Download or read book Thorium fueled D2O moderated Power Reactors written by Dale F. Babcock and published by . This book was released on 1963 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Heavy Water Moderated Power Reactors written by and published by . This book was released on 1958-11 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book D2O moderated Power Reactors written by and published by . This book was released on 1959 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Use of Thorium in Nuclear Power Reactors written by and published by . This book was released on 1969 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thorium Fuel Cycle written by Fouad Sabry and published by One Billion Knowledgeable. This book was released on 2022-10-15 with total page 530 pages. Available in PDF, EPUB and Kindle. Book excerpt: What Is Thorium Fuel Cycle The fertile material in the thorium fuel cycle is an isotope of thorium called 232Th, and the thorium fuel cycle itself is a kind of nuclear fuel cycle. Within the reactor, 232Th is converted into the fissile artificial uranium isotope 233U, which is then used as the fuel for the nuclear reactor. Natural thorium, in contrast to natural uranium, only contains minute quantities of fissile material, which is insufficient to kick off a nuclear chain reaction. In order to kickstart the fuel cycle, either more fissile material or an other neutron source is required. 233U is created when 232Th, which is powered by thorium, absorbs neutrons in a reactor. This is analogous to the process that occurs in uranium breeder reactors, in which fertile 238U is subjected to neutron absorption in order to produce fissile 239Pu. The produced 233U either fissions in situ or is chemically removed from the old nuclear fuel and converted into new nuclear fuel, depending on the architecture of the reactor and the fuel cycle. Fissioning in situ is the more efficient method. How You Will Benefit (I) Insights, and validations about the following topics: Chapter 1: Thorium fuel cycle Chapter 2: Nuclear reactor Chapter 3: Radioactive waste Chapter 4: Fissile material Chapter 5: Nuclear fuel cycle Chapter 6: MOX fuel Chapter 7: Breeder reactor Chapter 8: Uranium-238 Chapter 9: Energy amplifier Chapter 10: Subcritical reactor Chapter 11: Integral fast reactor Chapter 12: Fertile material Chapter 13: Uranium-233 Chapter 14: Plutonium-239 Chapter 15: Isotopes of uranium Chapter 16: Isotopes of plutonium Chapter 17: Weapons-grade nuclear material Chapter 18: Uranium-236 Chapter 19: Burnup Chapter 20: Liquid fluoride thorium reactor Chapter 21: Nuclear transmutation (II) Answering the public top questions about thorium fuel cycle. (III) Real world examples for the usage of thorium fuel cycle in many fields. (IV) 17 appendices to explain, briefly, 266 emerging technologies in each industry to have 360-degree full understanding of thorium fuel cycle' technologies. Who This Book Is For Professionals, undergraduate and graduate students, enthusiasts, hobbyists, and those who want to go beyond basic knowledge or information for any kind of thorium fuel cycle.
Download or read book An Evaluation of Heavy water moderated Power Reactors written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thorium Fuel Cycle written by International Atomic Energy Agency and published by . This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.
Download or read book Heavy Water Moderated Power Reactors written by and published by . This book was released on 1964-05 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thorium Energy for the Future written by A.K. Nayak and published by Springer. This book was released on 2019-01-30 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book comprises selected proceedings of the ThEC15 conference. The book presents research findings on various facets of thorium energy, including exploration and mining, thermo-physical and chemical properties of fuels, reactor physics, challenges in fuel fabrication, thorium fuel cycles, thermal hydraulics and safety, material challenges, irradiation experiences, and issues and challenges for the design of advanced thorium fueled reactors. Thorium is more abundant than uranium and has the potential to provide energy to the world for centuries if used in a closed fuel cycle. As such, technologies for using thorium for power generation in nuclear reactors are being developed worldwide. Since there is a strong global thrust towards designing nuclear reactors with thorium-based fuel, this book will be of particular interest to nuclear scientists, reactor designers, regulators, academics and policymakers.
Download or read book Large heavy water moderated Power Reactors written by and published by . This book was released on 1964 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Design and Analysis of Thorium fueled Reduced Moderation Boiling Water Reactors written by Phillip Michael Gorman and published by . This book was released on 2016 with total page 177 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Resource-renewable Boiling Water Reactors (RBWRs) are a set of light water reactors (LWRs) proposed by Hitachi which use a triangular lattice and high void fraction to incinerate fuel with an epithermal spectrum, which is highly atypical of LWRs. The RBWRs operate on a closed fuel cycle, which is impossible with a typical thermal spectrum reactor, in order to accomplish missions normally reserved for sodium fast reactors (SFRs) - either fuel self-sufficiency or waste incineration. The RBWRs also axially segregate the fuel into alternating fissile "seed" regions and fertile "blanket" regions in order to enhance breeding and leakage probability upon coolant voiding. This dissertation focuses on thorium design variants of the RBWR: the self-sufficient RBWR-SS and the RBWR-TR, which consumes reprocessed transuranic (TRU) waste from PWR used nuclear fuel. These designs were based off of the Hitachi-designed RBWR-AC and the RBWR-TB2, respectively, which use depleted uranium (DU) as the primary fertile fuel. The DU-fueled RBWRs use a pair of axially segregated seed sections in order to achieve a negative void coefficient; however, several concerns were raised with this multi-seed approach, including difficulty with controlling the reactor and unacceptably high axial power peaking. Since thorium-uranium fuel tends to have much more negative void feedback than uranium-plutonium fuels, the thorium RBWRs were designed to use a single elongated seed to avoid these issues. A series of parametric studies were performed in order to find the design space for the thorium RBWRs, and optimize the designs while meeting the required safety constraints. The RBWR-SS was optimized to maximize the discharge burnup, while the RBWR-TR was optimized to maximize the TRU transmutation rate. These parametric studies were performed on an assembly level model using the MocDown simulator, which calculates an equilibrium fuel composition with a specified reprocessing scheme. A full core model was then created for each design, using the Serpent/PARCS 3-D core simulator, and the full core performance was assessed. The RBWR-SS benefited from a harder spectrum than the RBWR-TR; a hard spectrum promotes breeding and increases the discharge burnup, but reduces the TRU transmutation rate. This led the RBWR-SS to have a very tight lattice, which has a lot of experimental uncertainty in the thermal hydraulic correlations. Two different RBWR-SS designs were created assuming different thermal hydraulic assumptions: the RBWR-SSH used the same assumptions as Hitachi used for the RBWR-AC, while the RBWR-SSM used more conservative correlations recommended by collaborators at MIT. However, the void feedback of the pure Th-fed system was too strongly negative, even with a single elongated seed. Therefore, instead of using just thorium, the self-sustaining designs were fed with a mix of between 30% and 50% DU and the rest thorium in order to keep the void feedback as close to zero as possible. This was not necessary for the RBWR-TR, as the external TRU feed fulfilled a similar role. Unfortunately, it was found that the RBWR-SSM could not sustain a critical cycle without either significantly downgrading the power or supplying an external feed of fissile material. While the RBWR-SSH and the RBWR-TR could reach similar burnups and transmutation rates to their DU-fueled counterparts as designed by Hitachi, the thorium designs were unable to simultaneously have negative void feedback and sufficient shutdown margin to shut down the core. The multi-seed approach of the Hitachi designs allowed their reactors to have much lower magnitudes of Doppler feedback than the single-seed designs, which helps them to have sufficient shutdown margin. It is expected that thorium-fueled RBWRs designed to have multiple seeds would permit adequate shutdown margin, although care would need to be taken in order to avoid running into the same issues as the DU fueled RBWRs. Alternatively, it may be possible to increase the amount of boron in the control blades by changing the assembly and core design. Nonetheless, the uncertainties in the multiplication factor due to nuclear data and void fraction uncertainty were assessed for the RBWR-SSH and the RBWR-TR, as well as for the RBWR-TB2. In addition, the uncertainty associated with the change in reactor states (such as the reactivity insertion in flooding the core) due to nuclear data uncertainties was quantified. The thorium RBWRs have much larger uncertainty of their DU-fueled counterparts as designed by Hitachi, as the fission cross section of 233U has very large uncertainty in the epithermal energy range. The uncertainty in the multiplication factor at reference conditions was about 1350 pcm for the RBWR-SSH, while it was about 900 pcm for the RBWR-TR. The uncertainty in the void coefficient of reactivity for both reactors is between 8 and 10 pcm/% void, which is on the same order of magnitude as the full core value. Finally, since sharp linear heat rate spikes were observed in the RBWR-TB2 simulation, the RBWR-TB2 unit cell was simulated using a much finer mesh than is possible using deterministic codes. It was found that the thermal neutrons reflecting back from the reflectors and the blankets were causing extreme spikes in the power density near the axial boundaries of the seeds, which were artificially smoothed out when using coarser meshes. It is anticipated that these spikes will cause melting in both seeds in the RBWR-TB2, unless design changes - such as reducing the enrichment level near the axial boundaries of the seeds - are made.
Download or read book The Thorium Fuel Cycle in Water moderated Reactor Systems written by E. Critoph and published by Chalk River, Ont. : Chalk River Nuclear Laboratories. This book was released on 1977 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Power Reactor Technology written by and published by . This book was released on 1957 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Heavy Water Moderated Reactor Design Studies State of the art Survey written by K. R. Wise and published by . This book was released on 1968 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the Heavy Water Reactor Program Office effort to define the "state-of-the-art" in heavy water moderated reactors a survey of reactor designs and design studies was undertaken. This survey includes: 1. A list and descriptions of the heavy water moderated power reactors either operating or under construction; 2. A list and description of the more recent design studies done no heavy water moderated reactors, with the exception of reactors using organic coolant; 3. A discussion of the various reactor types, as determined by type of coolant, indicating development trends; 4. A discussion of various design features or characteristics that many heavy water reactors have in common, such as pressure tubes, on-line refueling, and D2O loss rates.
Download or read book THORIUM FUEL CYCLE IN WATER MODERATED REACTOR SYSTEMS written by Atomic Energy of Canada Limited and published by . This book was released on 1975 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1962 with total page 506 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1970-03 with total page 946 pages. Available in PDF, EPUB and Kindle. Book excerpt:
