Tokamak Experimental Power Reactor Conceptual Design Volume Ii
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Release | : 1976 |
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Volume II contains the following appendices: (1) summary of EPR design parameters, (2) impurity control, (3) plasma computational models, (4) structural support system, (5) materials considerations for the primary energy conversion system, (6) magnetics, (7) neutronics penetration analysis, (8) first wall stress analysis, (9) enrichment of isotopes of hydrogen by cryogenic distillation, and (10) noncircular plasma considerations. (MOW).
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Release | : 1976 |
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A conceptual design has been developed for a tokamak Experimental Power Reactor to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 years. The EPR operates in a pulsed mode at a frequency of approximately 1/min., with an approximate 75 percent duty cycle, is capable of producing approximately 72 MWe and requires 42 MWe. The annual tritium consumption is 16 kg. The EPR vacuum chamber is 6.25 m in major radius and 2.4 m in minor radius, is constructed of 2-cm thick stainless steel, and has 2-cm thick detachable, beryllium-coated coolant panels mounted on the interior. An 0.28 m stainless steel blanket and a shield ranging from 0.6 to 1.0 m surround the vacuum vessel. The coolant is H2O. Sixteen niobium-titanium superconducting toroidal-field coils provide a field of 10 T at the coil and 4.47 T at the plasma. Superconducting ohmic-heating and equilibrium-field coils provide 135 V-s to drive the plasma current. Plasma heating is accomplished by 12 neutral beam-injectors, which provide 60 MW. The energy transfer and storage system consists of a central superconducting storage ring, a homopolar energy storage unit, and a variety of inductor-converters.
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Total Pages | : 674 |
Release | : 1976 |
Genre | : Fusion reactors |
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Total Pages | : 310 |
Release | : 1976 |
Genre | : Fusion reactors |
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Total Pages | : 946 |
Release | : 1990 |
Genre | : Power resources |
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Release | : 1976 |
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A conceptual design has been developed for a tokamak Experimental Power Reactor to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 yr. The EPR operates in a pulsed mode at a frequency of approximately 1/min, with approximately 75 percent duty cycle, is capable of producing approximately 72 MWe and requires 42 MWe. The annual tritium consumption is 16 kg. The EPR vacuum chamber is 6.25 m in major radius and 2.4 m in minor radius, is constructed of 2 cm thick stainless steel, and has 2 cm thick detachable, beryllium-coated coolant panels mounted on the interior. A 0.28 m stainless steel blanket and a shield ranging from 0.6 to 1.0 m surround the vacuum vessel. The coolant is H/sub 2/O. Sixteen niobium-titanium superconducting toroidal field coils provide a field of 10 T at the coil and 4.47 T at the plasma. Superconducting ohmic heating and equilibrium field coils provide 135 V-s to drive the plasma current. Plasma heating is accomplished by 12 neutral beam injectors which provide 60 MW. The energy transfer and storage system consists of a central superconducting storage ring, a homopolar energy storage unit, and a variety of inductor-convertors.
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Total Pages | : 742 |
Release | : 1977 |
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Author | : |
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Total Pages | : |
Release | : 1976 |
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A conceptual design has been developed for a tokamak Experimental Power Reactor to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 yr. The EPR operates in a pulsed mode at a frequency of approximately 1/min, with approximately 75 percent duty cycle, is capable of producing approximately 72 MWe and requires 42 MWe. The annual tritium consumption is 16 kg. The EPR vacuum chamber is 6.25 m in major radius and 2.4 m in minor radius, is constructed of 2 cm thick stainless steel, and has 2 cm thick detachable, beryllium-coated coolant panels mounted on the interior. A 0.28 m stainless steel blanket and a shield ranging from 0.6 to 1.0 m surround the vacuum vessel. The coolant is H2O. Sixteen niobium-titanium superconducting toroidal field coils provide a field of 10 T at the coil and 4.47 T at the plasma. Superconducting ohmic heating and equilibrium field coils provide 135 V-s to drive the plasma current. Plasma heating is accomplished by 12 neutral beam injectors which provide 60 MW. The energy transfer and storage system consists of a central superconducting storage ring, a homopolar energy storage unit, and a variety of inductor-convertors.
Author | : United States. Energy Research and Development Administration. Technical Information Center |
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Total Pages | : 1680 |
Release | : 1977 |
Genre | : Force and energy |
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Author | : H. Knoepfel |
Publisher | : Elsevier |
Total Pages | : 657 |
Release | : 2013-10-08 |
Genre | : Technology & Engineering |
ISBN | : 1483181995 |
Tokamak Reactors for Breakeven: A Critical Study of the Near-Term Fusion Reactor Program presents all possible aspects concerning the Tokamak line of research. This book examines the many significant implications of fusion research programs. Organized into five parts encompassing 29 chapters, this book begins with an overview of the mechanisms of anomalous loss in existing machines. This text then examines the environmental problems related to the use of large quantities of tritium. Other chapters consider the technology of superconducting Tokamak magnets, which provides challenging tasks both for specific developments in laboratories and hardware construction in industry. This book discusses as well the established program goal of the fusion program to develop and demonstrate pure fusion central electric power stations for commercial applications. The final chapter deals with the two types of reactors, namely, the liquid metal fast breeder reactors (LMFBR) and the high temperature reactors (HTR). This book is a valuable resource for scientists, engineers, and technologists.