM equations. The stability properties of limit cycles generated in Hopf bifurcation points and the conditions of their occurrence are of particular interest. Finally, the nonlinear phenomena predicted by the ROM will be analysed in more details by the system code. Hence, the thesis is not focused on rendering more precisely linear stability indicators like DR. The objective of the ROM development is to develop a model as simple as possible from the mathematical and numerical point of view, while preserving the physics of the BWR stability behaviour. The ODEs of the ROM are deduced from the PDEs describing the dynamics of a BWR. The system of ODEs includes all spatial effects in an approximated (spatial averaged) manner, e.g. the space-time dependent neutron flux is expanded in terms of a complete set of orthogonal spatial neutron flux modes. In order to simulate the stability characteristics of the in-phase and out-of-phase oscillation mode, it is only necessary to take into account the fundamental mode and the first azimuthal mode. The ROM, originally developed at PSI in collaboration with the University of Illinois (PSI-Illinois-ROM), was upgraded in significant points: • Development and implementation of a new calculation methodology for the mode feedback reactivity coefficients (void and fuel temperature reactivity) • Development and implementation of a recirculation loop model; analysis and discussion of its impact on the in-phase and out-of-phase oscillation mode • Development of a novel physically justified approach for the calculation of the ROM input data • Discussion of the necessity of consideration of the effect of subcooled boiling in an approximate manner With the upgraded ROM, nonlinear BWR stability analyses are performed for three OPs (one for NPP Leibstadt (cycle7), one for NPP Ringhals (cycle14) and one for NPP Brunsbüttel (cycle16) for which measuring data of stability tests are available. In this thesis, the novel approach to nonlinear BWR stability analyses is extensively presented for NPP Leibstadt. In particular, the nonlinear analysis is carried out for an operational point (OP), in which an out-of-phase power oscillation has been observed in the scope of a stability test at the beginning of cycle 7 (KKLc7_rec4). The ROM predicts a saddle-node bifurcation of cycles, occurring in the linear stable region, close to the KKLc7_rec4-OP. This result allows a new interpretation of the stability behaviour around the KKLc7_rec4-OP. The results of this thesis confirm that the RAM-ROM methodology is qualified for nonlinear BWR stability analyses
Die vorliegende Dissertation leistet einen Beitrag zum tieferen Verständnis des nichtlinearen Stabilitätsverhaltens von Siedewasserreaktoren (SWR). Trotz der Tatsache, dass in diesem technischen System nur negative innere Rückkopplungskoeffizienten auftreten, können in bestimmten Arbeitspunkten oszillatorische Instabilitäten auftreten. Obwohl relativ gute Kenntnisse über die signifikanten physikalischen Einflussgrößen vorliegen, fehlt bisher ein umfassendes Verständnis des SWR-Stabilitätsverhaltens. Das betrifft insbesondere die Bereiche der Systemparameter, in denen lineare Stabilitätsindikatoren, wie zum Beispiel das asymptotische Decay Ratio (DR), ihren Sinn verlieren. Die nichtlineare Stabilitätsanalyse wird im Allgemeinen mit Systemcodes (nichtlineare partielle Differentialgleichungen, PDG) durchgeführt. Jedoch kann mit Systemcodes kein oder nur ein sehr lückenhafter Überblick über die Typen von nichtlinearen Phänomenen, die in bestimmten System-Parameterbereichen auftreten, erhalten werden. Deshalb wurde im Rahmen der vorliegenden Arbeit eine neuartige Methode (RAM-ROM Methode) zur nichtlinearen SWR-Stabilitätsanalyse erprobt, bei der integrale Systemcodes und sog. vereinfachte SWR-Modelle (ROM) als sich gegenseitig ergänzende Methoden eingesetzt werden, um die Stabilitätseigenschaften von Fixpunkten und periodischen Lösungen (Grenzzyklen) des nichtlinearen Differentialgleichungssystems, welches das Stabilitätsverhalten des SWR beschreibt, zu bestimmen. Das ROM, in denen das dynamische System durch gewöhnliche Differentialgleichungen (GDG) beschrieben wird, kann relativ einfach mit leistungsfähigen Methoden aus der nichtlinearen Dynamik, wie zum Beispiel die semianalytische Bifurkationsanalyse, gekoppelt werden. Mit solchen Verfahren kann, ohne das DG-System explizit lösen zu müssen, ein Überblick über mögliche Typen von stabilen und instabilen oszillatorischen Verhalten des SWR erhalten werden. Insbesondere sind die Stabilitätseigenschaften von Grenzzyklen, die in Hopf-Bifurkationspunkten entstehen, und die Bedingungen, unter denen sie auftreten, von Interesse. Mit dem Systemcode (RAMONA5) werden dann die mit dem ROM vorhergesagten Phänomene in den entsprechenden Parameterbereichen detaillierter untersucht (Validierung des ROM). Die Methodik dient daher nicht der Verfeinerung der Berechnung linearer Stabilitätsindikatoren (wie das DR). Das ROM-Gleichungssystem entsteht aus den PDGs des Systemcodes durch geeignete (nichttriviale) räumliche Mittelung der PDG. Es wird davon ausgegangen, dass die Reduzierung der räumlichen Komplexität die Stabilitätseigenschaften des SWR nicht signifikant verfälschen, da durch geeignete Mittlungsverfahren, räumliche Effekte näherungsweise in den GDGs berücksichtig werden. Beispielsweise wird die raum- und zeitabhängige Neutronenflussdichte nach räumlichen Moden entwickelt, wobei für eine Simulation der Stabilitätseigenschaften der In-phase- und Out-of-Phase-Leistungsoszillationen nur der Fundamentalmode und der erste azimuthale Mode berücksichtigt werden muss. Das ROM, welches ursprünglich am Paul Scherrer Institut (PSI, Schweiz) in Zusammenarbeit mit der Universität Illinois (USA) entwickelt wurde, ist in zwei wesentlichen Punkten erweitert und verbessert worden: • Entwicklung und Implementierung einer neuen Methode zur Berechnung der Rückkopplungsreaktivitäten • Entwicklung und Implementierung eines Modells zur Beschreibung der Rezirkulationsschleife (insbesondere wurde der Einfluss der Rezirkulationsschleife auf den In-Phase-Oszillationszustand und auf den Out-of-Phase-Oszillationszustand untersucht) • Entwicklung einer physikalisch begründeten Methode zur Berechnung der ROM-Inputdaten • Abschätzung des Einflusses des unterkühlten Siedens im Rahmen der ROM-Näherungen Mit dem erweiterten ROM wurden nichtlineare Stabilitätsanalysen für drei Arbeitspunkte (KKW Leibstadt (Zyklus 7) KKW Ringhals (Zyklus 14) und KKW Brunsbüttel (Zyklus 16)), für die Messdaten vorliegen, durchgeführt. In der Dissertationsschrift wird die RAM-ROM Methode ausführlich am Beispiel eines Arbeitspunktes (OP) des KKW Leibstadt (KKLc7_rec4-OP), in dem eine aufklingende regionale Leistungsoszillation bei einem Stabilitätstest gemessen worden ist, demonstriert. Das ROM sagt die Existenz eines Umkehrpunktes (saddle-node bifurcation of cycles, fold-bifurcation) voraus, der sich im linear stabilen Gebiet nahe der Stabilitätsgrenze befindet. Mit diesem ROM-Ergebnis ist eine neue Interpretation der Stabilitätseigenschaften des KKLc7_rec4-OP möglich. Die Resultate der in der Dissertation durchgeführten RAM-ROM Analyse bestätigen, dass das weiterentwickelte ROM für die Analyse des Stabilitätsverhaltens realer Leistungsreaktoren qualifiziert wurde
APA, Harvard, Vancouver, ISO, and other styles
7

Can, Levent. "Analysis of coolant options for advanced metal cooled nuclear reactors." Thesis, Monterey, Calif. : Naval Postgraduate School, 2006. http://bosun.nps.edu/uhtbin/hyperion.exe/06Dec%5FCan%5FAP.pdf.

Full text
Abstract:
Thesis (M.S. in Applied Physics)--Naval Postgraduate School, December 2006.
Thesis Advisor(s): Craig F. Smith "December 2006." Includes bibliographical references (p. 69-70). Also available in print.
APA, Harvard, Vancouver, ISO, and other styles
8

Allen, Kenneth S. "Advanced polymeric burnable poison rod assemblies for pressurized water reactors." [Gainesville, Fla.] : University of Florida, 2003. http://purl.fcla.edu/fcla/etd/UFE0000628.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Pauli, Lisa M. "Containment building : architecture between the city and advanced nuclear reactors." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/62885.

Full text
Abstract:
Thesis (M. Arch.)--Massachusetts Institute of Technology, Dept. of Architecture, 2011.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Page 127 blank Cataloged from student submitted PDF version of thesis.
Includes bibliographical references (p. 124-126).
Since the inception of nuclear energy research, the element thorium (Th) has been considered the superior fuel for nuclear reactions because of its potency, safety, abundance and reduced waste. Cold War agendas broke from the logic of efficient energy production to establish a nationwide network of reactors designed to enrich uranium fuel for a nuclear arsenal. Contemporary dilemmas of global warming, increasing fuel prices, carbon emissions, and anti-proliferation movements have brought the discussion of clean, safe nuclear power to the forefront of American energy policy; it is no longer tolerable or sustainable to rely on a uranium (U) nuclear network. The architectural typology of nuclear energy has not been addressed in America for 35 years and is one that belies the promise of clean energy's progress through technology and public intervention. Containment Building is an architectural response to nuclear technological advancement that challenges historical separation between nuclear power and the public. It is a self-sustained, thorium-powered nuclear plant sited in and powering New York City. It is a nuclear campus that programatically and urbanistically engages the public and contains radio isotope labs, a nuclear medicine and imaging facility, a food irradiation center, a wellness hotel and spa, an electric taxi charging station, and a plug-in park along the Hudson River waterfront.
by Lisa M. Pauli.
M.Arch.
APA, Harvard, Vancouver, ISO, and other styles
10

Chaleff, Ethan S. "The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors." The Ohio State University, 2016. http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113.

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Books on the topic "Advanced Reactors"

1

Zohuri, Bahman, and Patrick McDaniel. Advanced Smaller Modular Reactors. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

United States. Congress. House. Committee on Science and Technology. Subcommittee on Energy Research and Production. Regulatory policy for advanced nuclear reactors: Report. Washington: U.S. G.P.O., 1986.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
3

Agency, OECD Nuclear Energy, and British Nuclear Fuels Limited, eds. Advanced reactors with innovative fuels: Second workshop proceedings, Chester, United Kingdom, 22-24 October 2001. Paris: Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2002.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
4

International Symposium on Advanced Nuclear Power Systems: Design, Technology, Safety and Strategies for Their Deployment (1993 Seoul, Korea). Advanced nuclear power systems: Design, technology, safety and strategies for their deployment : proceedings of an International Symposium on Advanced Nuclear Power Systems: Design, Technology, Safety and Strategies for their Deployment. Vienna: International Atomic Energy Agency, 1994.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
5

Hallbert, B. P. A study of control room staffing levels for advanced reactors. Washington, D.C: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
6

Sapra, M. K. Design, development, and testing of 25 NB size accumulator isolation passive value (AIPV) for advanced heavy water reactor (AHWR). Mumbai: Bhabha Atomic Research Centre, 2010.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
7

US-Japan Fusion Cooperation Program Exchange P148 Workshop on Advanced Current Drive Concepts (1988 Kyoto University). Proceedings of US-Japan Fusion Cooperation Program Exchange P148 Workshop on Advanced Current Drive Concepts, Dec. 6-8, 1988. Nagoya, Japan: Institute of Plasma Physics, Nagoya University, 1989.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
8

International Topical Meeting on Advanced Reactors Safety (1994 Pittsburgh, Pa.). Proceedings of the International Topical Meeting on Advanced Reactors Safety: Pittsburgh, Pennsylvania, April 17-21, 1994. La Grange Park, Ill: American Nuclear Society, 1994.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
9

Lillington, J. N. Light water reactor safety: The development of advanced models and codes for light water reactor safety analysis. Amsterdam: Elsevier, 1995.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
10

Sapra, M. K. Functional and performance evaluation of 28 bar hot shutdown passive valve (HSPV) at integral test loop (ITL) for advanced heavy water reactor (AHWR). Mumbai: Bhabha Atomic Research Centre, 2007.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Book chapters on the topic "Advanced Reactors"

1

Kulsrud, R. M. "Polarized Advanced Fuel Reactors." In Muon-Catalyzed Fusion and Fusion with Polarized Nuclei, 161–68. Boston, MA: Springer US, 1987. http://dx.doi.org/10.1007/978-1-4757-5930-3_13.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Osada, Hiroo, and Kiyonobu Yamashita. "Design of Advanced Reactors." In An Advanced Course in Nuclear Engineering, 231–303. Tokyo: Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-54898-0_4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Zohuri, Bahman, and Patrick McDaniel. "Economics of Advanced Small Modular Reactors." In Advanced Smaller Modular Reactors, 69–102. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_3.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Zohuri, Bahman, and Patrick McDaniel. "Advanced Small Modular Reactor and Environment Consideration." In Advanced Smaller Modular Reactors, 135–41. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_5.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Zohuri, Bahman, and Patrick McDaniel. "Advanced Power Conversion System for Small Modular Reactors." In Advanced Smaller Modular Reactors, 103–34. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Zohuri, Bahman, and Patrick McDaniel. "Integrating Energy Storage with Advanced Small Modular Reactors." In Advanced Smaller Modular Reactors, 177–85. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_8.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Zohuri, Bahman, and Patrick McDaniel. "Safety and Nonproliferation Aspect of Advanced Small Modular Reactor." In Advanced Smaller Modular Reactors, 143–63. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_6.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Zohuri, Bahman, and Patrick McDaniel. "The Electricity: An Essential Necessity in Our Life." In Advanced Smaller Modular Reactors, 1–21. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_1.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Zohuri, Bahman, and Patrick McDaniel. "Energy Resources and the Role of Nuclear Energy." In Advanced Smaller Modular Reactors, 23–67. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_2.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Zohuri, Bahman, and Patrick McDaniel. "Reliable Electricity Grids and Renewable Source of Energy." In Advanced Smaller Modular Reactors, 165–76. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-23682-3_7.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Advanced Reactors"

1

Reyes, Jose´ N., and Eric Young. "The NuScale Advanced Passive Safety Design." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6658.

Full text
Abstract:
NuScale Power is designing an advanced passive nuclear power plant that does not rely on any external sources of power or coolant for safety. Accordingly, the NuScale design inherently prevents the types of issues which led to fuel damage at the Fukushima Daiichi facility. This paper presents an overview of the advanced passive safety systems implemented in the NuScale nuclear power plant. During normal operation, each NuScale containment is fully immersed in a water-filled stainless steel lined concrete pool that resides underground. The pool, housed in a Seismic Category I building, is large enough to provide 30 days of core and containment cooling without adding additional water. After 30 days, the decay heat generation is sufficiently small that natural convection heat transfer to air on the outside surface of the containment coupled with thermal radiation heat transfer is completely adequate to remove core decay heat for an indefinite period of time. These passive safety systems can perform their function without requiring an external supply of water, power, or generators.
APA, Harvard, Vancouver, ISO, and other styles
2

Smith, Curtis. "Advanced Small Modular Reactor Probabilistic Risk Assessment Framework." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3332.

Full text
Abstract:
A key area of the Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) use is in the development of methodologies and tools that will be used to predict the safety, security, safeguards, performance, and deployment viability of SMR systems starting in the design process through the operation phase. Recently, the Idaho National Laboratory (INL) set out to develop quantitative methods and tools and the associated analysis framework for assessing a variety of SMR risks. Development and implementation of SMR-focused safety assessment methods may require new analytic methods or adaptation of traditional methods to the advanced design and operational features of SMRs. The development of SMR-specific safety models for margin determination will provide a safety case that describes potential accidents, design options (including postulated controls), and supports licensing activities by providing a technical basis for the safety envelope. INL has proposed an approach to expand and advance the state-of-the-practice in PRA. Specifically we will develop a framework for applying modern computational tools to create advanced risk-based methods for identifying design vulnerabilities in SMRs. This framework will require the fusion of state-of-the-art PRA methods, advanced 3D visualization methods, and highperformance optimization. The approach has several defining attributes focused within three general areas: 1. Models – A single 3D representation of all key systems, structures, and components (SSCs) will be defined for a particular facility. We will be able to simulate — by understanding how each SSC interacts with other parts of the facility — the hazard-induced susceptibilities of each SSC. 2. Phenomena – An approach to effectively representing hazards and their effect on physical behavior at a facility will need to be determined. In many cases, multiple models of a specific phenomenon may be available, but this ensemble of models will need to be intelligently managed. 3. Integration – Any advanced risk-informed decision support approach will rely on a variety of probabilistic and mechanistic information. The safety, security, and economic drivers will need to be integrated in order to determine the effectiveness of proposed mitigation strategies. We will need to be able to manage all (important) hazards for all (important) scenarios all of the time the facility is in operation. The focus of the paper will be on discussing the features of the proposed advanced SMR PRA Framework and providing an status update of the development activities.
APA, Harvard, Vancouver, ISO, and other styles
3

Hugo, Jacques V., and David I. Gertman. "Development of Operational Concepts for Advanced SMRs: The Role of Cognitive Systems Engineering." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3395.

Full text
Abstract:
Advanced small modular reactors (AdvSMRs) will use advanced digital instrumentation and control systems, and make greater use of automation. These advances not only pose technical and operational challenges, but will inevitably have an effect on the operating and maintenance cost of new plants. However, there is much uncertainty about the impact of AdvSMR designs on operational and human factors considerations, such as workload, situation awareness, human reliability, staffing levels, and the appropriate allocation of functions between the crew and various automated plant systems. Existing human factors and systems engineering design standards and methodologies are not current in terms of human interaction requirements for dynamic automated systems and are no longer suitable for the analysis of evolving operational concepts. New models and guidance for operational concepts for complex socio-technical systems need to adopt a state-of-the-art approach such as Cognitive Systems Engineering (CSE) that gives due consideration to the role of personnel. The approach described here helps to identify and evaluate human challenges related to non-traditional operational concepts. A framework for defining operational strategies was developed based on an analysis of the Experimental Breeder Reactor-II (EBR-II), a small (20MWe) sodium-cooled reactor that was successfully operated for thirty years. Insights from the application of the systematic application of the methodology and its utility are reviewed and arguments for the formal adoption of CSE as a value-added part of the Systems Engineering process are presented.
APA, Harvard, Vancouver, ISO, and other styles
4

Vilim, R. B., S. Passerini, and R. Ponciroli. "Active Control and Inherently Safe Operation in Advanced SMRs." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3410.

Full text
Abstract:
A strategy that ensures active control systems cannot override or compromise passive safety and that power generation goals are still met is described. The approach places an increased reliance on passive feedbacks to regulate plant operation. The tradeoffs this strategy entails are assessed through dynamic simulation studies of a liquid-metal cooled advanced SMR.
APA, Harvard, Vancouver, ISO, and other styles
5

Suzuki, Toshio, Toshiaki Yamaguchi, Yoshinobu Fujishiro, Masanobu Awano, and Yoshihiro Funahashi. "Recent Development of Micro Ceramic Reactors for Advanced Ceramic Reactor System." In ASME 2008 6th International Conference on Fuel Cell Science, Engineering and Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/fuelcell2008-65016.

Full text
Abstract:
Ceramic reactors, which convert materials and energy electrochemically, are expected to solve various environmental problems, and use of micro reactor design was shown to realize high performance reactor with high thermal durability operable at lower temperatures. Our research project “Advanced Ceramic Reactor” supported by NEDO targets to develop new fabrication technology for such micro reactors and modules using conventional, commercially available materials. In this study, fabrication technology of micro tubular ceramic reactors have been investigated for aiming solid oxide fuel cells (SOFCs) application, such as small distributed power generators, APU for vehicles, and portable power sources. So far, micro tubular SOFCs under 1 mm diam. using doped ceria electrolyte and Ni-ceria based cermet for tubular support has been successfully developed and evaluated. The single micro tubular SOFC showed cell performance of 0.46 W/cm2 (@0.7 V) at 550 °C with H2 fuel. Bundle design for such tubular cell was also proposed and fabricated. Discussion will cover fabrication technology of single tubular SOFC and bundle, and optimization of the cell and bundle design by considering gas pressure loss and current collecting loss.
APA, Harvard, Vancouver, ISO, and other styles
6

Jolly, Clifford D., Leonard J. Schussel, and Layne Carter. "Advanced Development of Immobilized Enzyme Reactors." In International Conference On Environmental Systems. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 1991. http://dx.doi.org/10.4271/911505.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Read, J. S. Benftez, M. Jamshidi, and R. Kisner. "Advanced Control Techniques for Nuclear Reactors." In 1991 American Control Conference. IEEE, 1991. http://dx.doi.org/10.23919/acc.1991.4791373.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Kurata, Yuji, Hitoshi Yokota, and Tetsuya Suzuki. "Development of Aluminum Alloy Coating for Advanced Nuclear Systems Using Lead Alloys." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6545.

Full text
Abstract:
Small and medium reactors using lead alloys as coolant are one of the promising reactor concepts with improved safety because of their thermal-physical and chemical properties. This paper focuses on development of Al-alloy coating for nuclear systems using liquid lead-bismuth eutectic (LBE). Since corrosion attack becomes severe against structural steels at high temperatures in liquid LBE, it is necessary to improve corrosion resistance of steels. An Al-alloy coating method using Al, Ti and Fe powders, and laser beam heating has been developed. Main defects formed in an Al-powder-alloy coating process are surface defects and cracks. Conditions required to avoid these defects are employment of the laser beam scanning rate of 20 mm/min and adjustment of the Al concentration in the coating layer. According to results of the corrosion tests at 550°C in liquid LBE, the Al-alloy coating layers on 316SS protect severe corrosion attack such as grain boundary corrosion and LBE penetration observed in 316SS without coating. The good corrosion resistance of the Al-alloy coating is based on the thin Al-oxide film which can be regenerated in liquid LBE. From the viewpoints of the soundness of produced Al-powder-alloy coating layers and preservation of their corrosion resistance, it is estimated that the range of the adequate Al concentration in the coating layer is from 4 to 12 wt%.
APA, Harvard, Vancouver, ISO, and other styles
9

Le Blanc, Katya L., and Johanna H. Oxstrand. "Initiators and Triggering Conditions for Adaptive Automation in Advanced Small Modular Reactors." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3401.

Full text
Abstract:
It is anticipated that Advanced Small Modular Reactors (AdvSMRs) will employ high degrees of automation. High levels of automation can enhance system performance, but often at the cost of reduced human performance. Automation can lead to human out-of the loop issues, unbalanced workload, complacency, and other problems if it is not designed properly. Researchers have proposed adaptive automation (defined as dynamic or flexible allocation of functions) as a way to get the benefits of higher levels of automation without the human performance costs. Adaptive automation has the potential to balance operator workload and enhance operator situation awareness by allocating functions to the operators in a way that is sensitive to overall workload and capabilities at the time of operation. However, there still a number of questions regarding how to effectively design adaptive automation to achieve that potential. One of those questions is related to how to initiate (or trigger) a shift in automation in order to provide maximal sensitivity to operator needs without introducing undesirable consequences (such as unpredictable mode changes). Several triggering mechanisms for shifts in adaptive automation have been proposed including: operator initiated, critical events, performance-based, physiological measurement, model-based, and hybrid methods. As part of a larger project to develop design guidance for human-automation collaboration in AdvSMRs, researchers at Idaho National Laboratory have investigated the effectiveness and applicability of each of these triggering mechanisms in the context of AdvSMR. Researchers reviewed the empirical literature on adaptive automation and assessed each triggering mechanism based on the human-system performance consequences of employing that mechanism. Researchers also assessed the practicality and feasibility of using the mechanism in the context of an AdvSMR control room. Results indicate that there are tradeoffs associated with each mechanism, but that some are more applicable to the AdvSMR domain than others. The two mechanisms that consistently improve performance in laboratory studies are operator initiated adaptive automation based on hierarchical task delegation and the Electroencephalogram (EEG)–based measure of engagement. Current EEG methods are intrusive and require intensive analysis; therefore it is not recommended for an AdvSMR control rooms at this time. Researchers also discuss limitations in the existing empirical literature and make recommendations for further research.
APA, Harvard, Vancouver, ISO, and other styles
10

Cetiner, Sacit M., David L. Fugate, Roger A. Kisner, Michael D. Muhlheim, and Richard T. Wood. "Development of a Supervisory Control System Concept for Advanced Small Modular Reactors." In ASME 2014 Small Modular Reactors Symposium. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/smr2014-3403.

Full text
Abstract:
Small modular reactors (SMRs) can provide the United States with a safe, sustainable, and carbon-neutral energy source. Because of their small size and, in many cases, simplified nuclear island configurations, it is expected that capital costs will be less for SMRs compared to that of large, Generation III+ light-water reactors. Advanced SMRs (AdvSMRs), which use coolants other than water as the primary heat transport medium, introduce several passive safety concepts and controls features that further reduce the complexity of primary system designs by eliminating redundant components and systems. Under U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), the Supervisory Control of Multi-Modular SMR Plants project was established to enable innovative control strategies and methods to supervise multi-unit plants, accommodate shared systems, identify opportunities to increase the level of automation, define economic metrics based on the relationship between control and staffing levels, and permit flexible co-generation operational regimes. This paper documents current findings from the Supervisory Control project. Specifically, it defines and documents strategies, functional elements, and an architectural structure for supervisory control of a representative generic AdvSMR plant. More specifically, this research advances the state-of-the art by incorporating decision making into the supervisory control system architectural layers through the introduction of tiered taxonomy of plant systems and subsystems. The proposed architecture has the features of planning and scheduling, analyzing plant status, diagnosing problems as they develop and predicting potential future problems, making decisions based on these features, and generating validated commands to lower control layers in the architecture.
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Advanced Reactors"

1

Kulsrud, R. M. Polarized advanced fuel reactors. Office of Scientific and Technical Information (OSTI), July 1987. http://dx.doi.org/10.2172/6169161.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Forsberg, C. (Advanced technologies for water-cooled reactors). Office of Scientific and Technical Information (OSTI), July 1988. http://dx.doi.org/10.2172/6888806.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

BOWEN, W. W. Advanced Reactors Transition Program Resource Loaded Schedule. Office of Scientific and Technical Information (OSTI), November 1999. http://dx.doi.org/10.2172/798702.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Durst, Philip C., Ike Therios, Robert Bean, A. Dougan, Brian Boyer, Rick L. Wallace, Michael H. Ehinger, Don N. Kovacic, and K. Tolk. Advanced Safeguards Approaches for New Fast Reactors. Office of Scientific and Technical Information (OSTI), December 2007. http://dx.doi.org/10.2172/949148.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

GANTT, D. A. Advanced Reactors Transition Program Resource Loaded Schedule. Office of Scientific and Technical Information (OSTI), January 2000. http://dx.doi.org/10.2172/801171.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Korsah, Kofi, Pradeep Ramuhalli, R. Vlim, Roger A. Kisner, Charles L. Britton, Jr, D. W. Wootan, N. C. Anheier, Jr, et al. Assessment of Sensor Technologies for Advanced Reactors. Office of Scientific and Technical Information (OSTI), October 2016. http://dx.doi.org/10.2172/1345781.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Nowlen, Steven Patrick, Victor G. Figueroa, Tara Jean Olivier, John C. Hewson, and Thomas K. Blanchat. Metal fires and their implications for advanced reactors. Office of Scientific and Technical Information (OSTI), October 2010. http://dx.doi.org/10.2172/1010415.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Goodarz Ahmadi. ADVANCED COMPUTATIONAL MODEL FOR THREE-PHASE SLURRY REACTORS. Office of Scientific and Technical Information (OSTI), November 2000. http://dx.doi.org/10.2172/825379.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Goodarz Ahmadi. ADVANCED COMPUTATIONAL MODEL FOR THREE-PHASE SLURRY REACTORS. Office of Scientific and Technical Information (OSTI), October 2001. http://dx.doi.org/10.2172/825380.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Cetiner, Sacit M., Michael D. Muhlheim, Askin Guler Yigitoglu, Randall (Randy) J. Belles, Michael Scott Greenwood, Thomas Jay Harrison, Richard S. Denning, et al. Supervisory Control System for Multi-Modular Advanced Reactors. Office of Scientific and Technical Information (OSTI), November 2016. http://dx.doi.org/10.2172/1615832.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Advanced Reactors' for particular source types:
Journal articles Dissertations / Theses Books
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography