Lunar mission design using nuclear thermal rockets

International Nuclear Information System (INIS)

Stancati, M.L.; Collins, J.T.; Borowski, S.K.

1991-01-01

The NERVA-class Nuclear Thermal Rocket (NTR), with performance nearly double that of advanced chemical engines, has long been considered an enabling technology for human missions to Mars. NTR engines address the demanding trip time and payload delivery needs of both cargo-only and piloted flights. But NTR can also reduce the Earth launch requirements for manned lunar missions. First use of NTR for the Moon would be less demanding and would provide a test-bed for early operations experience with this powerful technology. Study of application and design options indicates that NTR propulsion can be integrated with the Space Exploration Initiative scenarios to deliver performance gains while managing controlled, long-term disposal of spent reactors to highly stable orbits

Nuclear Rocket Engine Reactor

CERN Document Server

Lanin, Anatoly

2013-01-01

The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

Preliminary design study for a carbide LEU-nuclear thermal rocket

International Nuclear Information System (INIS)

Venneri, P.F.; Kim, Y.

2014-01-01

Nuclear space propulsion is a requirement for the successful exploration of the solar system. It offers the possibility of having both a high specific impulse and a relatively high thrust, allowing rapid transit times with a minimum usage of fuel. This paper proposes a nuclear thermal rocket design based on heritage NERVA rockets that makes use of Low Enriched Uranium (LEU) fuel. The Carbide LEU Nuclear Thermal Rocket (C-LEU-NTR) is designed to fulfill the rocket requirements as set forth in the NASA 2009 Mars Mission Design Reference Architecture 5.0, that is provide 25,000 lbf of thrust, operate at full power condition for at least two hours, and have a specific impulse close to 900 s. The neutronics analysis was done using MCNP5 with the ENDF/B-VII.1 neutron library. The thermal hydraulic calculations and size optimization were completed with a finite difference code being developed at the Center for Space Nuclear Research. (authors)

Innovative nuclear thermal rocket concept utilizing LEU fuel for space application

International Nuclear Information System (INIS)

Nam, Seung Hyun; Venneri, Paolo; Choi, Jae Young; Jeong, Yong Hoon; Chang, Soon Heung

2015-01-01

Space is one of the best places for humanity to turn to keep learning and exploiting. A Nuclear Thermal Rocket (NTR) is a viable and more efficient option for human space exploration than the existing Chemical Rockets (CRs) which are highly inefficient for long-term manned missions such as to Mars and its satellites. NERVA derived NTR engines have been studied for the human missions as a mainstream in the United States of America (USA). Actually, the NERVA technology has already been developed and successfully tested since 1950s. The state-of-the-art technology is based on a Hydrogen gas (H_2) cooled high temperature reactor with solid core utilizing High-Enriched Uranium (HEU) fuel to reduce heavy metal mass and to use fast or epithermal neutron spectrums enabling simple core designs. However, even though the NTR designs utilizing HEU is the best option in terms of rocket performance, they inevitably provoke nuclear proliferation obstacles on all Research and Development (R and D) activities by civilians and non-nuclear weapon states, and its eventual commercialization. To surmount the security issue to use HEU fuel for a NTR, a concept of the innovative NTR engine, Korea Advanced NUclear Thermal Engine Rocket utilizing Low-Enriched Uranium fuel (KANUTER-LEU) is presented in this paper. The design goal of KANUTER-LEU is to make use of a LEU fuel for its compact reactor, but does not sacrifice the rocket performance relative to the traditional NTRs utilizing HEU. KANUTER-LEU mainly consists of a fission reactor utilizing H_2 propellant, a propulsion system and an optional Electricity Generation System as a bimodal engine. To implement LEU fuel for the reactor, the innovative engine adopts W-UO_2 CERMET fuel to drastically increase uranium density and thermal neutron spectrum to improve neutron economy in the core. The moderator and structural material selections also consider neutronic and thermo-physical characteristics to reduce non-fission neutron loss and

Technology for low cost solid rocket boosters.

Science.gov (United States)

Ciepluch, C.

1971-01-01

A review of low cost large solid rocket motors developed at the Lewis Research Center is given. An estimate is made of the total cost reduction obtainable by incorporating this new technology package into the rocket motor design. The propellant, case material, insulation, nozzle ablatives, and thrust vector control are discussed. The effect of the new technology on motor cost is calculated for a typical expandable 260-in. booster application. Included in the cost analysis is the influence of motor performance variations due to specific impulse and weight changes. It is found for this application that motor costs may be reduced by up to 30% and that the economic attractiveness of future large solid rocket motors will be improved when the new technology is implemented.

Grooved Fuel Rings for Nuclear Thermal Rocket Engines

Science.gov (United States)

Emrich, William

2009-01-01

An alternative design concept for nuclear thermal rocket engines for interplanetary spacecraft calls for the use of grooved-ring fuel elements. Beyond spacecraft rocket engines, this concept also has potential for the design of terrestrial and spacecraft nuclear electric-power plants. The grooved ring fuel design attempts to retain the best features of the particle bed fuel element while eliminating most of its design deficiencies. In the grooved ring design, the hydrogen propellant enters the fuel element in a manner similar to that of the Particle Bed Reactor (PBR) fuel element.

Nuclear thermal rockets using indigenous Martian propellants

International Nuclear Information System (INIS)

Zubrin, R.M.

1989-01-01

This paper considers a novel concept for a Martian descent and ascent vehicle, called NIMF (for nuclear rocket using indigenous Martian fuel), the propulsion for which will be provided by a nuclear thermal reactor which will heat an indigenous Martian propellant gas to form a high-thrust rocket exhaust. The performance of each of the candidate Martian propellants, which include CO2, H2O, CH4, N2, CO, and Ar, is assessed, and the methods of propellant acquisition are examined. Attention is also given to the issues of chemical compatibility between candidate propellants and reactor fuel and cladding materials, and the potential of winged Mars supersonic aircraft driven by this type of engine. It is shown that, by utilizing the nuclear landing craft in combination with a hydrogen-fueled nuclear thermal interplanetary vehicle and a heavy lift booster, it is possible to achieve a manned Mars mission in one launch. 6 refs

Rocketing into the future the history and technology of rocket planes

CERN Document Server

van Pelt, Michel

2012-01-01

Rocketing into the Future journeys into the exciting world of rocket planes, examining the exotic concepts and actual flying vehicles that have been devised over the last one hundred years. Lavishly illustrated with over 150 photographs, it recounts the history of rocket planes from the early pioneers who attached simple rockets on to their wooden glider airplanes to the modern world of high-tech research vehicles. The book then looks at the possibilities for the future. The technological and economic challenges of the Space Shuttle proved insurmountable, and thus the program was unable to fulfill its promise of low-cost access to space. However, the burgeoning market of suborbital space tourism may yet give the necessary boost to the development of a truly reusable spaceplane.

Nuclear Thermal Rocket Element Environmental Simulator (NTREES)

International Nuclear Information System (INIS)

Emrich, William J. Jr.

2008-01-01

To support a potential future development of a nuclear thermal rocket engine, a state-of-the-art non nuclear experimental test setup has been constructed to evaluate the performance characteristics of candidate fuel element materials and geometries in representative environments. The test device simulates the environmental conditions (minus the radiation) to which nuclear rocket fuel components could be subjected during reactor operation. Test articles mounted in the simulator are inductively heated in such a manner as to accurately reproduce the temperatures and heat fluxes normally expected to occur as a result of nuclear fission while at the same time being exposed to flowing hydrogen. This project is referred to as the Nuclear Thermal Rocket Element Environment Simulator or NTREES. The NTREES device is located at the Marshall Space flight Center in a laboratory which has been modified to accommodate the high powers required to heat the test articles to the required temperatures and to handle the gaseous hydrogen flow required for the tests. Other modifications to the laboratory include the installation of a nitrogen gas supply system and a cooling water supply system. During the design and construction of the facility, every effort was made to comply with all pertinent regulations to provide assurance that the facility could be operated in a safe and efficient manner. The NTREES system can currently supply up to 50 kW of inductive heating to the fuel test articles, although the facility has been sized to eventually allow test article heating levels of up to several megawatts

Rhenium Rocket Manufacturing Technology

Science.gov (United States)

1997-01-01

The NASA Lewis Research Center's On-Board Propulsion Branch has a research and technology program to develop high-temperature (2200 C), iridium-coated rhenium rocket chamber materials for radiation-cooled rockets in satellite propulsion systems. Although successful material demonstrations have gained much industry interest, acceptance of the technology has been hindered by a lack of demonstrated joining technologies and a sparse materials property data base. To alleviate these concerns, we fabricated rhenium to C-103 alloy joints by three methods: explosive bonding, diffusion bonding, and brazing. The joints were tested by simulating their incorporation into a structure by welding and by simulating high-temperature operation. Test results show that the shear strength of the joints degrades with welding and elevated temperature operation but that it is adequate for the application. Rhenium is known to form brittle intermetallics with a number of elements, and this phenomena is suspected to cause the strength degradation. Further bonding tests with a tantalum diffusion barrier between the rhenium and C-103 is planned to prevent the formation of brittle intermetallics.

Unique nuclear thermal rocket engine

International Nuclear Information System (INIS)

Culver, D.W.; Rochow, R.

1993-06-01

In January, 1992, a new, advanced nuclear thermal rocket engine (NTRE) concept intended for manned missions to the moon and to Mars was introduced (Culver, 1992). This NTRE promises to be both shorter and lighter in weight than conventionally designed engines, because its forward flowing reactor is located within an expansion-deflection rocket nozzle. The concept has matured during the year, and this paper discusses a nearer term version that resolves four open issues identified in the initial concept: (1) the reactor design and cooling scheme simplification while retaining a high pressure power balance option; (2) elimination need for a new, uncooled nozzle throat material suitable for long life application; (3) a practical provision for reactor power control; and (4) use of near-term, long-life turbopumps

The broad view of nuclear technology for aerospace

International Nuclear Information System (INIS)

Buden, D.; Angelo, J.A. Jr.

1991-01-01

Nuclear technologies can directly support advanced space initiatives. For near-Earth missions, nuclear technology can be used to power air traffic control, communications and manufacturing platforms, provide emergency power for manned platforms, provide power for maneuvering units, move asteroids for mining, measure the natural radiation environment, provide radiation protection instruments, and design radiation hardened robotic systems. For the Lunar and Mars surfaces, nuclear technology can be used for base stationary, mobile, and emergency power, energy storage, process heat, nuclear thermal and electric rocket propulsion, excavation and underground engineering, water and sewage treatment and sterilization, food processing and preservation, mineral exploration, self-luminous systems, radiation protection instrumentation, radiation environmental warning systems, and habitat shielding design. Outer planet missions can make use of nuclear technology for power and propulsion. Programs need to be initiated to ensure the full beneficial use of nuclear technologies in advanced space missions

Nuclear power technology requirements for NASA exploration missions

International Nuclear Information System (INIS)

Bloomfield, H.S.

1990-01-01

This paper discusses how future exploration of the Moon and Mars will mandate developments in many areas of technology. In particular, major advances will be required in planet surface power systems and space transportation systems. Critical nuclear technology challenges that can enable strategic self-sufficiency, acceptable operational costs and cost-effective space transportation goals for NASA exploration missions have been identified. Critical technologies for surface power systems include stationary and mobile nuclear reactor and radio-isotope heat sources coupled to static and dynamic power conversion devices. These technologies can provide dramatic reductions in mass leading to operational and transportation cost savings. Critical technologies for space transportation systems include nuclear thermal rocket and nuclear electric propulsion options which present compelling concepts for significantly reducing mass, cost or travel time required for Earth-Mars transport

Nuclear thermal rocket nozzle testing and evaluation program

International Nuclear Information System (INIS)

Davidian, K.O.; Kacynski, K.J.

1993-01-01

Performance characteristics of the Nuclear Thermal Rocket can be enhanced through the use of unconventional nozzles as part of the propulsion system. In this report, the Nuclear Thermal Rocket nozzle testing and evaluation program being conducted at the NASA Lewis Research Center is outlined and the advantages of a plug nozzle are described. A facility description, experimental designs and schematics are given. Results of pretest performance analyses show that high nozzle performance can be attained despite substantial nozzle length reduction through the use of plug nozzles as compared to a convergent-divergent nozzle. Pretest measurement uncertainty analyses indicate that specific impulse values are expected to be within plus or minus 1.17%

Turbopump Design and Analysis Approach for Nuclear Thermal Rockets

International Nuclear Information System (INIS)

Chen, Shucheng S.; Veres, Joseph P.; Fittje, James E.

2006-01-01

A rocket propulsion system, whether it is a chemical rocket or a nuclear thermal rocket, is fairly complex in detail but rather simple in principle. Among all the interacting parts, three components stand out: they are pumps and turbines (turbopumps), and the thrust chamber. To obtain an understanding of the overall rocket propulsion system characteristics, one starts from analyzing the interactions among these three components. It is therefore of utmost importance to be able to satisfactorily characterize the turbopump, level by level, at all phases of a vehicle design cycle. Here at the NASA Glenn Research Center, as the starting phase of a rocket engine design, specifically a Nuclear Thermal Rocket Engine design, we adopted the approach of using a high level system cycle analysis code (NESS) to obtain an initial analysis of the operational characteristics of a turbopump required in the propulsion system. A set of turbopump design codes (PumpDes and TurbDes) were then executed to obtain sizing and performance parameters of the turbopump that were consistent with the mission requirements. A set of turbopump analyses codes (PUMPA and TURBA) were applied to obtain the full performance map for each of the turbopump components; a two dimensional layout of the turbopump based on these mean line analyses was also generated. Adequacy of the turbopump conceptual design will later be determined by further analyses and evaluation. In this paper, descriptions and discussions of the aforementioned approach are provided and future outlooks are discussed

Nuclear Thermal Rocket Element Environmental Simulator (NTREES) Upgrade Activities

Science.gov (United States)

Emrich, William J. Jr.; Moran, Robert P.; Pearson, J. Boise

2012-01-01

To support the on-going nuclear thermal propulsion effort, a state-of-the-art non nuclear experimental test setup has been constructed to evaluate the performance characteristics of candidate fuel element materials and geometries in representative environments. The facility to perform this testing is referred to as the Nuclear Thermal Rocket Element Environment Simulator (NTREES). This device can simulate the environmental conditions (minus the radiation) to which nuclear rocket fuel components will be subjected during reactor operation. Test articles mounted in the simulator are inductively heated in such a manner so as to accurately reproduce the temperatures and heat fluxes which would normally occur as a result of nuclear fission and would be exposed to flowing hydrogen. Initial testing of a somewhat prototypical fuel element has been successfully performed in NTREES and the facility has now been shutdown to allow for an extensive reconfiguration of the facility which will result in a significant upgrade in its capabilities

The behavior of fission products during nuclear rocket reactor tests

International Nuclear Information System (INIS)

Bokor, P.C.; Kirk, W.L.; Bohl, R.J.

1991-01-01

Fission product release from nuclear rocket propulsion reactor fuel is an important consideration for nuclear rocket development and application. Fission product data from the last six reactors of the Rover program are collected in this paper to provide as basis for addressing development and testing issues. Fission product loss from the fuel will depend on fuel composition and reactor design and operating parameters. During ground testing, fission products can be contained downstream of the reactor. The last Rover reactor tested, the Nuclear Furnance, was mated to an effluent clean-up system that was effective in preventing the discharge of fission products into the atmosphere

Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Lee, Jeong Ik; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2014-05-15

Nclear rockets improve the propellant efficiency more than twice compared to CRs and thus significantly reduce the propellant requirement. The superior efficiency of nuclear rockets is due to the combination of the huge energy density and a single low molecular weight propellant utilization. Nuclear Thermal Rockets (NTRs) are particularly suitable for manned missions to Mars because it satisfies a relatively high thrust as well as a high propellant efficiency. NTRs use thermal energy released from a nuclear fission reactor to heat a single low molecular weight propellant, i. e., Hydrogen (H{sub 2}) and then exhausted the extremely heated propellant through a thermodynamic nozzle to produce thrust. A propellant efficiency parameter of rocket engines is specific impulse (I{sub sp}) which represents the ratio of the thrust over the rate of propellant consumption. The difference of I{sub sp} makes over three times propellant savings of NTRs for a manned Mars mission compared to CRs. NTRs can also be configured to operate bimodally by converting the surplus nuclear energy to auxiliary electric power required for the operation of a spacecraft. Moreover, the concept and technology of NTRs are very simple, already proven, and safe. Thus, NTRs can be applied to various space missions such as solar system exploration, International Space Station (ISS) transport support, Near Earth Objects (NEOs) interception, etc. Nuclear propulsion is the most promising and viable option to achieve challenging deep space missions. Particularly, the attractions of a NTR include excellent thrust and propellant efficiency, bimodal capability, proven technology, and safe and reliable performance. The ROK has also begun the research for space nuclear systems as a volunteer of the international space race and a major world nuclear energy country. KANUTER is one of the advanced NTR engines currently under development at KAIST. This bimodal engine is operated in two modes of propulsion with 100 MW

Nuclear Thermal Rocket Simulation in NPSS

Science.gov (United States)

Belair, Michael L.; Sarmiento, Charles J.; Lavelle, Thomas M.

2013-01-01

Four nuclear thermal rocket (NTR) models have been created in the Numerical Propulsion System Simulation (NPSS) framework. The models are divided into two categories. One set is based upon the ZrC-graphite composite fuel element and tie tube-style reactor developed during the Nuclear Engine for Rocket Vehicle Application (NERVA) project in the late 1960s and early 1970s. The other reactor set is based upon a W-UO2 ceramic-metallic (CERMET) fuel element. Within each category, a small and a large thrust engine are modeled. The small engine models utilize RL-10 turbomachinery performance maps and have a thrust of approximately 33.4 kN (7,500 lbf ). The large engine models utilize scaled RL-60 turbomachinery performance maps and have a thrust of approximately 111.2 kN (25,000 lbf ). Power deposition profiles for each reactor were obtained from a detailed Monte Carlo N-Particle (MCNP5) model of the reactor cores. Performance factors such as thermodynamic state points, thrust, specific impulse, reactor power level, and maximum fuel temperature are analyzed for each engine design.

The rationale/benefits of nuclear thermal rocket propulsion for NASA's lunar space transportation system

Science.gov (United States)

Borowski, Stanley K.

1994-09-01

The solid core nuclear thermal rocket (NTR) represents the next major evolutionary step in propulsion technology. With its attractive operating characteristics, which include high specific impulse (approximately 850-1000 s) and engine thrust-to-weight (approximately 4-20), the NTR can form the basis for an efficient lunar space transportation system (LTS) capable of supporting both piloted and cargo missions. Studies conducted at the NASA Lewis Research Center indicate that an NTR-based LTS could transport a fully-fueled, cargo-laden, lunar excursion vehicle to the Moon, and return it to low Earth orbit (LEO) after mission completion, for less initial mass in LEO than an aerobraked chemical system of the type studied by NASA during its '90-Day Study.' The all-propulsive NTR-powered LTS would also be 'fully reusable' and would have a 'return payload' mass fraction of approximately 23 percent--twice that of the 'partially reusable' aerobraked chemical system. Two NTR technology options are examined--one derived from the graphite-moderated reactor concept developed by NASA and the AEC under the Rover/NERVA (Nuclear Engine for Rocket Vehicle Application) programs, and a second concept, the Particle Bed Reactor (PBR). The paper also summarizes NASA's lunar outpost scenario, compares relative performance provided by different LTS concepts, and discusses important operational issues (e.g., reusability, engine 'end-of life' disposal, etc.) associated with using this important propulsion technology.

Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment

Energy Technology Data Exchange (ETDEWEB)

David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

2012-07-01

In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

Nuclear Thermal Rocket Element Environmental Simulator (NTREES) Phase II Upgrade Activities

Science.gov (United States)

Emrich, William J.; Moran, Robert P.; Pearson, J. Bose

2013-01-01

To support the on-going nuclear thermal propulsion effort, a state-of-the-art non nuclear experimental test setup has been constructed to evaluate the performance characteristics of candidate fuel element materials and geometries in representative environments. The facility to perform this testing is referred to as the Nuclear Thermal Rocket Element Environment Simulator (NTREES). This device can simulate the environmental conditions (minus the radiation) to which nuclear rocket fuel components will be subjected during reactor operation. Test articles mounted in the simulator are inductively heated in such a manner so as to accurately reproduce the temperatures and heat fluxes which would normally occur as a result of nuclear fission and would be exposed to flowing hydrogen. Initial testing of a somewhat prototypical fuel element has been successfully performed in NTREES and the facility has now been shutdown to allow for an extensive reconfiguration of the facility which will result in a significant upgrade in its capabilities. Keywords: Nuclear Thermal Propulsion, Simulator

On the use of a pulsed nuclear thermal rocket for interplanetary travel

OpenAIRE

Arias Montenegro, Francisco Javier

2016-01-01

The object of this work is a first assessment of the use of a pulsed nuclear thermal rocket for thrust and specific impulse (Isp) augmentation with particular reference to interplanetary travel. The basis of the novel space propulsion idea is the possibility of working in a bimodal fashion where the classical stationary nuclear thermal rocket (NTR) could be switch on or switch off as a pulsed reactor as desired by the mission planners. It was found that the key factor for Isp augmentation ...

A review of the Los Alamos effort in the development of nuclear rocket propulsion

International Nuclear Information System (INIS)

Durham, F.P.; Kirk, W.L.; Bohl, R.J.

1991-01-01

This paper reviews the achievements of the Los Alamos nuclear rocket propulsion program and describes some specific reactor design and testing problems encountered during the development program along with the progress made in solving these problems. The relevance of these problems to a renewed nuclear thermal rocket development program for the Space Exploration Initiative (SEI) is discussed. 11 figs

Reusable Rocket Engine Advanced Health Management System. Architecture and Technology Evaluation: Summary

Science.gov (United States)

Pettit, C. D.; Barkhoudarian, S.; Daumann, A. G., Jr.; Provan, G. M.; ElFattah, Y. M.; Glover, D. E.

1999-01-01

In this study, we proposed an Advanced Health Management System (AHMS) functional architecture and conducted a technology assessment for liquid propellant rocket engine lifecycle health management. The purpose of the AHMS is to improve reusable rocket engine safety and to reduce between-flight maintenance. During the study, past and current reusable rocket engine health management-related projects were reviewed, data structures and health management processes of current rocket engine programs were assessed, and in-depth interviews with rocket engine lifecycle and system experts were conducted. A generic AHMS functional architecture, with primary focus on real-time health monitoring, was developed. Fourteen categories of technology tasks and development needs for implementation of the AHMS were identified, based on the functional architecture and our assessment of current rocket engine programs. Five key technology areas were recommended for immediate development, which (1) would provide immediate benefits to current engine programs, and (2) could be implemented with minimal impact on the current Space Shuttle Main Engine (SSME) and Reusable Launch Vehicle (RLV) engine controllers.

Nuclear vapor thermal reactor propulsion technology

International Nuclear Information System (INIS)

Maya, I.; Diaz, N.J.; Dugan, E.T.; Watanabe, Y.; McClanahan, J.A.; Wen-Hsiung Tu; Carman, R.L.

1993-01-01

The conceptual design of a nuclear rocket based on the vapor core reactor is presented. The Nuclear Vapor Thermal Rocket (NVTR) offers the potential for a specific impulse of 1000 to 1200 s at thrust-to-weight ratios of 1 to 2. The design is based on NERVA geometry and systems with the solid fuel replaced by uranium tetrafluoride (UF 4 ) vapor. The closed-loop core does not rely on hydrodynamic confinement of the fuel. The hydrogen propellant is separated from the UF 4 fuel gas by graphite structure. The hydrogen is maintained at high pressure (∼100 atm), and exits the core at 3,100 K to 3,500 K. Zirconium carbide and hafnium carbide coatings are used to protect the hot graphite from the hydrogen. The core is surrounded by beryllium oxide reflector. The nuclear reactor core has been integrated into a 75 klb engine design using an expander cycle and dual turbopumps. The NVTR offers the potential for an incremental technology development pathway to high performance gas core reactors. Since the fuel is readily available, it also offers advantages in the initial cost of development, as it will not require major expenditures for fuel development

CFD Analysis of Square Flow Channel in Thermal Engine Rocket Adventurer for Space Nuclear Application

Energy Technology Data Exchange (ETDEWEB)

Nam, S. H.; Suh, K. Y. [Seoul National University, Seoul (Korea, Republic of); Kang, S. G. [PHILOSOPHIA, Inc., Seoul (Korea, Republic of)

2008-10-15

Solar system exploration relying on chemical rockets suffers from long trip time and high cost. In this regard nuclear propulsion is an attractive option for space exploration. The performance of Nuclear Thermal Rocket (NTR) is more than twice that of the best chemical rocket. Resorting to the pure hydrogen (H{sub 2}) propellant the NTRs can possibly achieve as high as 1,000 s of specific impulse (I{sub sp}) representing the ratio of the thrust over the fuel consumption rate, as compared to only 425 s of H{sub 2}/O{sub 2} rockets. If we reflect on the mission to Mars, NTRs would reduce the round trip time to less than 300 days, instead of over 600 days with chemical rockets. This work presents CFD analysis of one Fuel Element (FE) of Thermal Engine Rocket Adventurer (TERA). In particular, one Square Flow Channel (SFC) is analyzed in Square Lattice Honeycomb (SLHC) fuel to examine the effects of mass flow rate on rocket performance.

CFD Analysis of Square Flow Channel in Thermal Engine Rocket Adventurer for Space Nuclear Application

International Nuclear Information System (INIS)

Nam, S. H.; Suh, K. Y.; Kang, S. G.

2008-01-01

Solar system exploration relying on chemical rockets suffers from long trip time and high cost. In this regard nuclear propulsion is an attractive option for space exploration. The performance of Nuclear Thermal Rocket (NTR) is more than twice that of the best chemical rocket. Resorting to the pure hydrogen (H 2 ) propellant the NTRs can possibly achieve as high as 1,000 s of specific impulse (I sp ) representing the ratio of the thrust over the fuel consumption rate, as compared to only 425 s of H 2 /O 2 rockets. If we reflect on the mission to Mars, NTRs would reduce the round trip time to less than 300 days, instead of over 600 days with chemical rockets. This work presents CFD analysis of one Fuel Element (FE) of Thermal Engine Rocket Adventurer (TERA). In particular, one Square Flow Channel (SFC) is analyzed in Square Lattice Honeycomb (SLHC) fuel to examine the effects of mass flow rate on rocket performance

Small Rocket/Spacecraft Technology (SMART) Platform

Science.gov (United States)

Esper, Jaime; Flatley, Thomas P.; Bull, James B.; Buckley, Steven J.

2011-01-01

The NASA Goddard Space Flight Center (GSFC) and the Department of Defense Operationally Responsive Space (ORS) Office are exercising a multi-year collaborative agreement focused on a redefinition of the way space missions are designed and implemented. A much faster, leaner and effective approach to space flight requires the concerted effort of a multi-agency team tasked with developing the building blocks, both programmatically and technologically, to ultimately achieve flights within 7-days from mission call-up. For NASA, rapid mission implementations represent an opportunity to find creative ways for reducing mission life-cycle times with the resulting savings in cost. This in tum enables a class of missions catering to a broader audience of science participants, from universities to private and national laboratory researchers. To that end, the SMART (Small Rocket/Spacecraft Technology) micro-spacecraft prototype demonstrates an advanced avionics system with integrated GPS capability, high-speed plug-and-playable interfaces, legacy interfaces, inertial navigation, a modular reconfigurable structure, tunable thermal technology, and a number of instruments for environmental and optical sensing. Although SMART was first launched inside a sounding rocket, it is designed as a free-flyer.

Nuclear thermal rocket workshop reference system Rover/NERVA

International Nuclear Information System (INIS)

Borowski, S.K.

1991-01-01

The Rover/NERVA engine system is to be used as a reference, against which each of the other concepts presented in the workshop will be compared. The following topics are reviewed: the operational characteristics of the nuclear thermal rocket (NTR); the accomplishments of the Rover/NERVA programs; and performance characteristics of the NERVA-type systems for both Mars and lunar mission applications. Also, the issues of ground testing, NTR safety, NASA's nuclear propulsion project plans, and NTR development cost estimates are briefly discussed

Thermohydraulic Design Analysis Modeling for Korea Advanced NUclear Thermal Engine Rocket for Space Application

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung [KAIST, Daejeon (Korea, Republic of)

2015-05-15

NTR engines have continued as a main stream based on the mature technology. The typical core design of the NERVA derived engines uses hexagonal shaped fuel elements with circular cooling channels and structural tie-tube elements for supporting the fuel elements, housing moderator and regeneratively cooling the moderator. The state-of-the-art NTR designs mostly use a fast or epithermal neutron spectrum core utilizing a HEU fuel to make a high power reactor with small and simple core geometry. Nuclear propulsion is the most promising and viable option to achieve challenging deep space missions. Particularly, the attractions of a NTR include excellent thrust and propellant efficiency, bimodal capability, proven technology, and safe and reliable performance. The KANUTER-HEU and -LEU are the innovative and futuristic NTR engines to reduce the reactor size and to implement a LEU fuel in the reactor by using thermal neutron spectrum. The KANUTERs have some features in the reactor design such as the integrated fuel element and the regeneratively cooling channels to increase room for moderator and heat transfer in the core, and ensuing rocket performance. To study feasible design points in terms of thermo-hydraulics and to estimate rocket performance of the KANUTERs, the NSES is under development. The model of the NSES currently focuses on thermo-hydraulic analysis of the peculiar and complex EHTGR design during the propulsion mode in steady-state. The results indicate comparable performance for future applications, even though it uses the heavier LEU fuel. In future, the NSES will be modified to obtain temperature distribution of the entire reactor components and then more extensive design analysis of neutronics, thermohydraulics and their coupling will be conducted to validate design feasibility and to optimize the reactor design enhancing the rocket performance.

History of the development of rocket technology and astronautics in Poland

Science.gov (United States)

Geisler, W.

1977-01-01

The development of rocket technology in Poland is outlined. The history cites 13th century use of war rockets in combating Tartars as well as 20th century studies of the future and reality of space flights.

Gas core nuclear rocket feasibility project

International Nuclear Information System (INIS)

Howe, S.D.; DeVolder, B.; Thode, L.; Zerkle, D.

1997-09-01

The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas core nuclear rocket (GCNR) has the potential to be such a system. The gas core concept relies on the use of fluid dynamic forces to create and maintain a vortex. The vortex is composed of a fissile material which will achieve criticality and produce high power levels. By radiatively coupling to the surrounding fluids, extremely high temperatures in the propellant and, thus, high specific impulses can be generated. The ship velocities enabled by such performance may allow a 9 month round trip, manned Mars mission to be considered. Alternatively, one might consider slightly longer missions in ships that are heavily shielded against the intense Galactic Cosmic Ray flux to further reduce the radiation dose to the crew. The current status of the research program at the Los Alamos National Laboratory into the gas core nuclear rocket feasibility will be discussed

Use of Soft Computing Technologies For Rocket Engine Control

Science.gov (United States)

Trevino, Luis C.; Olcmen, Semih; Polites, Michael

2003-01-01

The problem to be addressed in this paper is to explore how the use of Soft Computing Technologies (SCT) could be employed to further improve overall engine system reliability and performance. Specifically, this will be presented by enhancing rocket engine control and engine health management (EHM) using SCT coupled with conventional control technologies, and sound software engineering practices used in Marshall s Flight Software Group. The principle goals are to improve software management, software development time and maintenance, processor execution, fault tolerance and mitigation, and nonlinear control in power level transitions. The intent is not to discuss any shortcomings of existing engine control and EHM methodologies, but to provide alternative design choices for control, EHM, implementation, performance, and sustaining engineering. The approaches outlined in this paper will require knowledge in the fields of rocket engine propulsion, software engineering for embedded systems, and soft computing technologies (i.e., neural networks, fuzzy logic, and Bayesian belief networks), much of which is presented in this paper. The first targeted demonstration rocket engine platform is the MC-1 (formerly FASTRAC Engine) which is simulated with hardware and software in the Marshall Avionics & Software Testbed laboratory that

U.S./CIS eye joint nuclear rocket venture

Science.gov (United States)

Clark, John S.; Mcilwain, Melvin C.; Smetanikov, Vladimir; D'Yakov, Evgenij K.; Pavshuk, Vladimir A.

1993-01-01

An account is given of the significance for U.S. spacecraft development of a nuclear thermal rocket (NTR) reactor concept that has been developed in the (formerly Soviet) Commonwealth of Independent States (CIS). The CIS NTR reactor employs a hydrogen-cooled zirconium hydride moderator and ternary carbide fuels; the comparatively cool operating temperatures associated with this design promise overall robustness.

Hydrocarbon Rocket Technology Impact Forecasting

Science.gov (United States)

Stuber, Eric; Prasadh, Nishant; Edwards, Stephen; Mavris, Dimitri N.

2012-01-01

Forecasting method is a normative forecasting technique that allows the designer to quantify the effects of adding new technologies on a given design. This method can be used to assess and identify the necessary technological improvements needed to close the gap that exists between the current design and one that satisfies all constraints imposed on the design. The TIF methodology allows for more design knowledge to be brought to the earlier phases of the design process, making use of tools such as Quality Function Deployments, Morphological Matrices, Response Surface Methodology, and Monte Carlo Simulations.2 This increased knowledge allows for more informed decisions to be made earlier in the design process, resulting in shortened design cycle time. This paper will investigate applying the TIF method, which has been widely used in aircraft applications, to the conceptual design of a hydrocarbon rocket engine. In order to reinstate a manned presence in space, the U.S. must develop an affordable and sustainable launch capability. Hydrocarbon-fueled rockets have drawn interest from numerous major government and commercial entities because they offer a low-cost heavy-lift option that would allow for frequent launches1. However, the development of effective new hydrocarbon rockets would likely require new technologies in order to overcome certain design constraints. The use of advanced design methods, such as the TIF method, enables the designer to identify key areas in need of improvement, allowing one to dial in a proposed technology and assess its impact on the system. Through analyses such as this one, a conceptual design for a hydrocarbon-fueled vehicle that meets all imposed requirements can be achieved.

A Programmatic and Engineering Approach to the Development of a Nuclear Thermal Rocket for Space Exploration

Science.gov (United States)

Bordelon, Wayne J., Jr.; Ballard, Rick O.; Gerrish, Harold P., Jr.

2006-01-01

With the announcement of the Vision for Space Exploration on January 14, 2004, there has been a renewed interest in nuclear thermal propulsion. Nuclear thermal propulsion is a leading candidate for in-space propulsion for human Mars missions; however, the cost to develop a nuclear thermal rocket engine system is uncertain. Key to determining the engine development cost will be the engine requirements, the technology used in the development and the development approach. The engine requirements and technology selection have not been defined and are awaiting definition of the Mars architecture and vehicle definitions. The paper discusses an engine development approach in light of top-level strategic questions and considerations for nuclear thermal propulsion and provides a suggested approach based on work conducted at the NASA Marshall Space Flight Center to support planning and requirements for the Prometheus Power and Propulsion Office. This work is intended to help support the development of a comprehensive strategy for nuclear thermal propulsion, to help reduce the uncertainty in the development cost estimate, and to help assess the potential value of and need for nuclear thermal propulsion for a human Mars mission.

The Rocket Balloon (Rocketball): Applications to Science, Technology, and Education

Science.gov (United States)

Esper, Jaime

2009-01-01

Originally envisioned to study upper atmospheric phenomena, the Rocket Balloon system (or Rocketball for short) has utility in a range of applications, including sprite detection and in-situ measurements, near-space measurements and calibration correlation with orbital assets, hurricane observation and characterization, technology testing and validation, ground observation, and education. A salient feature includes the need to reach space and near-space within a critical time-frame and in adverse local meteorological conditions. It can also provide for the execution of technology validation and operational demonstrations at a fraction of the cost of a space flight. In particular, planetary entry probe proof-of-concepts can be examined. A typical Rocketball operational scenario consists of a sounding rocket launch and subsequent deployment of a balloon above a desired location. An obvious advantage of this combination is the additional mission 'hang-time' rendered by the balloon once the sounding rocket flight is completed. The system leverages current and emergent technologies at the NASA Goddard Space Flight Center and other organizations.

Cryogenic rocket engine development at Delft aerospace rocket engineering

NARCIS (Netherlands)

Wink, J; Hermsen, R.; Huijsman, R; Akkermans, C.; Denies, L.; Barreiro, F.; Schutte, A.; Cervone, A.; Zandbergen, B.T.C.

2016-01-01

This paper describes the current developments regarding cryogenic rocket engine technology at Delft Aerospace Rocket Engineering (DARE). DARE is a student society based at Delft University of Technology with the goal of being the first student group in the world to launch a rocket into space. After

Design and analysis of a single stage to orbit nuclear thermal rocket reactor engine

Energy Technology Data Exchange (ETDEWEB)

Labib, Satira, E-mail: Satira.Labib@duke-energy.com; King, Jeffrey, E-mail: kingjc@mines.edu

2015-06-15

Graphical abstract: - Highlights: • Three NTR reactors are optimized for the single stage launch of 1–15 MT payloads. • The proposed rocket engines have specific impulses in excess of 700 s. • Reactivity and submersion criticality requirements are satisfied for each reactor. - Abstract: Recent advances in the development of high power density fuel materials have renewed interest in nuclear thermal rockets (NTRs) as a viable propulsion technology for future space exploration. This paper describes the design of three NTR reactor engines designed for the single stage to orbit launch of payloads from 1 to 15 metric tons. Thermal hydraulic and rocket engine analyses indicate that the proposed rocket engines are able to reach specific impulses in excess of 800 s. Neutronics analyses performed using MCNP5 demonstrate that the hot excess reactivity, shutdown margin, and submersion criticality requirements are satisfied for each NTR reactor. The reactors each consist of a 40 cm diameter core packed with hexagonal tungsten cermet fuel elements. The core is surrounded by radial and axial beryllium reflectors and eight boron carbide control drums. The 40 cm long reactor meets the submersion criticality requirements (a shutdown margin of at least $1 subcritical in all submersion scenarios) with no further modifications. The 80 and 120 cm long reactors include small amounts of gadolinium nitride as a spectral shift absorber to keep them subcritical upon submersion in seawater or wet sand following a launch abort.

Design and analysis of a single stage to orbit nuclear thermal rocket reactor engine

International Nuclear Information System (INIS)

Labib, Satira; King, Jeffrey

2015-01-01

Graphical abstract: - Highlights: • Three NTR reactors are optimized for the single stage launch of 1–15 MT payloads. • The proposed rocket engines have specific impulses in excess of 700 s. • Reactivity and submersion criticality requirements are satisfied for each reactor. - Abstract: Recent advances in the development of high power density fuel materials have renewed interest in nuclear thermal rockets (NTRs) as a viable propulsion technology for future space exploration. This paper describes the design of three NTR reactor engines designed for the single stage to orbit launch of payloads from 1 to 15 metric tons. Thermal hydraulic and rocket engine analyses indicate that the proposed rocket engines are able to reach specific impulses in excess of 800 s. Neutronics analyses performed using MCNP5 demonstrate that the hot excess reactivity, shutdown margin, and submersion criticality requirements are satisfied for each NTR reactor. The reactors each consist of a 40 cm diameter core packed with hexagonal tungsten cermet fuel elements. The core is surrounded by radial and axial beryllium reflectors and eight boron carbide control drums. The 40 cm long reactor meets the submersion criticality requirements (a shutdown margin of at least $1 subcritical in all submersion scenarios) with no further modifications. The 80 and 120 cm long reactors include small amounts of gadolinium nitride as a spectral shift absorber to keep them subcritical upon submersion in seawater or wet sand following a launch abort

Nuclear thermal rocket engine operation and control

International Nuclear Information System (INIS)

Gunn, S.V.; Savoie, M.T.; Hundal, R.

1993-06-01

The operation of a typical Rover/Nerva-derived nuclear thermal rocket (NTR) engine is characterized and the control requirements of the NTR are defined. A rationale for the selection of a candidate diverse redundant NTR engine control system is presented and the projected component operating requirements are related to the state of the art of candidate components and subsystems. The projected operational capabilities of the candidate system are delineated for the startup, full-thrust, shutdown, and decay heat removal phases of the engine operation. 9 refs

JPRS Report, Nuclear Developments

National Research Council Canada - National Science Library

1991-01-01

Partial Contents: Medium Range Missiles, Rocket Engine, Nuclear Submarine, Nuclear Reactor, Nuclear Inspection, Nuclear Weapons, Transfer Technology, Scud, Safety, Nuclear Power, Chernobyl Trial, ,CHemical Weapons...

Nuclear-powered rocket of the future

Energy Technology Data Exchange (ETDEWEB)

Yunqiao, B

1979-06-01

A possible manned mission to Mars with a crew of 7 in an 80-meter-long nuclear-powered rocket will take 180 days to reach its destination, will spend 10 to 14 days on the surface, and will take 200 days to return. A nuclear-powered engine (using U-235 or U-239) is the most likely means of propulsion. Four designs are described. The superheated exhaust engine will use a reactor to heat liquid hydrogen to over 4000/sup 0/C, after which it will be ejected from the exhaust. A plasma compression engine will use electric current produced by a reactor to heat hydrogen to plasma temperature (70,000/sup 0/C), after which it will be ejected through the exhaust by a magnetic field. In a gaseous-core reactor engine, gaseous fuel will heat liquid hydrogen to over 9,000/sup 0/C and use it as the propellant. The boldest solution is a proposal to use small nuclear explosions as the propulsive force. The first alternative will probably not produce enough thrust, while there will be a difficulty producing sufficient electricity in the second alternative. The other two alternatives seem promising.

Turbopump options for nuclear thermal rockets

International Nuclear Information System (INIS)

Bissell, W.R.; Gunn, S.V.

1992-07-01

Several turbopump options for delivering liquid nitrogen to nuclear thermal rocket (NTR) engines were evaluated and compared. Axial and centrifugal flow pumps were optimized, with and without boost pumps, utilizing current design criteria within the latest turbopump technology limits. Two possible NTR design points were used, a modest pump pressure rise of 1,743 psia and a relatively higher pump pressure rise of 4,480 psia. Both engines utilized the expander cycle to maximize engine performance for the long duration mission. Pump suction performance was evaluated. Turbopumps with conventional cavitating inducers were compared with zero NPSH (saturated liquid in the tanks) pumps over a range of tank saturation pressures, with and without boost pumps. Results indicate that zero NSPH pumps at high tank vapor pressures, 60 psia, are very similar to those with the finite NPSHs. At low vapor pressures efficiencies fall and turbine pressure ratios increase leading to decreased engine chamber pressures and or increased pump pressure discharges and attendant high-pressure component weights. It may be concluded that zero tank NSPH capabilities can be obtained with little penalty to the engine systems but boost pumps are needed if tank vapor pressure drops below 30 psia. Axial pumps have slight advantages in weight and chamber pressure capability while centrifugal pumps have a greater operating range. 10 refs

Nuclear Thermal Rocket/Vehicle Design Options for Future NASA Missions to the Moon and Mars

Science.gov (United States)

Borowski, Stanley K.; Corban, Robert R.; Mcguire, Melissa L.; Beke, Erik G.

1995-01-01

The nuclear thermal rocket (NTR) provides a unique propulsion capability to planners/designers of future human exploration missions to the Moon and Mars. In addition to its high specific impulse (approximately 850-1000 s) and engine thrust-to-weight ratio (approximately 3-10), the NTR can also be configured as a 'dual mode' system capable of generating electrical power for spacecraft environmental systems, communications, and enhanced stage operations (e.g., refrigeration for long-term liquid hydrogen storage). At present the Nuclear Propulsion Office (NPO) is examining a variety of mission applications for the NTR ranging from an expendable, single-burn, trans-lunar injection (TLI) stage for NASA's First Lunar Outpost (FLO) mission to all propulsive, multiburn, NTR-powered spacecraft supporting a 'split cargo-piloted sprint' Mars mission architecture. Each application results in a particular set of requirements in areas such as the number of engines and their respective thrust levels, restart capability, fuel operating temperature and lifetime, cryofluid storage, and stage size. Two solid core NTR concepts are examined -- one based on NERVA (Nuclear Engine for Rocket Vehicle Application) derivative reactor (NDR) technology, and a second concept which utilizes a ternary carbide 'twisted ribbon' fuel form developed by the Commonwealth of Independent States (CIS). The NDR and CIS concepts have an established technology database involving significant nuclear testing at or near representative operating conditions. Integrated systems and mission studies indicate that clusters of two to four 15 to 25 klbf NDR or CIS engines are sufficient for most of the lunar and Mars mission scenarios currently under consideration. This paper provides descriptions and performance characteristics for the NDR and CIS concepts, summarizes NASA's First Lunar Outpost and Mars mission scenarios, and describes characteristics for representative cargo and piloted vehicles compatible with a

Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

International Nuclear Information System (INIS)

Hicks, H.G.

1981-11-01

This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines

Research Technology (ASTP) Rocket Based Combined Cycle (RBCC) Engine

Science.gov (United States)

2004-01-01

Pictured is an artist's concept of the Rocket Based Combined Cycle (RBCC) launch. The RBCC's overall objective is to provide a technology test bed to investigate critical technologies associated with opperational usage of these engines. The program will focus on near term technologies that can be leveraged to ultimately serve as the near term basis for Two Stage to Orbit (TSTO) air breathing propulsions systems and ultimately a Single Stage To Orbit (SSTO) air breathing propulsion system.

Development of the nuclear technology in Latvia in the second half of 20 century

International Nuclear Information System (INIS)

Gavars, V.; Tomsons, E.

2004-01-01

In the second part of 20th century Latvia that was at that time a part of the Soviet Union, one of the nuclear power world powers, participated in the development of nuclear technology. Already in the 60ies the local specialists created an original nuclear equipment highly recognized by specialists from different countries. The most important of them was critical assembly (zero power nuclear reactor) - RKS, large-scale gamma rays source - RK-LM, special control devices for space-rocket nuclear reactors and a renovated research nuclear reactor IRT-M with thermo power of 5MW, etc.(authors)

Design, qualification and operation of nuclear rockets for safe Mars missions

International Nuclear Information System (INIS)

Buden, D.; Madsen, W.W.; Olson, T.S.; Redd, L.R.

1993-01-01

Nuclear thermal propulsion modules planned for use on crew missions to Mars improve mission reliability and overall safety of the mission. This, as well as all other systems, are greatly enhanced if the system specifications take into account safety from design initiation, and operational considerations are well thought through and applied. For instance, the use of multiple engines in the propulsion module can lead to very high system safety and reliability. Operational safety enhancements may include: the use of multiple perigee burns, thus allowing time to ensure that all systems are functioning properly prior to departure from Earth orbit; the ability to perform all other parts of the mission in a degraded mode with little or no degradation of the mission; and the safe disposal of the nuclear propulsion module in a heliocentric orbit out of the ecliptic plane. The standards used to qualify nuclear rockets are one of the main cost drivers of the program. Concepts and systems that minimize cost and risk will rely on use of the element and component levels to demonstrate technology readiness and validation. Subsystem or systems testing then is only needed for verification of performance. Also, these will be the safest concepts because they will be more thoroughly understood and the safety margins will be well established and confirmed by tests

Nuclear Propulsion through Direct Conversion of Fusion Energy: The Fusion Driven Rocket

Science.gov (United States)

Slough, John; Pancotti, Anthony; Kirtley, David; Pihl, Christopher; Pfaff, Michael

2012-01-01

The future of manned space exploration and development of space depends critically on the creation of a dramatically more proficient propulsion architecture for in-space transportation. A very persuasive reason for investigating the applicability of nuclear power in rockets is the vast energy density gain of nuclear fuel when compared to chemical combustion energy. Current nuclear fusion efforts have focused on the generation of electric grid power and are wholly inappropriate for space transportation as the application of a reactor based fusion-electric system creates a colossal mass and heat rejection problem for space application.

An example of successful international cooperation in rocket motor technology

Science.gov (United States)

Ellis, Russell A.; Berdoyes, Michel

2002-07-01

The history of over 25 years of cooperation between Pratt & Whitney, San Jose, CA, USA and Snecma Moteurs, Le Haillan, France in solid rocket motor and, in one case, liquid rocket engine technology is presented. Cooperative efforts resulted in achievements that likely would not have been realized individually. The combination of resources and technologies resulted in synergistic benefits and advancement of the state of the art in rocket motors and components. Discussions begun between the two companies in the early 1970's led to the first cooperative project, demonstration of an advanced apogee motor nozzle, during the mid 1970's. Shortly thereafter advanced carboncarbon (CC) throat materials from Snecma were comparatively tested with other materials in a P&W program funded by the USAF. Use of Snecma throat materials in CSD Tomahawk boosters followed. Advanced space motors were jointly demonstrated in company-funded joint programs in the late 1970's and early 1980's: an advanced space motor with an extendible exit cone and an all-composite advanced space motor that included a composite chamber polar adapter. Eight integral-throat entrances (ITEs) of 4D and 6D construction were tested by P&W for Snecma in 1982. Other joint programs in the 1980's included test firing of a "membrane" CC exit cone, and integral throat and exit cone (ITEC) nozzle incorporating NOVOLTEX® SEPCARB® material. A variation of this same material was demonstrated as a chamber aft polar boss in motor firings that included demonstration of composite material hot gas valve thrust vector control (TVC). In the 1990's a supersonic splitline flexseal nozzle was successfully demonstrated by the two companies as part of a US Integrated High Payoff Rocket Propulsion Technology (IHPRPT) program effort. Also in the mid-1990s the NOVOLTEX® SEPCARB® material, so successful in solid rocket motor application, was successfully applied to a liquid engine nozzle extension. The first cooperative

Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

Energy Technology Data Exchange (ETDEWEB)

Friesen, H.N.

1995-06-01

Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

Thermohydraulic modeling of nuclear thermal rockets: The KLAXON code

International Nuclear Information System (INIS)

Hall, M.L.; Rider, W.J.; Cappiello, M.W.

1992-01-01

The hydrogen flow from the storage tanks, through the reactor core, and out the nozzle of a Nuclear Thermal Rocket is an integral design consideration. To provide an analysis and design tool for this phenomenon, the KLAXON code is being developed. A shock-capturing numerical methodology is used to model the gas flow (the Harten, Lax, and van Leer method, as implemented by Einfeldt). Preliminary results of modeling the flow through the reactor core and nozzle are given in this paper

Yes--This is Rocket Science: MMCs for Liquid Rocket Engines

National Research Council Canada - National Science Library

Shelley, J

2001-01-01

The Air Force's Integrated High-Payoff Rocket Propulsion Technologies (IHPRPT) Program has established aggressive goals for both improved performance and reduced cost of rocket engines and components...

Low Cost Nuclear Thermal Rocket Cermet Fuel Element Environment Testing

Science.gov (United States)

Bradley, David E.; Mireles, Omar R.; Hickman, Robert R.

2011-01-01

Deep space missions with large payloads require high specific impulse (Isp) and relatively high thrust in order to achieve mission goals in reasonable time frames. Conventional, storable propellants produce average Isp. Nuclear thermal rockets (NTR) capable of high Isp thrust have been proposed. NTR employs heat produced by fission reaction to heat and therefore accelerate hydrogen which is then forced through a rocket nozzle providing thrust. Fuel element temperatures are very high (up to 3000K) and hydrogen is highly reactive with most materials at high temperatures. Data covering the effects of high temperature hydrogen exposure on fuel elements is limited. The primary concern is the mechanical failure of fuel elements which employ high-melting-point metals, ceramics or a combination (cermet) as a structural matrix into which the nuclear fuel is distributed. It is not necessary to include fissile material in test samples intended to explore high temperature hydrogen exposure of the structural support matrices. A small-scale test bed designed to heat fuel element samples via non-contact RF heating and expose samples to hydrogen is being developed to assist in optimal material and manufacturing process selection without employing fissile material. This paper details the test bed design and results of testing conducted to date.

Particle bed reactor nuclear rocket concept

International Nuclear Information System (INIS)

Ludewig, H.

1991-01-01

The particle bed reactor nuclear rocket concept consists of fuel particles (in this case (U,Zr)C with an outer coat of zirconium carbide). These particles are packed in an annular bed surrounded by two frits (porous tubes) forming a fuel element; the outer one being a cold frit, the inner one being a hot frit. The fuel element are cooled by hydrogen passing in through the moderator. These elements are assembled in a reactor assembly in a hexagonal pattern. The reactor can be either reflected or not, depending on the design, and either 19 or 37 elements, are used. Propellant enters in the top, passes through the moderator fuel element and out through the nozzle. Beryllium used for the moderator in this particular design to withstand the high radiation exposure implied by the long run times

An historical collection of papers on nuclear thermal propulsion

Science.gov (United States)

The present volume of historical papers on nuclear thermal propulsion (NTP) encompasses NTP technology development regarding solid-core NTP technology, advanced concepts from the early years of NTP research, and recent activities in the field. Specific issues addressed include NERVA rocket-engine technology, the development of nuclear rocket propulsion at Los Alamos, fuel-element development, reactor testing for the Rover program, and an overview of NTP concepts and research emphasizing two decades of NASA research. Also addressed are the development of the 'nuclear light bulb' closed-cycle gas core and a demonstration of a fissioning UF6 gas in an argon vortex. The recent developments reviewed include the application of NTP to NASA's Lunar Space Transportation System, the use of NTP for the Space Exploration Initiative, and the development of nuclear rocket engines in the former Soviet Union.

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

International Nuclear Information System (INIS)

Michael Kruzic

2007-01-01

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D and D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release

An improved heat transfer configuration for a solid-core nuclear thermal rocket engine

International Nuclear Information System (INIS)

Clark, J.S.; Walton, J.T.; Mcguire, M.L.

1992-07-01

Interrupted flow, impingement cooling, and axial power distribution are employed to enhance the heat-transfer configuration of a solid-core nuclear thermal rocket engine. Impingement cooling is introduced to increase the local heat-transfer coefficients between the reactor material and the coolants. Increased fuel loading is used at the inlet end of the reactor to enhance heat-transfer capability where the temperature differences are the greatest. A thermal-hydraulics computer program for an unfueled NERVA reactor core is employed to analyze the proposed configuration with attention given to uniform fuel loading, number of channels through the impingement wafers, fuel-element length, mass-flow rate, and wafer gap. The impingement wafer concept (IWC) is shown to have heat-transfer characteristics that are better than those of the NERVA-derived reactor at 2500 K. The IWC concept is argued to be an effective heat-transfer configuration for solid-core nuclear thermal rocket engines. 11 refs

Conceptual Engine System Design for NERVA derived 66.7KN and 111.2KN Thrust Nuclear Thermal Rockets

International Nuclear Information System (INIS)

Fittje, James E.; Buehrle, Robert J.

2006-01-01

The Nuclear Thermal Rocket concept is being evaluated as an advanced propulsion concept for missions to the moon and Mars. A tremendous effort was undertaken during the 1960's and 1970's to develop and test NERVA derived Nuclear Thermal Rockets in the 111.2 KN to 1112 KN pound thrust class. NASA GRC is leveraging this past NTR investment in their vehicle concepts and mission analysis studies, and has been evaluating NERVA derived engines in the 66.7 KN to the 111.2 KN thrust range. The liquid hydrogen propellant feed system, including the turbopumps, is an essential component of the overall operation of this system. The NASA GRC team is evaluating numerous propellant feed system designs with both single and twin turbopumps. The Nuclear Engine System Simulation code is being exercised to analyze thermodynamic cycle points for these selected concepts. This paper will present propellant feed system concepts and the corresponding thermodynamic cycle points for 66.7 KN and 111.2 KN thrust NTR engine systems. A pump out condition for a twin turbopump concept will also be evaluated, and the NESS code will be assessed against the Small Nuclear Rocket Engine preliminary thermodynamic data

Nuclear thermal rocket propulsion application to Mars missions

International Nuclear Information System (INIS)

Emrich, W.J. Jr.; Young, A.C.; Mulqueen, J.A.

1991-01-01

Options for vehicle configurations are reviewed in which nuclear thermal rocket (NTR) propulsion is used for a reference mission to Mars. The scenario assumes an opposition-class Mars transfer trajectory, a 435-day mission, and the use of a single nuclear engine with 75,000 lbs of thrust. Engine parameters are examined by calculating mission variables for a range of specific impulses and thrust/weight ratios. The reference mission is found to have optimal values of 925 s for the specific impulse and thrust/weight ratios of 4.0 and 0.06 for the engine and total stage ratios respectively. When the engine thrust/weight ratio is at least 4/1 the most critical engine parameter is engine specific impulse for reducing overall stage weight. In the context of this trans-Mars three-burn maneuver the NTR engine with an expander engine cycle is considered a more effective alternative than chemical/aerobrake and other propulsion options

Nuclear thermal rockets using indigenous extraterrestrial propellants

International Nuclear Information System (INIS)

Zubrin, R.M.

1990-01-01

A preliminary examination of a concept for a Mars and outer solar system exploratory vehicle is presented. Propulsion is provided by utilizing a nuclear thermal reactor to heat a propellant volatile indigenous to the destination world to form a high thrust rocket exhaust. Candidate propellants, whose performance, materials compatibility, and ease of acquisition are examined and include carbon dioxide, water, methane, nitrogen, carbon monoxide, and argon. Ballistics and winged supersonic configurations are discussed. It is shown that the use of this method of propulsion potentially offers high payoff to a manned Mars mission. This is accomplished by sharply reducing the initial mission mass required in low earth orbit, and by providing Mars explorers with greatly enhanced mobility in traveling about the planet through the use of a vehicle that can refuel itself each time it lands. Thus, the nuclear landing craft is utilized in combination with a hydrogen-fueled nuclear-thermal interplanetary launch. By utilizing such a system in the outer solar system, a low level aerial reconnaissance of Titan combined with a multiple sample return from nearly every satellite of Saturn can be accomplished in a single launch of a Titan 4 or the Space Transportation System (STS). Similarly a multiple sample return from Callisto, Ganymede, and Europa can also be accomplished in one launch of a Titan 4 or the STS

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

International Nuclear Information System (INIS)

Michael R. Kruzic

2007-01-01

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D and D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D and D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D and D strategy is now being employed on the larger ''sister'' facility, Test Cell C

Nuclear propulsion for the space exploration initiative

International Nuclear Information System (INIS)

Stanley, M.L.

1991-01-01

President Bush's speech of July 20, 1989, outlining a goal to go back to the moon and then Mars initiated the Space Exploration Initiative (SEI). The US Department of Defense (DOD), US Department of Energy (DOE), and NASA have been working together in the planning necessary to initiate a program to develop a nuclear propulsion system. Applications of nuclear technology for in-space transfer of personnel and cargo between Earth orbit and lunar or Martian orbit are being considered as alternatives to chemical propulsion systems. Mission and system concept studies conducted over the past 30 yr have consistently indicated that use of nuclear technology can substantially reduce in-space propellant requirements. A variety of nuclear technology options are currently being studied, including nuclear thermal rockets, nuclear electrical propulsion systems, and hybrid nuclear thermal rockets/nuclear electric propulsion concepts. Concept performance in terms of thrust, weight, power, and efficiency are dependent, and appropriate concept application is mission dependent (i.e., lunar, Mars, cargo, personnel, trajectory, transit time, payload). A comprehensive evaluation of mission application, technology performance capability and maturity, technology development programmatics, and safety characteristics is required to optimize both technology and mission selection to support the Presidential initiative

Initial risk assessment for a single stage to orbit nuclear thermal rocket

Energy Technology Data Exchange (ETDEWEB)

Labib, Satira, E-mail: Satira.Labib@duke-energy.com; King, Jeffrey, E-mail: kingjc@mines.edu

2015-06-15

Highlights: • The risks posed by the surface launch of a nuclear thermal rocket are considered. • Radiation exposure at the public viewing distance is insignificant. • Production of fission products and actinides during launch is limited. • The production of activated argon around the rocket may be a significant concern. - Abstract: In order to consider the possibility of a nuclear thermal rocket (NTR) ground launch, it is necessary to evaluate the risks from such a launch. This includes analysis of the radiation dose rate around the rocket, determining the rate of activation of the materials near the launch, and considering the radionuclides present in the core after the launch. This paper evaluates the potential risk of the NTR ground launch for a range of payloads from 1 to 15 metric tons (MT) using three NTR reactor cores (40, 80, and 120 cm in length) designed in a previous study, based on data produced by MCNP5 and MCNPX models. At the same power level, the 40 cm core length reactor results in the lowest radiation dose rate of the three reactors. Radiation dose rates decrease to background levels 3.5 km from the launch site. After a 1-year decay time, all of the activated materials produced by an NTR launch would be classified as Class A low-level waste. The activation of air produces significant amounts of argon-41 and nitrogen-16 within 100 m of the launch. The derived air concentration (DAC) ratio of the activation products decays to less than unity within 2 days, with only argon-41 remaining. After 10 min of full power operation, the 120 cm core for a 15 MT payload contains 2.5 × 10{sup 13}, 1.4 × 10{sup 12} and 1.5 × 10{sup 12} Bq of {sup 131}I, {sup 137}Cs, and {sup 90}Sr, respectively. The decay heat after shutdown increases with increasing reactor power with a maximum decay heat of 108 kW immediately after shutdown for the 15 MT payload.

Analysis of plume backflow around a nozzle lip in a nuclear rocket

International Nuclear Information System (INIS)

Chung, C.H.; Kim, S.C.; Stubbs, R.M.; De Witt, K.J.

1993-06-01

The structure of the flow around a nuclear thermal rocket nozzle lip has been investigated using the direct simulation Monte Carlo method. Special attention has been paid to the behavior of a small amount of harmful particles that may be present in the rocket exhaust gas. The harmful fission product particles are modeled by four inert gases whose molecular weights are in a range of 4 131. Atomic hydrogen, which exists in the flow due to the extremely high nuclear fuel temperature in the reactor, is also included. It is shown that the plume backflow is primarily determined by the thin subsonic fluid layer adjacent to the surface of the nozzle lip, and that the inflow boundary in the plume region has negligible effect on the backflow. It is also shown that a relatively large amount of the lighter species is scattered into the backflow region while the amount of the heavier species becomes negligible in this region due to extreme separation between the species. Results indicate that the backscattered molecules are very energetic and are fast-moving along the surface in the backflow region near the nozzle lip. 22 refs

Nuclear Propulsion and Power Non-Nuclear Test Facility (NP2NTF): Preliminary Analysis and Feasibility Assessment

Data.gov (United States)

National Aeronautics and Space Administration — Nuclear thermal propulsion (NTP) has been identified as a high NASA technology priority area by the National Research Council because nuclear thermal rockets (NTRs)...

Rocket propulsion elements - An introduction to the engineering of rockets (6th revised and enlarged edition)

Science.gov (United States)

Sutton, George P.

The subject of rocket propulsion is treated with emphasis on the basic technology, performance, and design rationale. Attention is given to definitions and fundamentals, nozzle theory and thermodynamic relations, heat transfer, flight performance, chemical rocket propellant performance analysis, and liquid propellant rocket engine fundamentals. The discussion also covers solid propellant rocket fundamentals, hybrid propellant rockets, thrust vector control, selection of rocket propulsion systems, electric propulsion, and rocket testing.

On fundamentally new sources of energy for rockets in the early works of the pioneers of astronautics

Science.gov (United States)

Melkumov, T. M.

1977-01-01

The research for more efficient methods of propelling a spacecraft, than can be achieved with chemical energy, was studied. During a time when rockets for space flight had not actually been built pioneers in rocket technology were already concerned with this problem. Alternative sources proposed at that time, were nuclear and solar energy. Basic engineering problems of each source were investigated.

Pellet bed reactor for nuclear propelled vehicles: Part 1: Reactor technology

Science.gov (United States)

El-Genk, Mohamed S.

1991-01-01

The pellet bed reactor (PBR) for nuclear propelled vehicles is briefly discussed. Much of the information is given in viewgraph form. Viewgraphs include information on the layout for a Mars mission using a PBR nuclear thermal rocket, the rocket reactor layout, the fuel pellet design, materials compatibility, fuel microspheres, microsphere coating, melting points in quasibinary systems, stress analysis of microspheres, safety features, and advantages of the PBR concept.

Pellet bed reactor for nuclear propelled vehicles: Part 1: Reactor technology

International Nuclear Information System (INIS)

El-genk, M.S.

1991-01-01

The pellet bed reactor (PBR) for nuclear propelled vehicles is briefly discussed. Much of the information is given in viewgraph form. Viewgraphs include information on the layout for a Mars mission using a PBR nuclear thermal rocket, the rocket reactor layout, the fuel pellet design, materials compatibility, fuel microspheres, microsphere coating, melting points in quasibinary systems, stress analysis of microspheres, safety features, and advantages of the PBR concept

Rockets: An Educator's Guide with Activities in Science, Mathematics, and Technology.

Science.gov (United States)

National Aeronautics and Space Administration, Washington, DC.

This educational guide discusses rockets and includes activities in science, mathematics, and technology. It begins with background information on the history of rocketry, scientific principles, and practical rocketry. The sections on scientific principles and practical rocketry focus on Sir Isaac Newton's Three Laws of Motion. These laws explain…

Nuclear Thermal Rocket (NTR) Development Risk Communication

Science.gov (United States)

Kim, Tony

2014-01-01

There are clear advantages of development of a Nuclear Thermal Rocket (NTR) for a crewed mission to Mars. NTR for in-space propulsion enables more ambitious space missions by providing high thrust at high specific impulse (approximately 900 sec) that is 2 times the best theoretical performance possible for chemical rockets. Missions can be optimized for maximum payload capability to take more payload with reduced total mass to orbit; saving cost on reduction of the number of launch vehicles needed. Or missions can be optimized to minimize trip time significantly to reduce the deep space radiation exposure to the crew. NTR propulsion technology is a game changer for space exploration. However, "NUCLEAR" is a word that is feared and vilified by some groups and the hostility towards development of any nuclear systems can meet great opposition by the public as well as from national leaders and people in authority. Communication of nuclear safety will be critical to the success of the development of the NTR. Why is there a fear of nuclear? A bomb that can level a city is a scary weapon. The first and only times the Nuclear Bomb was used in a war was on Hiroshima and Nagasaki during World War 2. The "Little Boy" atomic bomb was dropped on Hiroshima on August 6, 1945 and the "Fat Man" on Nagasaki 3 days later on August 9th. Within the first 4 months of bombings, 90- 166 thousand people died in Hiroshima and 60-80 thousand died in Nagasaki. It is important to note for comparison that over 500 thousand people died and 5 million made homeless due to strategic bombing (approximately 150 thousand tons) of Japanese cities and war assets with conventional non-nuclear weapons between 1942- 1945. A major bombing campaign of "firebombing" of Tokyo called "Operation Meetinghouse" on March 9 and 10 consisting of 334 B-29's dropped approximately1,700 tons of bombs around 16 square mile area and over 100 thousand people have been estimated to have died. The declaration of death is very

Technology Development of a Fiber Optic-Coupled Laser Ignition System for Multi-Combustor Rocket Engines

Science.gov (United States)

Trinh, Huu P.; Early, Jim; Osborne, Robin; Thomas, Matthew E.; Bossard, John A.

2002-01-01

This paper addresses the progress of technology development of a laser ignition system at NASA Marshall Space Flight Center (MSFC). The first two years of the project focus on comprehensive assessments and evaluations of a novel dual-pulse laser concept, flight- qualified laser system, and the technology required to integrate the laser ignition system to a rocket chamber. With collaborations of the Department of Energy/Los Alamos National Laboratory (LANL) and CFD Research Corporation (CFDRC), MSFC has conducted 26 hot fire ignition tests with lab-scale laser systems. These tests demonstrate the concept feasibility of dual-pulse laser ignition to initiate gaseous oxygen (GOX)/liquid kerosene (RP-1) combustion in a rocket chamber. Presently, a fiber optic- coupled miniaturized laser ignition prototype is being implemented at the rocket chamber test rig for future testing. Future work is guided by a technology road map that outlines the work required for maturing a laser ignition system. This road map defines activities for the next six years, with the goal of developing a flight-ready laser ignition system.

Affordable Development and Demonstration of a Small Nuclear Thermal Rocket (NTR) Engine and Stage: How Small Is Big Enough?

Science.gov (United States)

Borowski, Stanley K.; Sefcik, Robert J.; Fittje, James E.; McCurdy, David R.; Qualls, Arthur L.; Schnitzler, Bruce G.; Werner, James E.; Weitzberg, Abraham; Joyner, Claude R.

2016-01-01

The Nuclear Thermal Rocket (NTR) derives its energy from fission of uranium-235 atoms contained within fuel elements that comprise the engine's reactor core. It generates high thrust and has a specific impulse potential of approximately 900 specific impulse - a 100 percent increase over today's best chemical rockets. The Nuclear Thermal Propulsion (NTP) project, funded by NASA's Advanced Exploration Systems (AES) program, includes five key task activities: (1) Recapture, demonstration, and validation of heritage graphite composite (GC) fuel (selected as the Lead Fuel option); (2) Engine Conceptual Design; (3) Operating Requirements Definition; (4) Identification of Affordable Options for Ground Testing; and (5) Formulation of an Affordable Development Strategy. During fiscal year (FY) 2014, a preliminary Design Development Test and Evaluation (DDT&E) plan and schedule for NTP development was outlined by the NASA Glenn Research Center (GRC), Department of Energy (DOE) and industry that involved significant system-level demonstration projects that included Ground Technology Demonstration (GTD) tests at the Nevada National Security Site (NNSS), followed by a Flight Technology Demonstration (FTD) mission. To reduce cost for the GTD tests and FTD mission, small NTR engines, in either the 7.5 or 16.5 kilopound-force thrust class, were considered. Both engine options used GC fuel and a common fuel element (FE) design. The small approximately 7.5 kilopound-force criticality-limited engine produces approximately157 thermal megawatts and its core is configured with parallel rows of hexagonal-shaped FEs and tie tubes (TTs) with a FE to TT ratio of approximately 1:1. The larger approximately 16.5 kilopound-force Small Nuclear Rocket Engine (SNRE), developed by Los Alamos National Laboratory (LANL) at the end of the Rover program, produces approximately 367 thermal megawatts and has a FE to TT ratio of approximately 2:1. Although both engines use a common 35-inch (approximately

From A-4 to Explorer 1. [U.S. rocket and missile technology historical review

Science.gov (United States)

Debus, K. H.

1973-01-01

Historical review of the development of rocket and missile technology in the United States over the period from 1945 to 1958. Attention is given to the organization of activities, the launch facilities, and the scope of test rocket firings at the White Sands Proving Ground area during the initial phase of research with captured German V2 rockets. The development of the Redstone missiles is outlined by discussing aspects of military involvement, cooperation with industrial suppliers, details of ground support equipment, and results of initial test firings. Subsequent development of the Jupiter missiles is examined in a similar manner, and attention is given to activities involved in the launching of the Explorer 1 satellite.

A computational model for thermal fluid design analysis of nuclear thermal rockets

International Nuclear Information System (INIS)

Given, J.A.; Anghaie, S.

1997-01-01

A computational model for simulation and design analysis of nuclear thermal propulsion systems has been developed. The model simulates a full-topping expander cycle engine system and the thermofluid dynamics of the core coolant flow, accounting for the real gas properties of the hydrogen propellant/coolant throughout the system. Core thermofluid studies reveal that near-wall heat transfer models currently available may not be applicable to conditions encountered within some nuclear rocket cores. Additionally, the possibility of a core thermal fluid instability at low mass fluxes and the effects of the core power distribution are investigated. Results indicate that for tubular core coolant channels, thermal fluid instability is not an issue within the possible range of operating conditions in these systems. Findings also show the advantages of having a nonflat centrally peaking axial core power profile from a fluid dynamic standpoint. The effects of rocket operating conditions on system performance are also investigated. Results show that high temperature and low pressure operation is limited by core structural considerations, while low temperature and high pressure operation is limited by system performance constraints. The utility of these programs for finding these operational limits, optimum operating conditions, and thermal fluid effects is demonstrated

Modeling Transients and Designing a Passive Safety System for a Nuclear Thermal Rocket Using Relap5

Science.gov (United States)

Khatry, Jivan

Long-term high payload missions necessitate the need for nuclear space propulsion. Several nuclear reactor types were investigated by the Nuclear Engine for Rocket Vehicle Application (NERVA) program of National Aeronautics and Space Administration (NASA). Study of planned/unplanned transients on nuclear thermal rockets is important due to the need for long-term missions. A NERVA design known as the Pewee I was selected for this purpose. The following transients were run: (i) modeling of corrosion-induced blockages on the peripheral fuel element coolant channels and their impact on radiation heat transfer in the core, and (ii) modeling of loss-of-flow-accidents (LOFAs) and their impact on radiation heat transfer in the core. For part (i), the radiation heat transfer rate of blocked channels increases while their neighbors' decreases. For part (ii), the core radiation heat transfer rate increases while the flow rate through the rocket system is decreased. However, the radiation heat transfer decreased while there was a complete LOFA. In this situation, the peripheral fuel element coolant channels handle the majority of the radiation heat transfer. Recognizing the LOFA as the most severe design basis accident, a passive safety system was designed in order to respond to such a transient. This design utilizes the already existing tie rod tubes and connects them to a radiator in a closed loop. Hence, this is basically a secondary loop. The size of the core is unchanged. During normal steady-state operation, this secondary loop keeps the moderator cool. Results show that the safety system is able to remove the decay heat and prevent the fuel elements from melting, in response to a LOFA and subsequent SCRAM.

Program ELM: A tool for rapid thermal-hydraulic analysis of solid-core nuclear rocket fuel elements

International Nuclear Information System (INIS)

Walton, J.T.

1992-11-01

This report reviews the state of the art of thermal-hydraulic analysis codes and presents a new code, Program ELM, for analysis of fuel elements. ELM is a concise computational tool for modeling the steady-state thermal-hydraulics of propellant flow through fuel element coolant channels in a nuclear thermal rocket reactor with axial coolant passages. The program was developed as a tool to swiftly evaluate various heat transfer coefficient and friction factor correlations generated for turbulent pipe flow with heat addition which have been used in previous programs. Thus, a consistent comparison of these correlations was performed, as well as a comparison with data from the NRX reactor experiments from the Nuclear Engine for Rocket Vehicle Applications (NERVA) project. This report describes the ELM Program algorithm, input/output, and validation efforts and provides a listing of the code

Thirteenth Workshop for Computational Fluid Dynamic Applications in Rocket Propulsion and Launch Vehicle Technology. Volume 2

Science.gov (United States)

Williams, R. W. (Compiler)

1996-01-01

This conference publication includes various abstracts and presentations given at the 13th Workshop for Computational Fluid Dynamic Applications in Rocket Propulsion and Launch Vehicle Technology held at the George C. Marshall Space Flight Center April 25-27 1995. The purpose of the workshop was to discuss experimental and computational fluid dynamic activities in rocket propulsion and launch vehicles. The workshop was an open meeting for government, industry, and academia. A broad number of topics were discussed including computational fluid dynamic methodology, liquid and solid rocket propulsion, turbomachinery, combustion, heat transfer, and grid generation.

Engineering thermal engine rocket adventurer for space nuclear application

International Nuclear Information System (INIS)

Nam, Seung H.; Suh, Kune Y.; Kang, Seong G.

2008-01-01

The conceptual design for the first-of-a-kind engineering of Thermal Engine Rocket Adventure (TERA) is described. TERA comprising the Battery Omnibus Reactor Integral System (BORIS) as the heat resource and the Space Propulsion Reactor Integral System (SPRIS) as the propulsion system, is one of the advanced Nuclear Thermal Rocket (NTR) engine utilizing hydrogen (H 2 ) propellant being developed at present time. BORIS in this application is an open cycle high temperature gas cooled reactor that has eighteen fuel elements for propulsion and one fuel element for electricity generation and propellant pumping. Each fuel element for propulsion has its own small nozzle. The nineteen fuel elements are arranged into hexagonal prism shape in the core and surrounded by outer Be reflector. The TERA maximum power is 1,000 MW th , specific impulse 1,000 s, thrust 250,000 N, and the total mass is 550 kg including the reactor, turbo pump and auxiliaries. Each fuel element comprises the fuel assembly, moderators, pressure tube and small nozzle. The TERA fuel assembly is fabricated of 93% enriched 1.5 mm (U, Zr, Nb)C wafers in 25.3% voided Square Lattice Honeycomb (SLHC). The H 2 propellant passes through these flow channels. This study is concerned with thermohydrodynamic analysis of the fuel element for propulsion with hypothetical axial power distribution because nuclear analysis of TERA has not been performed yet. As a result, when the power distribution of INSPI's M-SLHC is applied to the fuel assembly, the local heat concentration of fuel is more serious and the pressure of the initial inlet H 2 is higher than those of constant average power distribution applied. This means the fuel assembly geometry of 1.5 mm fuel wafers and 25.3% voided SLHC needs to be changed in order to reduce thermal and mechanical shocks. (author)

Review of coaxial flow gas core nuclear rocket fluid mechanics

International Nuclear Information System (INIS)

Weinstein, H.

1976-01-01

In a prematurely aborted attempt to demonstrate the feasibility of using a gas core nuclear reactor as a rocket engine, NASA initiated a number of studies on the relevant fluid mechanics problems. These studies were carried out at NASA laboratories, universities and industrial research laboratories. Because of the relatively sudden termination of most of this work, a unified overview was never presented which demonstrated the accomplishments of the program and pointed out the areas where additional work was required for a full understanding of the cavity flow. This review attempts to fulfill a part of this need in two important areas

INVESTIGATION OF MARKETING TECHNOLOGIES IN THE INNOVATION PROCESS OF ROCKET AND SPACE INDUSTRY

Directory of Open Access Journals (Sweden)

K. B. Dobrova

2016-01-01

Full Text Available In this article we have studied the use of marketing technologies in the innovation process of enterprises of rocket and space industry. The present study specifies the relevance of chosen research topic, as well as the essence of marketing innovations at the enterprises of rocket and space industry, the structuring of marketing and management processes in the innovation process. There are provided the most common analytical instruments in the marketing and there is marked the importance of use of a global strategy for the enterprises of rocket and space industry. The article also specifies a clear example of application of marketing technologies in the innovation process of the Federal State Unitary Enterprise "State Space Research and Production Center named after Khrunichev M.V'.'. At the beginning the role and place of innovation management and innovation process in the strategic management of the FSUE "SSRPC named after Khrunichev M.V." are shown. Then there are described the basic marketing methods of program-oriented management of the innovation process in the FSUE "SSRPC named after Khrunichev M.V"" and there is highlighted the innovation marketing strategy of the FSUE "SSRPC named after Khrunichev M.V.". There are presented the distinctive features of the competitive strategy of the company of the rocket and space industry and the features of formation (development of the innovative enterprise development strategy based on marketing innovation in the FSUE "SSRPC named after Khrunichev M.V.". The conclusion includes the main findings of the study conducted.

History of Solid Rockets

Science.gov (United States)

Green, Rebecca

2017-01-01

Solid rockets are of interest to the space program because they are commonly used as boosters that provide the additional thrust needed for the space launch vehicle to escape the gravitational pull of the Earth. Larger, more advanced solid rockets allow for space launch vehicles with larger payload capacities, enabling mankind to reach new depths of space. This presentation will discuss, in detail, the history of solid rockets. The history begins with the invention and origin of the solid rocket, and then goes into the early uses and design of the solid rocket. The evolution of solid rockets is depicted by a description of how solid rockets changed and improved and how they were used throughout the 16th, 17th, 18th, and 19th centuries. Modern uses of the solid rocket include the Solid Rocket Boosters (SRBs) on the Space Shuttle and the solid rockets used on current space launch vehicles. The functions and design of the SRB and the advancements in solid rocket technology since the use of the SRB are discussed as well. Common failure modes and design difficulties are discussed as well.

Launch Vehicles Based on Advanced Hybrid Rocket Motors: An Enabling Technology for the Commercial Small and Micro Satellite Planetary Science

Science.gov (United States)

Karabeyoglu, Arif; Tuncer, Onur; Inalhan, Gokhan

2016-07-01

Mankind is relient on chemical propulsion systems for space access. Nevertheless, this has been a stagnant area in terms of technological development and the technology base has not changed much almost for the past forty years. This poses a vicious circle for launch applications such that high launch costs constrain the demand and low launch freqencies drive costs higher. This also has been a key limiting factor for small and micro satellites that are geared towards planetary science. Rather this be because of the launch frequencies or the costs, the access of small and micro satellites to orbit has been limited. With today's technology it is not possible to escape this circle. However the emergence of cost effective and high performance propulsion systems such as advanced hybrid rockets can decrease launch costs by almost an order or magnitude. This paper briefly introduces the timeline and research challenges that were overcome during the development of advanced hybrid LOX/paraffin based rockets. Experimental studies demonstrated effectiveness of these advanced hybrid rockets which incorporate fast burning parafin based fuels, advanced yet simple internal balistic design and carbon composite winding/fuel casting technology that enables the rocket motor to be built from inside out. A feasibility scenario is studied using these rocket motors as building blocks for a modular launch vehicle capable of delivering micro satellites into low earth orbit. In addition, the building block rocket motor can be used further solar system missions providing the ability to do standalone small and micro satellite missions to planets within the solar system. This enabling technology therefore offers a viable alternative in order to escape the viscous that has plagued the space launch industry and that has limited the small and micro satellite delivery for planetary science.

Nuclear thermal rocket clustering: 1, A summary of previous work and relevant issues

International Nuclear Information System (INIS)

Buksa, J.J.; Houts, M.G.

1991-01-01

A general review of the technical merits of nuclear thermal rocket clustering is presented. A summary of previous analyses performed during the Rover program is presented and used to assess clustering in the context of projected Space Exploration Initiative missions. A number of technical issues are discussed including cluster reliability, engine-out operation, neutronic coupling, shutdown core power generation, shutdown reactivity requirements, reactor kinetics, and radiation shielding. 7 refs., 3 figs., 2 tabs

Nuclear power in space

International Nuclear Information System (INIS)

Anghaie, S.

2007-01-01

The development of space nuclear power and propulsion in the United States started in 1955 with the initiation of the ROVER project. The first step in the ROVER program was the KIWI project that included the development and testing of 8 non-flyable ultrahigh temperature nuclear test reactors during 1955-1964. The KIWI project was precursor to the PHOEBUS carbon-based fuel reactor project that resulted in ground testing of three high power reactors during 1965-1968 with the last reactor operated at 4,100 MW. During the same time period a parallel program was pursued to develop a nuclear thermal rocket based on cermet fuel technology. The third component of the ROVER program was the Nuclear Engine for Rocket Vehicle Applications (NERVA) that was initiated in 1961 with the primary goal of designing the first generation of nuclear rocket engine based on the KIWI project experience. The fourth component of the ROVER program was the Reactor In-Flight Test (RIFT) project that was intended to design, fabricate, and flight test a NERVA powered upper stage engine for the Saturn-class lunch vehicle. During the ROVER program era, the Unites States ventured in a comprehensive space nuclear program that included design and testing of several compact reactors and space suitable power conversion systems, and the development of a few light weight heat rejection systems. Contrary to its sister ROVER program, the space nuclear power program resulted in the first ever deployment and in-space operation of the nuclear powered SNAP-10A in 1965. The USSR space nuclear program started in early 70's and resulted in deployment of two 6 kWe TOPAZ reactors into space and ground testing of the prototype of a relatively small nuclear rocket engine in 1984. The US ambition for the development and deployment of space nuclear powered systems was resurrected in mid 1980's and intermittently continued to date with the initiation of several research programs that included the SP-100, Space Exploration

Focused RBCC Experiments: Two-Rocket Configuration Experiments and Hydrocarbon/Oxygen Rocket Ejector Experiments

Science.gov (United States)

Santoro, Robert J.; Pal, Sibtosh

2003-01-01

This addendum report documents the results of two additional efforts for the Rocket Based Combined Cycle (RBCC) rocket-ejector mode research work carried out at the Penn State Propulsion Engineering Research Center in support of NASA s technology development efforts for enabling 3 d generation Reusable Launch Vehicles (RLV). The tasks reported here build on an earlier NASA MSFC funded research program on rocket ejector investigations. The first task investigated the improvements of a gaseous hydrogen/oxygen twin thruster RBCC rocket ejector system over a single rocket system. The second task investigated the performance of a hydrocarbon (liquid JP-7)/gaseous oxygen single thruster rocket-ejector system. To gain a systematic understanding of the rocket-ejector s internal fluid mechanic/combustion phenomena, experiments were conducted with both direct-connect and sea-level static diffusion and afterburning (DAB) configurations for a range of rocket operating conditions. For all experimental conditions, overall system performance was obtained through global measurements of wall static pressure profiles, heat flux profiles and engine thrust. Detailed mixing and combustion information was obtained through Raman spectroscopy measurements of major species (gaseous oxygen, hydrogen, nitrogen and water vapor) for the gaseous hydrogen/oxygen rocket ejector experiments.

Conventional and Bimodal Nuclear Thermal Rocket (NTR) Artificial Gravity Mars Transfer Vehicle Concepts

Science.gov (United States)

Borowski, Stanley K.; McCurdy, David R.; Packard, Thomas W.

2016-01-01

A variety of countermeasures have been developed to address the debilitating physiological effects of zero-gravity (0-g) experienced by cosmonauts and astronauts during their approximately 0.5 to 1.2 year long stays in low Earth orbit (LEO). Longer interplanetary flights, combined with possible prolonged stays in Mars orbit, could subject crewmembers to up to approximately 2.5 years of weightlessness. In view of known and recently diagnosed problems associated with 0-g, an artificial gravity (AG) spacecraft offers many advantages and may indeed be an enabling technology for human flights to Mars. A number of important human factors must be taken into account in selecting the rotation radius, rotation rate, and orientation of the habitation module or modules. These factors include the gravity gradient effect, radial and tangential Coriolis forces, along with cross-coupled acceleration effects. Artificial gravity Mars transfer vehicle (MTV) concepts are presented that utilize both conventional NTR, as well as, enhanced bimodal nuclear thermal rocket (BNTR) propulsion. The NTR is a proven technology that generates high thrust and has a specific impulse (Isp) capability of approximately 900 s-twice that of today's best chemical rockets. The AG/MTV concepts using conventional Nuclear Thermal Propulsion (NTP) carry twin cylindrical International Space Station (ISS)- type habitation modules with their long axes oriented either perpendicular or parallel to the longitudinal spin axis of the MTV and utilize photovoltaic arrays (PVAs) for spacecraft power. The twin habitat modules are connected to a central operations hub located at the front of the MTV via two pressurized tunnels that provide the rotation radius for the habitat modules. For the BNTR AG/MTV option, each engine has its own closed secondary helium(He)-xenon (Xe) gas loop and Brayton Rotating Unit (BRU) that can generate 10s of kilowatts (kWe) of spacecraft electrical power during the mission coast phase

SEI nuclear technology findings by the Stafford Synthesis Group

International Nuclear Information System (INIS)

Buden, D.

1991-01-01

Nuclear propulsion is key to reducing travel time to Mars, greatly reducing the mass in low Earth orbit, and enhancing schedule flexibility by increasing the Earth orbit departure launch window. Nuclear thermal rockets have twice to three times the performance of the best chemical rockets. This directly translates into reduced trip times and lower mass in low Earth orbit. Trip times of < 400 days in space are possible, a limitation if restricted to chemical propulsion. Psychological, physiological and radiological problems are significant issues for long mission times. The psychology of being cooped up so long in a minimum-sized capsule is cause for concern - much longer than considered healthy for nuclear submarine crews. The effects of long-term weightlessness are being debated. Short trip times eliminate the need for artificial gravity. The largest uncertainty is the effect of galactic radiation that will expose the crew to high levels of radiation for as much as 60 rem/yr

China's space development history: A comparison of the rocket and satellite sectors

Science.gov (United States)

Erickson, Andrew S.

2014-10-01

China is the most recent great power to emerge in aerospace. It has become the first developing nation to achieve some measure of aerospace production capability across the board. Outside the developed aerospace powers, only China has demonstrated competence concerning all aspects of a world-class aerospace industry: production of advanced rockets, satellites, and aircraft and of their supporting engineering, materials, and systems. As an emerging great power during the Cold War, China was still limited in resources, technology access, and capabilities. It thereby faced difficult choices and constraints. Yet it achieved increasing, though uneven, technological levels in different aerospace sub-sectors. Explaining this variance can elucidate challenges and opportunities confronting developing nations sharing limitations that previously constrained China. Rockets (missiles and space launch vehicles/SLVs) and satellites (military and civilian) were two areas of early achievement for China, and represent this article's two in-depth case studies. Initial import of American and Soviet knowledge and technology, coupled with national resources focused under centralized leadership, enabled China to master missiles and satellites ahead of other systems. Early in the Cold War, great power status hinged on atomic development. China devoted much of its limited technical resources to producing nuclear weapons in order to “prevent nuclear blackmail,” “break the superpowers' monopoly,” and thereby secure great power status. Beijing's second strategic priority was to develop reliable ballistic missiles to credibly deliver warheads, thereby supporting nuclear deterrence. Under Chairman Mao Zedong's direction and the guidance of the American-educated Dr. Qian Xuesen (H.S. Tsien), missile development became China's top aerospace priority. Satellites were also prioritized for military-strategic reasons and because they could not be purchased from abroad following the Sino

Technology for Transient Simulation of Vibration during Combustion Process in Rocket Thruster

Science.gov (United States)

Zubanov, V. M.; Stepanov, D. V.; Shabliy, L. S.

2018-01-01

The article describes the technology for simulation of transient combustion processes in the rocket thruster for determination of vibration frequency occurs during combustion. The engine operates on gaseous propellant: oxygen and hydrogen. Combustion simulation was performed using the ANSYS CFX software. Three reaction mechanisms for the stationary mode were considered and described in detail. The way for obtaining quick CFD-results with intermediate combustion components using an EDM model was found. The way to generate the Flamelet library with CFX-RIF was described. A technique for modeling transient combustion processes in the rocket thruster was proposed based on the Flamelet library. A cyclic irregularity of the temperature field like vortex core precession was detected in the chamber. Frequency of flame precession was obtained with the proposed simulation technique.

Nuclear technology and societal needs

International Nuclear Information System (INIS)

2004-11-01

This volume aims to review the present status of development of nuclear technologies and their applications in the country and also to make projections for future requirements. This will also cover state-of-the-art technologies in these areas. The following topics are covered in detail: nuclear technologies for water desalination, water resources development and management using nuclear technology, industrial applications of isotopes and radiation technology, radiation technology in health care, nuclear technology for food preservation, agricultural applications of nuclear technology. Papers relevant to INIS are indexed separately

Liquid Rocket Engine Testing Overview

Science.gov (United States)

Rahman, Shamim

2005-01-01

Contents include the following: Objectives and motivation for testing. Technology, Research and Development Test and Evaluation (RDT&E), evolutionary. Representative Liquid Rocket Engine (LRE) test compaigns. Apollo, shuttle, Expandable Launch Vehicles (ELV) propulsion. Overview of test facilities for liquid rocket engines. Boost, upper stage (sea-level and altitude). Statistics (historical) of Liquid Rocket Engine Testing. LOX/LH, LOX/RP, other development. Test project enablers: engineering tools, operations, processes, infrastructure.

Energy production using fission fragment rockets

International Nuclear Information System (INIS)

Chapline, G.; Matsuda, Y.

1991-08-01

Fission fragment rockets are nuclear reactors with a core consisting of thin fibers in a vacuum, and which use magnetic fields to extract the fission fragments from the reactor core. As an alternative to ordinary nuclear reactors, fission fragment rockets would have the following advantages: Approximately twice as efficient if one can directly convert the fission fragment energy into electricity; by reducing the buildup of a fission fragment inventory in the reactor one could avoid a Chernobyl type disaster; and collecting the fission fragments outside the reactor could simplify the waste disposal problem. 6 refs., 4 figs., 2 tabs

Nuclear thermal propulsion workshop overview

International Nuclear Information System (INIS)

Clark, J.S.

1991-01-01

NASA is planning an Exploration Technology Program as part of the Space Exploration Initiative to return U.S. astronauts to the moon, conduct intensive robotic exploration of the moon and Mars, and to conduct a piloted mission to Mars by 2019. Nuclear Propulsion is one of the key technology thrust for the human mission to Mars. The workshop addresses NTP (Nuclear Thermal Rocket) technologies with purpose to: assess the state-of-the-art of nuclear propulsion concepts; assess the potential benefits of the concepts for the mission to Mars; identify critical, enabling technologies; lay-out (first order) technology development plans including facility requirements; and estimate the cost of developing these technologies to flight-ready status. The output from the workshop will serve as a data base for nuclear propulsion project planning

Development of small solid rocket boosters for the ILR-33 sounding rocket

Science.gov (United States)

Nowakowski, Pawel; Okninski, Adam; Pakosz, Michal; Cieslinski, Dawid; Bartkowiak, Bartosz; Wolanski, Piotr

2017-09-01

This paper gives an overview of the development of a 6000 Newton-class solid rocket motor for suborbital applications. The design configuration and results of interior ballistics calculations are given. The initial use of the motor as the main propulsion system of the H1 experimental in-flight test platform, within the Polish Small Sounding Rocket Program, is presented. Comparisons of theoretical and experimental performance are shown. Both on-ground and in-flight tests are discussed. A novel composite-case manufacturing technology, which enabled to reach high propellant mass fractions, was validated and significant cost-reductions were achieved. This paper focuses on the process of adapting the design for use as the booster stage of the ILR-33 sounding rocket, under development at the Institute of Aviation in Warsaw, Poland. Parallel use of two of the flight-proven rocket motors along with the main stage is planned. The process of adapting the rocket motor for booster application consists of stage integration, aerothermodynamics and reliability analyses. The separation mechanism and environmental impact are also discussed within this paper. Detailed performance analysis with focus on propellant grain geometry is provided. The evolution of the design since the first flights of the H1 rocket is covered and modifications of the manufacturing process are described. Issues of simultaneous ignition of two motors and their non-identical performance are discussed. Further applications and potential for future development are outlined. The presented results are based on the initial work done by the Rocketry Group of the Warsaw University of Technology Students' Space Association. The continuation of the Polish Small Sounding Rocket Program on a larger scale at the Institute of Aviation proves the value of the outcomes of the initial educational project.

The international nuclear technology

International Nuclear Information System (INIS)

Remick, F.J.

1992-01-01

With today's technology, isolationism is virtually impossible. The world's economies are so strongly intertwined that what affects one country will, in some way, influence another. Nuclear technology is no exception. If anything, nuclear technology is a catalyst for international cooperation. In the United States of America, nuclear technology is undergoing significant changes. Many of these changes are being greatly influenced by programs of international cooperation

Bimodal Nuclear Thermal Rocket Analysis Developments

Science.gov (United States)

Belair, Michael; Lavelle, Thomas; Saimento, Charles; Juhasz, Albert; Stewart, Mark

2014-01-01

Nuclear thermal propulsion has long been considered an enabling technology for human missions to Mars and beyond. One concept of operations for these missions utilizes the nuclear reactor to generate electrical power during coast phases, known as bimodal operation. This presentation focuses on the systems modeling and analysis efforts for a NERVA derived concept. The NERVA bimodal operation derives the thermal energy from the core tie tube elements. Recent analysis has shown potential temperature distributions in the tie tube elements that may limit the thermodynamic efficiency of the closed Brayton cycle used to generate electricity with the current design. The results of this analysis are discussed as well as the potential implications to a bimodal NERVA type reactor.

Development and analysis of startup strategies for particle bed nuclear rocket engine

Science.gov (United States)

Suzuki, David E.

1993-06-01

The particle bed reactor (PBR) nuclear thermal propulsion rocket engine concept is the focus of the Air Force's Space Nuclear Thermal Propulsion program. While much progress has been made in developing the concept, several technical issues remain. Perhaps foremost among these concerns is the issue of flow stability through the porous, heated bed of fuel particles. There are two complementary technical issues associated with this concern: the identification of the flow stability boundary and the design of the engine controller to maintain stable operation. This thesis examines a portion of the latter issue which has yet to be addressed in detail. Specifically, it develops and analyzes general engine system startup strategies which maintain stable flow through the PBR fuel elements while reaching the design conditions as quickly as possible. The PBR engine studies are conducted using a computer model of a representative particle bed reactor and engine system. The computer program utilized is an augmented version of SAFSIM, an existing nuclear thermal propulsion modeling code; the augmentation, dubbed SAFSIM+, was developed by the author and provides a more complete engine system modeling tool.

Nuclear Propulsion for Space (Rev.)

Energy Technology Data Exchange (ETDEWEB)

Corliss, William R; Schwenk, Francis C

1971-01-01

The operation of nuclear rockets and a description of the development of nuclear rockets in the U.S. is given. Early developments and Project Rover, Project Pluto, and the NERVA (Nuclear Engine for Rocket Vehicle Application) Program are detailed. The Nuclear Rocket Development Station facilities in Nevada are described. The possibilities and advantages of using nuclear rockets for missions beginning from an earth orbit and moving outward toward higher earth orbits, the moon, and the planets are discussed.

Nuclear technology is dead - long live nuclear technology

International Nuclear Information System (INIS)

Mayer, G.

1976-01-01

While a group of German scientists asked for a moratorium for nuclear power plants in the Heidelberg memorandum, lecturers at the Reaktortagung in Duesseldorf offered convincing arguments in favour of nuclear technology and for the necessity of safety. Almost 2,000 participants, about 200 of those from 26 different countries, listened to 235 individual lectures on the state of science and technology. Main topics were activities in reactor safety research carried out in industry and in various institutes. (orig./RW) [de

Nuclear Waste Disposal in Space: BEP's Best Hope?

International Nuclear Information System (INIS)

Coopersmith, Jonathan

2006-01-01

The best technology is worthless if it cannot find a market Beam energy propulsion (BEP) is a very promising technology, but faces major competition from less capable but fully developed conventional rockets. Rockets can easily handle projected markets for payloads into space. Without a new, huge demand for launch capability, BEP is unlikely to gain the resources it needs for development and application. Launching tens of thousands of tons of nuclear waste into space for safe and permanent disposal will provide that necessary demand while solving a major problem on earth. Several options exist to dispose of nuclear waste, including solar orbit, lunar orbit, soft lunar landing, launching outside the solar system, and launching into the sun

Nuclear technologies

International Nuclear Information System (INIS)

Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

2010-01-01

In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

Hybrid rocket motor testing at Nammo Raufoss A/S

Science.gov (United States)

Rønningen, Jan-Erik; Kubberud, Nils

2005-08-01

Hybrid rocket motor technology and the use of hybrid rockets have gained increased interest in recent years in many countries. A typical hybrid rocket consists of a tank containing the oxidizer in either liquid or gaseous state connected to the combustion chamber containing an injector, inert solid fuel grain and nozzle. Nammo Raufoss A/S has for almost 40 years designed and produced high-performance solid propellant rocket motors for many military missile systems as well as solid propellant rocket motors for civil space use. In 2003 an in-house technology program was initiated to investigate and study hybrid rocket technology. On 23 September 2004 the first in-house designed hybrid test rocket motor was static test fired at Nammo Raufoss Test Center. The oxidizer was gaseous oxygen contained in a tank pressurized to 10MPa, flow controlled through a sonic orifice into the combustion chamber containing a multi port radial injector and six bore cartridge-loaded fuel grain containing a modified HTPB fuel composition. The motor was ignited using a non-explosive heated wire. This paper will present what has been achieved at Nammo Raufoss since the start of the program.

National Nuclear Technology Map Development

International Nuclear Information System (INIS)

Shin, J. I.; Lee, T. J.; Yoon, S. W.

2005-03-01

The objective of NuTRM is to prepare a plan of nuclear R and D and technological innovations which is very likely to make nuclear technology a promising power source for future national developments. The NuTRM finds out systematically the nuclear R and D vision and the high-value-added strategic technologies to be developed by the efficient cooperation of actors including government, industry, academy and research institute by 2020. In other words, NuTRM aims at a long-term strategic planning of nuclear R and D and technological innovation in order to promote the socio-economic contributions of nuclear science and technology for the nation's future competitiveness and sustainable development and to raise the global status of the Korean nuclear R and D and Industry

Reexamining the Ethics of Nuclear Technology.

Science.gov (United States)

Andrianov, Andrei; Kanke, Victor; Kuptsov, Ilya; Murogov, Viktor

2015-08-01

This article analyzes the present status, development trends, and problems in the ethics of nuclear technology in light of a possible revision of its conceptual foundations. First, to better recognize the current state of nuclear technology ethics and related problems, this article focuses on presenting a picture of the evolution of the concepts and recent achievements related to technoethics, based on the ethics of responsibility. The term 'ethics of nuclear technology' describes a multidisciplinary endeavor to examine the problems associated with nuclear technology through ethical frameworks and paradigms. Second, to identify the reasons for the intensification of efforts to develop ethics in relation to nuclear technology, this article presents an analysis of the recent situation and future prospects of nuclear technology deployment. This includes contradictions that have aggravated nuclear dilemmas and debates stimulated by the shortcomings of nuclear technology, as well as the need for the further development of a nuclear culture paradigm that is able to provide a conceptual framework to overcome nuclear challenges. Third, efforts in the field of nuclear technology ethics are presented as a short overview of particular examples, and the major findings regarding obstacles to the development of nuclear technology ethics are also summarized. Finally, a potential methodological course is proposed to overcome inaction in this field; the proposed course provides for the further development of nuclear technology ethics, assuming the axiological multidisciplinary problematization of the main concepts in nuclear engineering through the basic ethical paradigms: analytical, hermeneutical, and poststructuralist.

Non-nuclear power application of nuclear technology in Nigeria

International Nuclear Information System (INIS)

Funtua, I.I.

2008-01-01

Nuclear Technology applications are found in Food and Agriculture, Human Health, Water Resources, Industry, Environment, Education and Research.There are more potentials for the deployment of nuclear technology in more aspects of our life with needed economic development in Nigeria.Nuclear Technology plays and would continue to play vital role in Agriculture, Human health, Water resources and industry in Nigeria.Nuclear technologies have been useful in developmental efforts worldwide and for these to take hold, capacity building programmes must be expanded and the general public must have informed opinions about the benefits and risk associated with the technologies.This presentation gives an overview of nuclear technology applications in Nigeria in the following areas: Food and Agriculture, Human Health, Water Resources, Industry, Education and Research

Nuclear thermal rocket plume interactions with spacecraft. Final report

International Nuclear Information System (INIS)

Mauk, B.H.; Gatsonis, N.A.; Buzby, J.; Yin, X.

1997-01-01

This is the first study that has treated the Nuclear Thermal Rocket (NTR) effluent problem in its entirety, beginning with the reactor core, through the nozzle flow, to the plume backflow. The summary of major accomplishments is given below: (1) Determined the NTR effluents that include neutral, ionized and radioactive species, under typical NTR chamber conditions. Applied an NTR chamber chemistry model that includes conditions and used nozzle geometries and chamber conditions typical of NTR configurations. (2) Performed NTR nozzle flow simulations using a Navier-Stokes solver. We assumed frozen chemistry at the chamber conditions and used nozzle geometries and chamber conditions typical of NTR configurations. (3) Performed plume simulations using a Direct Simulation Monte Carlo (DSMC) code with chemistry. In order to account for radioactive trace species that may be important for contamination purposes we developed a multi-weighted DSMC methodology. The domain in our simulations included large regions downstream and upstream of the exit. Inputs were taken from the Navier-Stokes solutions

Robust Exploration and Commercial Missions to the Moon Using Nuclear Thermal Rocket Propulsion and Lunar Liquid Oxygen Derived from FeO-Rich Pyroclasitc Deposits

Science.gov (United States)

Borowski, Stanley K.; Ryan, Stephen W.; Burke, Laura M.; McCurdy, David R.; Fittje, James E.; Joyner, Claude R.

2018-01-01

The nuclear thermal rocket (NTR) has frequently been identified as a key space asset required for the human exploration of Mars. This proven technology can also provide the affordable access through cislunar space necessary for commercial development and sustained human presence on the Moon. It is a demonstrated technology capable of generating both high thrust and high specific impulse (I(sub sp) approx. 900 s) twice that of today's best chemical rockets. Nuclear lunar transfer vehicles-consisting of a propulsion stage using three approx. 16.5-klb(sub f) small nuclear rocket engines (SNREs), an in-line propellant tank, plus the payload-are reusable, enabling a variety of lunar missions. These include cargo delivery and crewed lunar landing missions. Even weeklong ''tourism'' missions carrying passengers into lunar orbit for a day of sightseeing and picture taking are possible. The NTR can play an important role in the next phase of lunar exploration and development by providing a robust in-space lunar transportation system (LTS) that can allow initial outposts to evolve into settlements supported by a variety of commercial activities such as in-situ propellant production used to supply strategically located propellant depots and transportation nodes. The use of lunar liquid oxygen (LLO2) derived from iron oxide (FeO)-rich volcanic glass beads, found in numerous pyroclastic deposits on the Moon, can significantly reduce the launch mass requirements from Earth by enabling reusable, surface-based lunar landing vehicles (LLVs)that use liquid oxygen and hydrogen (LO2/LH2) chemical rocket engines. Afterwards, a LO2/LH2 propellant depot can be established in lunar equatorial orbit to supply the LTS. At this point a modified version of the conventional NTR-called the LO2-augmented NTR, or LANTR-is introduced into the LTS allowing bipropellant operation and leveraging the mission benefits of refueling with lunar-derived propellants for Earth return. The bipropellant LANTR

Using Innovative Technologies for Manufacturing and Evaluating Rocket Engine Hardware

Science.gov (United States)

Betts, Erin M.; Hardin, Andy

2011-01-01

Many of the manufacturing and evaluation techniques that are currently used for rocket engine component production are traditional methods that have been proven through years of experience and historical precedence. As we enter into a new space age where new launch vehicles are being designed and propulsion systems are being improved upon, it is sometimes necessary to adopt new and innovative techniques for manufacturing and evaluating hardware. With a heavy emphasis on cost reduction and improvements in manufacturing time, manufacturing techniques such as Direct Metal Laser Sintering (DMLS) and white light scanning are being adopted and evaluated for their use on J-2X, with hopes of employing both technologies on a wide variety of future projects. DMLS has the potential to significantly reduce the processing time and cost of engine hardware, while achieving desirable material properties by using a layered powdered metal manufacturing process in order to produce complex part geometries. The white light technique is a non-invasive method that can be used to inspect for geometric feature alignment. Both the DMLS manufacturing method and the white light scanning technique have proven to be viable options for manufacturing and evaluating rocket engine hardware, and further development and use of these techniques is recommended.

Technology Roadmaps: Nuclear Energy

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This nuclear energy roadmap has been prepared jointly by the IEA and the OECD Nuclear Energy Agency (NEA). Unlike most other low-carbon energy sources, nuclear energy is a mature technology that has been in use for more than 50 years. The latest designs for nuclear power plants build on this experience to offer enhanced safety and performance, and are ready for wider deployment over the next few years. Several countries are reactivating dormant nuclear programmes, while others are considering nuclear for the first time. China in particular is already embarking on a rapid nuclear expansion. In the longer term, there is great potential for new developments in nuclear energy technology to enhance nuclear's role in a sustainable energy future.

A Study on Nuclear Technology Policy

International Nuclear Information System (INIS)

Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik; Lee, J. H.

2006-02-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply

A Study on Nuclear Technology Policy

Energy Technology Data Exchange (ETDEWEB)

Oh, K B; Chung, W S; Lee, T J; Yun, S W; Jeong, Ik; Lee, J H

2006-02-15

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. In the investigation and analysis of international environmental and technological change 1. Viability of Nuclear Renaissance 2. Recent of Nuclear Technology Policy in Japan 3. Collaboration for Advanced Nuclear Technologies in GIF, INPRO and INERI 4. Nuclear Energy Utilization and Development in Europe. In the evaluation of nuclear technology and sustainable development from the point of views of environmental change 5. External Cost of Environmental Impact in Electric Power Sector 6. Nuclear Technology Development Direction Considering Changes of the Science and Technology Policy Environment 7. Nuclear Energy Development Strategy for a Sustainable National Energy Supply.

Nuclear technology and beyond

International Nuclear Information System (INIS)

Akiyama, Mamoru

1997-01-01

After the confrontation of East and West, and the problem of North and South, we are now facing the era of Globalization in the presence of twenty-first century. Tracing the history of civilization, human being has progressed along with the accumulation of experience, and the development of science and technology. Science and technology bloomed in modern ages, especially, energy technology showed the giant leap in this century. Nuclear science and technology has been developed for peaceful purposes, and for the benefit of humanity. As a result, today, its progress led nuclear science and technology to have the great applicability to the development of the society. Toward the twenty-first century and Globalization, the science and technology developed in nuclear field is hoped to play a great contribution in various area of the society. (author)

Initial Operation of the Nuclear Thermal Rocket Element Environmental Simulator

Science.gov (United States)

Emrich, William J., Jr.; Pearson, J. Boise; Schoenfeld, Michael P.

2015-01-01

The Nuclear Thermal Rocket Element Environmental Simulator (NTREES) facility is designed to perform realistic non-nuclear testing of nuclear thermal rocket (NTR) fuel elements and fuel materials. Although the NTREES facility cannot mimic the neutron and gamma environment of an operating NTR, it can simulate the thermal hydraulic environment within an NTR fuel element to provide critical information on material performance and compatibility. The NTREES facility has recently been upgraded such that the power capabilities of the facility have been increased significantly. At its present 1.2 MW power level, more prototypical fuel element temperatures nay now be reached. The new 1.2 MW induction heater consists of three physical units consisting of a transformer, rectifier, and inverter. This multiunit arrangement facilitated increasing the flexibility of the induction heater by more easily allowing variable frequency operation. Frequency ranges between 20 and 60 kHz can accommodated in the new induction heater allowing more representative power distributions to be generated within the test elements. The water cooling system was also upgraded to so as to be capable of removing 100% of the heat generated during testing In this new higher power configuration, NTREES will be capable of testing fuel elements and fuel materials at near-prototypic power densities. As checkout testing progressed and as higher power levels were achieved, several design deficiencies were discovered and fixed. Most of these design deficiencies were related to stray RF energy causing various components to encounter unexpected heating. Copper shielding around these components largely eliminated these problems. Other problems encountered involved unexpected movement in the coil due to electromagnetic forces and electrical arcing between the coil and a dummy test article. The coil movement and arcing which were encountered during the checkout testing effectively destroyed the induction coil in use at

Using Innovative Technologies for Manufacturing Rocket Engine Hardware

Science.gov (United States)

Betts, E. M.; Eddleman, D. E.; Reynolds, D. C.; Hardin, N. A.

2011-01-01

Many of the manufacturing techniques that are currently used for rocket engine component production are traditional methods that have been proven through years of experience and historical precedence. As the United States enters into the next space age where new launch vehicles are being designed and propulsion systems are being improved upon, it is sometimes necessary to adopt innovative techniques for manufacturing hardware. With a heavy emphasis on cost reduction and improvements in manufacturing time, rapid manufacturing techniques such as Direct Metal Laser Sintering (DMLS) are being adopted and evaluated for their use on NASA s Space Launch System (SLS) upper stage engine, J-2X, with hopes of employing this technology on a wide variety of future projects. DMLS has the potential to significantly reduce the processing time and cost of engine hardware, while achieving desirable material properties by using a layered powder metal manufacturing process in order to produce complex part geometries. Marshall Space Flight Center (MSFC) has recently hot-fire tested a J-2X gas generator (GG) discharge duct that was manufactured using DMLS. The duct was inspected and proof tested prior to the hot-fire test. Using a workhorse gas generator (WHGG) test fixture at MSFC's East Test Area, the duct was subjected to extreme J-2X hot gas environments during 7 tests for a total of 537 seconds of hot-fire time. The duct underwent extensive post-test evaluation and showed no signs of degradation. DMLS manufacturing has proven to be a viable option for manufacturing rocket engine hardware, and further development and use of this manufacturing method is recommended.

Introduction to the Special Issue on Sounding Rockets and Instrumentation

OpenAIRE

Christe, Steven; Zeiger, Ben; Pfaff, Rob; Garcia, Michael

2016-01-01

Rocket technology, originally developed for military applications, has provided a low-cost observing platform to carry critical and rapid-response scientific investigations for over 70 years. Even with the development of launch vehicles that could put satellites into orbit, high altitude sounding rockets have remained relevant. In addition to science observations, sounding rockets provide a unique technology test platform and a valuable training ground for scientists and engineers. Most impor...

Kinetic---a system code for analyzing nuclear thermal propulsion rocket engine transients

International Nuclear Information System (INIS)

Schmidt, E.; Lazareth, O.; Ludewig, H.

1993-01-01

A system code suitable for analyzing Nuclear Thermal Propulsion (NTP) rocket engines is described in this paper. The code consists of a point reactor model and nodes to describe the fluid dynamics and heat transfer mechanism. Feedback from the fuel, coolant, moderator and reflector are allowed for, and the control of the reactor is by motion of controls element (drums or rods). The worth of the control element and feedback coefficients are predetermined. Separate models for the turbo-pump assembly (TPA) and nozzle are also included. The model to be described in this paper is specific for the Particle Bed Reactor (PBR). An illustrative problem is solved. This problem consists of a PBR operating in a blowdown mode

Kinetic—a system code for analyzing nuclear thermal propulsion rocket engine transients

Science.gov (United States)

Schmidt, Eldon; Lazareth, Otto; Ludewig, Hans

1993-01-01

A system code suitable for analyzing Nuclear Thermal Propulsion (NTP) rocket engines is described in this paper. The code consists of a point reactor model and nodes to describe the fluid dynamics and heat transfer mechanism. Feedback from the fuel, coolant, moderator and reflector are allowed for, and the control of the reactor is by motion of controls element (drums or rods). The worth of the control element and feedback coefficients are predetermined. Separate models for the turbo-pump assembly (TPA) and nozzle are also included. The model to be described in this paper is specific for the Particle Bed Reactor (PBR). An illustrative problem is solved. This problem consists of a PBR operating in a blowdown mode.

KINETIC: A system code for analyzing Nuclear thermal propulsion rocket engine transients

Science.gov (United States)

Schmidt, E.; Lazareth, O.; Ludewig, H.

1993-07-01

A system code suitable for analyzing Nuclear Thermal Propulsion (NTP) rocket engines is described in this paper. The code consists of a point reactor model and nodes to describe the fluid dynamics and heat transfer mechanism. Feedback from the fuel coolant, moderator and reflector are allowed for, and the control of the reactor is by motion of control elements (drums or rods). The worth of the control clement and feedback coefficients are predetermined. Separate models for the turbo-pump assembly (TPA) and nozzle are also included. The model to be described in this paper is specific for the Particle Bed Reactor (PBR). An illustrative problem is solved. This problem consists of a PBR operating in a blowdown mode.

Nuclear energy technology

Science.gov (United States)

Buden, David

1992-01-01

An overview of space nuclear energy technologies is presented. The development and characteristics of radioisotope thermoelectric generators (RTG's) and space nuclear power reactors are discussed. In addition, the policy and issues related to public safety and the use of nuclear power sources in space are addressed.

Nuclear propulsion tradeoffs for manned Mars missions

International Nuclear Information System (INIS)

Walton, L.A.; Malloy, J.D.

1991-01-01

A conjunction class split/sprint manned Mars exploration mission was studied to evaluate tradeoffs in performance characteristics of nuclear thermal rockets. A Particle Bed Reactor-based nuclear thermal rocket was found to offer a 38% to 52% total mass savings compared with a NERVA-based nuclear thermal rocket for this mission. This advantage is primarily due to the higher thrust-to-weight ratio of the Particle Bed Reactor nuclear rocket. The mission is enabled by nuclear thermal rockets. It cannot be performed practically using chemical propulsion

Hypothetical Dark Matter/axion Rockets:. Dark Matter in Terms of Space Physics Propulsion

Science.gov (United States)

Beckwith, A.

2010-12-01

Current proposed photon rocket designs include the Nuclear Photonic Rocket and the Antimatter Photonic Rocket (proposed by Eugen Sanger in the 1950s, as reported by Ref. 1). This paper examines the feasibility of improving the thrust of photon-driven ramjet propulsion by using DM rocket propulsion. The open question is: would a heavy WIMP, if converted to photons, upgrade the power (thrust) of a photon rocket drive, to make interstellar travel a feasible proposition?

Design methods in solid rocket motors

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

A compilation of lectures summarizing the current state-of-the-art in designing solid rocket motors and and their components is presented. The experience of several countries in the use of new technologies and methods is represented. Specific sessions address propellant grains, cases, nozzles, internal thermal insulation, and the general optimization of solid rocket motor designs.

SSTO rockets. A practical possibility

Science.gov (United States)

Bekey, Ivan

1994-07-01

Most experts agree that single-stage-to-orbit (SSTO) rockets would become feasible if more advanced technologies were available to reduce the vehicle dry weight, increase propulsion system performance, or both. However, these technologies are usually judged to be very ambitious and very far off. This notion persists despite major advances in technology and vehicle design in the past decade. There appears to be four major misperceptions about SSTOs, regarding their mass fraction, their presumed inadequate performance margin, their supposedly small payloads, and their extreme sensitivity to unanticipated vehicle weight growth. These misperceptions can be dispelled for SSTO rockets using advanced technologies that could be matured and demonstrated in the near term. These include a graphite-composite primary structure, graphite-composite and Al-Li propellant tanks with integral reusable thermal protection, long-life tripropellant or LOX-hydrogen engines, and several technologies related to operational effectiveness, including vehicle health monitoring, autonomous avionics/flight control, and operable launch and ground handling systems.

Why nuclear technology

International Nuclear Information System (INIS)

Vieira, Wilson J.; Ishiguro, Yuji; Urbina, Ligia M. Soto

1996-01-01

The importance of nuclear energy in the global society implies the nacional need to give priority and maintain an effective technology policy for nuclear science. In this work, it is considered three points that, although do not represent all the problems in the nuclear sector, were chosen because of their importance and need of change that require: evaluation of the Brazilian scientific policy, which is directed towards the publication in international periodicals, yielding more benefits to the developed countries; evaluation of the few and small investment in laboratories and research institutes, which are the natural producers of technology for the industry and service sectors; evaluation of the lack of concrete of concrete objectives in the universities and research institutes, whose policies are elaborated with-out the due consideration of the collective benefits. It is necessary a national plan for the nuclear are that makes investments in technology development, investments in the laboratories and research institutes, and that makes these universities and research institutes accountable for the success or failure to accomplish the proposed objectives. (author)

Nuclear Thermal Rocket Element Environmental Simulator (NTREES) Upgrade Activities

Science.gov (United States)

Emrich, William J., Jr.

2014-01-01

Over the past year the Nuclear Thermal Rocket Element Environmental Simulator (NTREES) has been undergoing a significant upgrade beyond its initial configuration. The NTREES facility is designed to perform realistic non-nuclear testing of nuclear thermal rocket (NTR) fuel elements and fuel materials. Although the NTREES facility cannot mimic the neutron and gamma environment of an operating NTR, it can simulate the thermal hydraulic environment within an NTR fuel element to provide critical information on material performance and compatibility. The first phase of the upgrade activities which was completed in 2012 in part consisted of an extensive modification to the hydrogen system to permit computer controlled operations outside the building through the use of pneumatically operated variable position valves. This setup also allows the hydrogen flow rate to be increased to over 200 g/sec and reduced the operation complexity of the system. The second stage of modifications to NTREES which has just been completed expands the capabilities of the facility significantly. In particular, the previous 50 kW induction power supply has been replaced with a 1.2 MW unit which should allow more prototypical fuel element temperatures to be reached. The water cooling system was also upgraded to so as to be capable of removing 100% of the heat generated during. This new setup required that the NTREES vessel be raised onto a platform along with most of its associated gas and vent lines. In this arrangement, the induction heater and water systems are now located underneath the platform. In this new configuration, the 1.2 MW NTREES induction heater will be capable of testing fuel elements and fuel materials in flowing hydrogen at pressures up to 1000 psi at temperatures up to and beyond 3000 K and at near-prototypic reactor channel power densities. NTREES is also capable of testing potential fuel elements with a variety of propellants, including hydrogen with additives to inhibit

Introduction to nuclear technology

International Nuclear Information System (INIS)

Goldsmith, M.W.

1985-01-01

In the late 1940s and early 1950s when nuclear technology emerged, there was no oil embargo or any obvious signs of an energy crisis. The driving forces for the rapid development of the atom were its fuel efficiency and its potential cost-effectiveness compared to its alternatives. Uranium was a cheap and abundant domestic fuel and the development of the technology provided new vistas and challenges for the engineering community. It was the goal of providing environmentally clean, abundant, and reasonably priced energy that motivated engineers then as now. Nuclear technology developed under a mixture of government regulation and promotion and utility industry commercialization. This paper discusses the development and implementation of a technology largely resulting from the efforts of government to make the production of nuclear-powered electricity a commercial enterprise. This effort has largely succeeded, as greater than 10% of the electricity generated nationally is now provided by nuclear power

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Lim, C. Y.; Lee, K. S.; Jeong, I.; Lee, J. H.

2009-04-01

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, recent changes of international nuclear energy policy and trends of nuclear technology R and D was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed the trends of nuclear technology policies and (2) discussed the mid and long term strategy of nuclear energy R and D. To put it in more detail, each subject was further explored as follows; (1) analyzed the trends of nuclear technology policies - Trend and prospects of the international and domestic nuclear policies - Investigation of development of small and medium sized policies - International collaboration for advanced nuclear technologies (2) discussed the mid and long term strategy of nuclear energy R and D - The long term development plan for future nuclear energy system - The facilitation of technology commercialization

A Study on the Nuclear Technology Policy

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Lim, C. Y.; Yang, M. H. (and others)

2008-03-15

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI.

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Kim, H. J.; Lim, C. Y.; Yang, M. H.

2008-03-01

The objective of the study was to make policy-proposes for enhancing the effectiveness and efficiency of national nuclear technology development programs. To do this, changes of international nuclear energy policy environment and trends of nuclear technology development was surveyed and analyzed. In the viewpoint of analysis of the changes in the global policy environment surrounding nuclear technology development and development of national nuclear R and D strategy, this study (1) analyzed trends of nuclear technology policies and (2) developed the nuclear energy R and D innovation strategies. To put it in more detail, each subject was further explored as follows; (1) themes to analyze trends of nuclear policies: nuclear Renaissance and forecast for nuclear power plant, International collaboration for advanced nuclear technologies in GIF, INPRO and I-NERI, The present situation and outlook for world uranium market (2) themes to develop of nuclear energy R and D innovation strategies: The mid-term strategy plan of the KAERI, The technological innovation case of the KAERI

Nuclear Technology Programs

International Nuclear Information System (INIS)

Harmon, J.E.

1990-10-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product 99 Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

Nuclear technology programs

International Nuclear Information System (INIS)

Harmon, J.E.

1992-01-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

Nuclear Technology Programs

Energy Technology Data Exchange (ETDEWEB)

Harmon, J.E. (ed.)

1990-10-01

This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

International Nuclear Information System (INIS)

Michael R, Kruzic

2008-01-01

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D and D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

Energy Technology Data Exchange (ETDEWEB)

Michael R. Kruzic

2008-06-01

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

Reducing the risk to Mars: The gas core nuclear rocket

International Nuclear Information System (INIS)

Howe, S.D.; DeVolder, B.; Thode, L.; Zerkle, D.

1998-01-01

The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas-core nuclear rocket (GCNR) has the potential to be such a system. The authors have completed a comparative study of the potential impact that a GCNR could have on a manned Mars mission. The total IMLEO, transit times, and accumulated radiation dose to the crew will be compared with the NASA Design Reference Missions

A unique nuclear thermal rocket engine using a particle bed reactor

Science.gov (United States)

Culver, Donald W.; Dahl, Wayne B.; McIlwain, Melvin C.

1992-01-01

Aerojet Propulsion Division (APD) studied 75-klb thrust Nuclear Thermal Rocket Engines (NTRE) with particle bed reactors (PBR) for application to NASA's manned Mars mission and prepared a conceptual design description of a unique engine that best satisfied mission-defined propulsion requirements and customer criteria. This paper describes the selection of a sprint-type Mars transfer mission and its impact on propulsion system design and operation. It shows how our NTRE concept was developed from this information. The resulting, unusual engine design is short, lightweight, and capable of high specific impulse operation, all factors that decrease Earth to orbit launch costs. Many unusual features of the NTRE are discussed, including nozzle area ratio variation and nozzle closure for closed loop after cooling. Mission performance calculations reveal that other well known engine options do not support this mission.

Nuclear Technology applications

International Nuclear Information System (INIS)

Cibils Machado, W. E- mail: wrcibils@adinet.com.uy

2002-01-01

The present work tries on the applications of the nuclear technology in the life daily, such as agriculture and feeding, human health, industry, non destructive essays, isotopic hydrology, and the nuclear power stations for electricity production and radioisotopes production

Overview of space nuclear technologies and the American Nuclear Society

International Nuclear Information System (INIS)

Singleterry, R.C. Jr.

2000-01-01

The American Nuclear Society (ANS) has seen an aspect of the universe where nuclear technology is the best energy source available for power, transportation, etc. The National Aeronautics and Space Administration (NASA) has been exploiting this aspect of the universe by sending machines and humans into it and exploring, colonizing, industrializing, developing, inhabiting, etc. Space is the final frontier, and nuclear technology is the best suited for today's or the next century's space exploration and development. Many aspects of nuclear technology and its uses in space will be needed. ANS encompasses these and many more aspects of nuclear technology, and all have some role to play in the exploration and development of space. It should be ANS's intent to be an advisory body to NASA on the nuclear aspects of space exploration

Korean experiences on nuclear power technology

International Nuclear Information System (INIS)

Kim, H.; Yang, H.

1994-01-01

This paper describes the outstanding performance of the indigenous development program of nuclear power technology such as the design and fabrication of both CANDU and PWR fuel and in the design and construction of nuclear steam supply system in Korea. The success has been accomplished through the successful technology transfer from foreign suppliers and efficient utilization of R and D manpower in the design and engineering of nuclear power projects. In order to implement the technology transfer successfully, the joint design concept has been introduced along with effective on-the-job training and the transfer of design documents and computer codes. Korea's successful development of nuclear power program has resulted in rapid expansion of nuclear power generation capacity in a short time, and the nuclear power has contributed to the national economy through lowering electricity price by about 50 % as well as stabilizing electricity supply in 1980s. The nuclear power is expected to play a key role in the future electricity supply in Korea. Now Korea is under way of taking a step toward advanced nuclear technology. The national electricity system expansion plan includes 18 more units of NPPs to be constructed by the year 2006. In this circumstance, the country has fixed the national long-term nuclear R and D program (lgg2-2001) to enhance the national capability of nuclear technology. This paper also briefly describes future prospects of nuclear technology development program in Korea

The nuclear option

International Nuclear Information System (INIS)

Herken, G.

1992-01-01

A development history and current status evaluation are presented for nuclear-thermal rocket propulsion systems applicable to interplanetary flight. While the most advanced current chemical rocket engines, such as the SSMEs of the Space Shuttle, produce specific impulses of the order of 450 secs, a nuclear-thermal rocket engine tested at Los Alamos in 1969 generated 845 secs; such specific impulse improvements could represent weeks or months of interplanetary travel time. Attention is given to the achievements of the historical Nuclear Engine for Rocket Vehicle Application, Helios, and Orion design programs, as well as to the current Vehicle for Interplanetary Space Transportation Applications, which is fusion-based

A Study on the Nuclear Technology Policy

International Nuclear Information System (INIS)

Oh, K. B.; Lee, K. S.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, I.; Lee, J. H.

2007-02-01

The objective of the study was to make policy-proposals for enhancing the effectiveness and efficiency of national nuclear technology R and D programs. To do this, environmental changes of international nuclear energy policy and trends of nuclear technology development were surveyed and analyzed. This Study analyzed trends of nuclear technology policies and developed the nuclear energy R and D innovation strategy in a viewpoint of analyzing the changes in the global policy environment associated with nuclear technology development and development of national nuclear R and D strategy

Additive Manufacturing for Affordable Rocket Engines

Science.gov (United States)

West, Brian; Robertson, Elizabeth; Osborne, Robin; Calvert, Marty

2016-01-01

Additive manufacturing (also known as 3D printing) technology has the potential to drastically reduce costs and lead times associated with the development of complex liquid rocket engine systems. NASA is using 3D printing to manufacture rocket engine components including augmented spark igniters, injectors, turbopumps, and valves. NASA is advancing the process to certify these components for flight. Success Story: MSFC has been developing rocket 3D-printing technology using the Selective Laser Melting (SLM) process. Over the last several years, NASA has built and tested several injectors and combustion chambers. Recently, MSFC has 3D printed an augmented spark igniter for potential use the RS-25 engines that will be used on the Space Launch System. The new design is expected to reduce the cost of the igniter by a factor of four. MSFC has also 3D printed and tested a liquid hydrogen turbopump for potential use on an Upper Stage Engine. Additive manufacturing of the turbopump resulted in a 45% part count reduction. To understanding how the 3D printed parts perform and to certify them for flight, MSFC built a breadboard liquid rocket engine using additive manufactured components including injectors, turbomachinery, and valves. The liquid rocket engine was tested seven times in 2016 using liquid oxygen and liquid hydrogen. In addition to exposing the hardware to harsh environments, engineers learned to design for the new manufacturing technique, taking advantage of its capabilities and gaining awareness of its limitations. Benefit: The 3D-printing technology promises reduced cost and schedule for rocket engines. Cost is a function of complexity, and the most complicated features provide the largest opportunities for cost reductions. This is especially true where brazes or welds can be eliminated. The drastic reduction in part count achievable with 3D printing creates a waterfall effect that reduces the number of processes and drawings, decreases the amount of touch

A study on the nuclear technology policy

International Nuclear Information System (INIS)

Kim, H. J.; Oh, K. B.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik

2005-01-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. Acknowledging the importance of the relationship between the external environment and the national nuclear R and D strategic planning for changing of environment of surrounding nuclear technology and development in the world, this study focused on the three major subjects: (1) investigation and analysis of international nuclear environmental and technological change; (2) developing nuclear R and D strategy based on the analysis of national and global environment surrounding nuclear technology development and diffusion; (3) the evaluation of role of nuclear technology and environment from the point of views of environmental effects. In order to enhance the role of national nuclear R and D program and to cope with the environmental and technological change surrounding nuclear energy, it is recommended that active participation should be done in ongoing international collaboration on future innovative nuclear technology for absorption of advanced technologies and strategic R and D planning should be centered on core technology field based on long-term vision and suggested NuTRM considering future energy-environmental surroundings for maximized use of domestic technology capabilities and resources

Pakistan's experience in transfer of nuclear technology

International Nuclear Information System (INIS)

Ahmad Khan, Nunir

1977-01-01

Of all technologies, nuclear technology is perhaps the most interdisciplinary in character as it encompasses such varied fields as nuclear physics, reactor physics, mechanical, electrical electronics controls, metallurgical and even civil and geological engineering. When we speak of transfer of acquisition of nuclear technology we imply cumulative know-how in many fields, most of which are not nuclear per se but are essential for building the necessry infrastructure and back-up facilities for developing and implementing any nuclear energy program. In Pakistan, efforts on utilization of nuclear energy for peaceful applications were initiated about twenty years ago. During these years stepwise development of nuclear technology has taken place. The experience gained by Pakistan so far in transfer of nuclear technology is discussed. Suggestions have been made for continuing the transfer of this most essential technology from the advanced to the developing countries while making sure that necessary safeguard requirements are fullfilled

Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

International Nuclear Information System (INIS)

Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

1992-01-01

Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

Aerodynamics and flow characterisation of multistage rockets

Science.gov (United States)

Srinivas, G.; Prakash, M. V. S.

2017-05-01

The main objective of this paper is to conduct a systematic flow analysis on single, double and multistage rockets using ANSYS software. Today non-air breathing propulsion is increasing dramatically for the enhancement of space exploration. The rocket propulsion is playing vital role in carrying the payload to the destination. Day to day rocket aerodynamic performance and flow characterization analysis has becoming challenging task to the researchers. Taking this task as motivation a systematic literature is conducted to achieve better aerodynamic and flow characterization on various rocket models. The analyses on rocket models are very little especially in numerical side and experimental area. Each rocket stage analysis conducted for different Mach numbers and having different flow varying angle of attacks for finding the critical efficiency performance parameters like pressure, density and velocity. After successful completion of the analysis the research reveals that flow around the rocket body for Mach number 4 and 5 best suitable for designed payload. Another major objective of this paper is to bring best aerodynamics flow characterizations in both aero and mechanical features. This paper also brings feature prospectus of rocket stage technology in the field of aerodynamic design.

Nuclear thermal propulsion engine based on particle bed reactor using light water steam as a propellant

Science.gov (United States)

Powell, James R.; Ludewig, Hans; Maise, George

1993-01-01

In this paper the possibility of configuring a water cooled Nuclear Thermal Propulsion (NTP) rocket, based on a Particle Bed Reactor (PBR) is investigated. This rocket will be used to operate on water obtained from near earth objects. The conclusions reached in this paper indicate that it is possible to configure a PBR based NTP rocket to operate on water and meet the mission requirements envisioned for it. No insurmountable technology issues have been identified.

Nuclear thermal propulsion engine based on particle bed reactor using light water steam as a propellant

International Nuclear Information System (INIS)

Powell, J.R.; Ludewig, H.; Maise, G.

1993-01-01

In this paper the possibility of configuring a water cooled Nuclear Thermal Propulsion (NTP) rocket, based on a Particle Bed Reactor (PBR) is investigated. This rocket will be used to operate on water obtained from near earth objects. The conclusions reached in this paper indicate that it is possible to configure a PBR based NTP rocket to operate on water and meet the mission requirements envisioned for it. No insurmountable technology issues have been identified

Nuclear medicine technology study guide

CERN Document Server

Patel, Dee

2011-01-01

Nuclear Medicine Technology Study Guide presents a comprehensive review of nuclear medicine principles and concepts necessary for technologists to pass board examinations. The practice questions and content follow the guidelines of the Nuclear Medicine Technology Certification Board (NMTCB) and American Registry of Radiological Technologists (ARRT), allowing test takers to maximize their success in passing the examinations. The book is organized by sections of increasing difficulty, with over 600 multiple-choice questions covering all areas of nuclear medicine, including radiation safety; radi

Nuclear technology

International Nuclear Information System (INIS)

1983-03-01

This report examines nuclear technology in Canada, with emphasis on Quebec, as a means of revitilizing industry. The historical, present day, and future states of Atomic Energy of Canada Limited are examined. Future research programs are discussed in greatest detail. These range from disposal of porcine wastes to new applications for electricity to nuclear medical techniques (to cite only a few examples). The executive summary is written in English. (23 fig., 16 tab.)

Experience in transfer of nuclear technology

International Nuclear Information System (INIS)

Beckurts, K.H.

1977-01-01

Nuclear energy development in the Federal Republic of Germany was initiated in 1955. In spite of this late start, the country now has a broad potential in all branches of peaceful nuclear technology. Turkey nuclear power plants are erected by German industry, and the country has the basic technology at its disposal for all stages of the nuclear fuel cycle. In the areas of uranium enrichment and reprocessing, multilateral joint ventures with European countries have been formed. The country also has an active development program for advanced reactors. In general areas of technology transfer and development aid, in the nuclear field, there are interrelated activities of both government and industry. The government has concluded bilateral agreements with a number of countires e.g. Argentina, Brazil, India, Iran and Pakistan, covering the general field of nuclear science; in the framework of these agreements, which are being carried out mainly by the nuclear research centers at Juelich and Karlsruhe, active cooperation in research, development, education, and training are being pursued. The nonproliferation of nuclear weapons is a major objective of the Federal government which strongly affects its policies for international nuclear trade. The paper describes the nuclear technology potential available in the Federal Republic of Germany and reviews experience gathered in cooperation with developing countries. Future policies for nuclear technology transfer are discussed with special reference to the role of national R and D laboratories

The development of nuclear technology transfer

International Nuclear Information System (INIS)

Nack-chung Sung

1987-01-01

Korea, as a recipient of nuclear technology transfer, has good experience of progressively building up its indigeneous capability of nuclear technology through three stages of technology transfer, namely: technology transfer under the turnkey approach, component approach, and integrated technology transfer with a local prime contractor. Here, each stage of experience of technology transfer, with Korea as a recipient, is presented. (author)

Effect of buoyancy on fuel containment in an open-cycle gas-core nuclear rocket engine.

Science.gov (United States)

Putre, H. A.

1971-01-01

Analysis aimed at determining the scaling laws for the buoyancy effect on fuel containment in an open-cycle gas-core nuclear rocket engine, so conducted that experimental conditions can be related to engine conditions. The fuel volume fraction in a short coaxial flow cavity is calculated with a programmed numerical solution of the steady Navier-Stokes equations for isothermal, variable density fluid mixing. A dimensionless parameter B, called the Buoyancy number, was found to correlate the fuel volume fraction for large accelerations and various density ratios. This parameter has the value B = 0 for zero acceleration, and B = 350 for typical engine conditions.

Canadian Experience in Nuclear Power Technology Transfer

International Nuclear Information System (INIS)

Boulton, J.

1987-01-01

Technology transfer has and will continue to play a major role in the development of nuclear power programs. From the early beginnings of the development of the peaceful uses of nuclear power by just a few nations in the mid-1940s there has been a considerable transfer of technology and today 34 countries have nuclear programs in various stages of development. Indeed, some of the major nuclear vendors achieves their present position through a process of technology transfer and subsequent development. Canada, one of the early leaders in the development of nuclear power, has experience with a wide range of programs bout within its own borders and with other countries. This paper briefly describes this experience and the lessons learned from Canada's involvement in the transfer of nuclear power technology. Nuclear technology is complex and diverse and yet it can be assimilated by a nation given a fire commitment of both suppliers and recipients of technology to achieve success. Canada has reaped large benefits from its nuclear program and we believe this has been instrumentally linked to the sharing of goals and opportunity for participation over extended periods of time by many interests within the Canadian infrastructure. While Canada has accumulated considerable expertise in nuclear technology transfer, we believe there is still much for US to learn. Achieving proficiency in any of the many kinds of nuclear related technologies will place a heavy burden on the financial and human resources of a nation. Care must be taken to plan carefully the total criteria which will assure national benefits in industrial and economic development. Above all, effective transfer of nuclear technology requires a long term commitment by both parties

Canada's commitment to nuclear technology

International Nuclear Information System (INIS)

Stewart, Murray J.

1998-01-01

This paper gives a broad update on all facets of the Canadian nuclear industry and demonstrates Canada's continuing commitment to nuclear technology. Canada has developed a global leadership position in nuclear technology for power generation, uranium production and isotope supply. This commitment is being further enhanced by successes in international markets with Candu technology, new uranium mine developments in our province of Saskatchewan, and expanding isotope capabilities including the construction of two new production reactors. Korea's economy is benefiting through collaboration with Canada's leading nuclear companies, both in Korea and Canada. These collaborations have the potential to expand considerably with the implementation of the Kyoto Framework Convention on Climate Change and the anticipated increased demand for new nuclear power generation installations in all major global markets. Much has been publicized about the situation surrounding Ontario Hydro Nuclear and its nuclear recovery program. This paper gives the background and highlights the actions within Ontario and Ontario Hydro designed to ensure the long term recovery of all twenty nuclear units in Ontario. The presentation at the conference will bring the audience completely up-to-date on recent events. (author)

CANDU nuclear reactor technology

International Nuclear Information System (INIS)

Kakaria, B. K.

1994-01-01

AECL has over 40 years of experience in the nuclear field. Over the past 20 years, this unique Canadian nuclear technology has made a worldwide presence, In addition to 22 CANDU reactors in Canada, there are also two in India, one in Pakistan, one in Argentina, four in Korea and five in Romania. CANDU advancements are based on evolutionary plant improvements. They consist of system performance improvements, design technology improvements and research and development in support of advanced nuclear power. Given the good performance of CANOU plants, it is important that this CANDU operating experience be incorporated into new and repeat designs

Fusion of Nuclear and Emerging Technology

International Nuclear Information System (INIS)

Nahrul Khaer Alang Rashid

2005-04-01

The presentation discussed the following subjects: emerging technology; nuclear technology; fusion emerging and nuclear technology; progressive nature of knowledge; optically stimulated luminescence - application of luminescence technology to sediments; Biosystemics technology -convergence nanotechnology, ecological science, biotechnology, cognitive science and IT - prospective impact on materials science, the management of public system for bio-health, eco and food system integrity and disease mitigation

ANSTO: Australian Nuclear Science and Technology Organization

International Nuclear Information System (INIS)

1989-01-01

The Australian Nuclear Science and Technology Organization conducts or is engaged in collaborative research and development in the application of nuclear science and associated technology. Through its Australian radio-isotopes unit, it markets radioisotopes, their products and other services for nuclear medicine industry and research. It also operates national nuclear facilities ( HIFAR and Moata research reactors), promote training, provide advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities. ills

A Unique Master's Program in Combined Nuclear Technology and Nuclear Chemistry at Chalmers University of Technology, Sweden

International Nuclear Information System (INIS)

Skarnemark, Gunnar; Allard, Stefan; Ekberg, Christian; Nordlund, Anders

2009-01-01

The need for engineers and scientists who can ensure safe and secure use of nuclear energy is large in Sweden and internationally. Chalmers University of Technology is therefore launching a new 2-year master's program in Nuclear Engineering, with start from the autumn of 2009. The program is open to Swedish and foreign students. The program starts with compulsory courses dealing with the basics of nuclear chemistry and physics, radiation protection, nuclear power and reactors, nuclear fuel supply, nuclear waste management and nuclear safety and security. There are also compulsory courses in nuclear industry applications and sustainable energy futures. The subsequent elective courses can be chosen freely but there is also a possibility to choose informal tracks that concentrate on nuclear chemistry or reactor technology and physics. The nuclear chemistry track comprises courses in e.g. chemistry of lanthanides, actinides and transactinides, solvent extraction, radioecology and radioanalytical chemistry and radiopharmaceuticals. The program is finished with a one semester thesis project. This is probably a unique master program in the sense of its combination of deep courses in both nuclear technology and nuclear chemistry.

Development of high burnup nuclear fuel technology

International Nuclear Information System (INIS)

Suk, Ho Chun; Kang, Young Hwan; Jung, Jin Gone; Hwang, Won; Park, Zoo Hwan; Ryu, Woo Seog; Kim, Bong Goo; Kim, Il Gone

1987-04-01

The objectives of the project are mainly to develope both design and manufacturing technologies for 600 MWe-CANDU-PHWR-type high burnup nuclear fuel, and secondly to build up the foundation of PWR high burnup nuclear fuel technology on the basis of KAERI technology localized upon the standard 600 MWe-CANDU- PHWR nuclear fuel. So, as in the first stage, the goal of the program in the last one year was set up mainly to establish the concept of the nuclear fuel pellet design and manufacturing. The economic incentives for high burnup nuclear fuel technology development are improvement of fuel utilization, backend costs plant operation, etc. Forming the most important incentives of fuel cycle costs reduction and improvement of power operation, etc., the development of high burnup nuclear fuel technology and also the research on the incore fuel management and safety and technologies are necessary in this country

Technology transfer from Canadian nuclear laboratories

International Nuclear Information System (INIS)

MacDonald, R.D.; Evans, W.; MacEwan, J.R.; Melvin, J.G.

1985-09-01

Canada has developed a unique nuclear power system, the CANDU reactor. AECL - Research Company (AECL-RC) has played a key role in the CANDU program by supplying its technology to the reactor's designers, constructors and operators. This technology was transferred from our laboratories to our sister AECL companies and to domestic industries and utilities. As CANDUs were built overseas, AECL-RC made its technology available to foreign utilities and agencies. Recently the company has embarked on a new transfer program, commercial R and D for nuclear and non-nuclear customers. During the years of CANDU development, AECL-RC has acquired the skills and technology that are especially valuable to other countries embarking on their own nuclear programs. This report describes AECL-RC's thirty years' experience with the transfer of technology

Nuclear Reactors and Technology; (USA)

Energy Technology Data Exchange (ETDEWEB)

Cason, D.L.; Hicks, S.C. (eds.)

1991-01-01

Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

A study on nuclear technology policy

International Nuclear Information System (INIS)

Kim, H. J.; Oh, K. B.; Lee, K. S.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, I.

2004-01-01

This study was conducted as a part of institutional activities of KAERI, and the objective of the study is to survey and analyze the change of international environment in nuclear use and research and development environment, and to propose systematic alternatives on technology policy for efficiency and effectiveness of research and development through national R and D program while timely responding to the environmental change in local and global sense. Acknowledging the importance of the relationship between the external environment and the national nuclear R and D strategic planning, this study focused on the two major subjects: (1) the international environmental and technological change attached to the development of nuclear power; (2) the direction and strategy of nuclear R and D to improve effectiveness through national R and D programs as role of electricity in the future society, strategic environment of nuclear use and R and D in the future society, energy environment and nuclear technology development scenario in the future, strategic study on future vision of KAERI and technological road-mapping of national nuclear R and D for enhancing competitiveness

Cryogenics in nuclear reactor technology

International Nuclear Information System (INIS)

Dharmadurai, G.

1982-01-01

The cryogenic technology has significantly contributed to the development of several proven techniques for use in the nuclear power industry. A noteworthy feature is the unique role of cryogenics in minimising the release of radioactive and some chemical pollutants to the environment during the operation of various plants associated with this industry. The salient technological features of several cryogenic processes relevant to the nuclear reactor technology are discussed. (author)

China's nuclear technology for economy growth

International Nuclear Information System (INIS)

Lu, Yanxiao

1998-01-01

The transfer of nuclear technology to practical applications in energy, agriculture, food, industries and others has made important contributions to the prosperity of the national economy and the improvement of living standard of Chinese people in the past 40 years. Facing the great challenges in upcoming years, sustained efforts are needed to promote industrialization, commercialization and internationalization of nuclear technology. Rapid economic growth is providing the golden opportunities for the development of nuclear technology in China. With the trends to globalization of economic development, civilian applications of nuclear technology will have to be involved in international co-operation and competitive world markets to narrow the gap between China and other developed countries in the world in the next century. (author)

Strategy for Nuclear Technology Education at Uppsala University

International Nuclear Information System (INIS)

Osterlund, M.; Hakansson, A.; Tengborn, E.

2010-01-01

After the TMI accident 1979, and later the Tjernobyl accident, the future of nuclear power was vividly debated in Sweden. The negative public opinion governed a number of political decisions that marked an ambition to out-phase nuclear power prior to 2010. Due to this, the student's interest in nuclear technology ceased and together with the fact that public funding to nuclear technology was withdrawn, academic research and education within the field were effectively dismounted. In the beginning of 1990 it became clear to the society that nuclear power could not easily be closed down and the issue of the future competence supply to the nuclear industry was initiated. In the mid-nineties the situation became acute due to the fact that personnel in the nuclear industry started to retire in an increasing pace necessitating measures to be taken in order to secure the future operation of the nuclear power plants. In the year 2000, the Swedish nuclear power plants, Westinghouse Electric Sweden and the Swedish Radiation Safety Authority embarked a project together with the three major universities in the field, Uppsala University, The Royal Institute of Technology and Chalmers University of Technology. The aim of this project was to define a financial platform for reconstructing the Swedish research and education in nuclear technology. The project, named the Swedish Centre for Nuclear Technology (SKC), has during a decade been the major financier to nuclear technology research and education. Using funding from SKC, Uppsala University formulated a strategy along two tracks: 1) Instead of creating ambitious master programs in nuclear technology, the already existing engineering programs in a wide range of fields were utilized to expose as many students as possible to nuclear technology. 2) A program was initiated together with the nuclear industry aiming at educating newly employed personnel. The result is encouraging; starting from essentially zero, typically 100

Application of SDI technology in space propulsion

International Nuclear Information System (INIS)

Klein, A.J.

1992-01-01

Numerous technologies developed by the DOD within the SDI program are now available for adaptation to the requirements of commercial spacecraft; SDI has accordingly organized the Technology Applications Information System data base, which contains nearly 2000 nonproprietary abstracts on SDI technology. Attention is here given to such illustrative systems as hydrogen arcjets, ammonia arcjets, ion engines, SSTO launch vehicles, gel propellants, lateral thrusters, pulsed electrothermal thrusters, laser-powered rockets, and nuclear propulsion

Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-10-15

Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW{sub th} and an electricity generation mode of 100 kW{sub th}, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

International Nuclear Information System (INIS)

Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon

2015-01-01

Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW th and an electricity generation mode of 100 kW th , equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and thermohydraulics

Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

Directory of Open Access Journals (Sweden)

Seung Hyun Nam

2015-10-01

Full Text Available Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER, for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MWth and an electricity generation mode of 100 kWth, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

Nuclear technology in Peru

International Nuclear Information System (INIS)

Montoya, M.

1993-01-01

This book deals with the Nuclear Energy in Peru. It consists of ten chapters. In the first chapter is presented a rapid overview on nuclear science history. The second chapter describes the nuclear proliferation and the nuclear competition in South America. The nuclear organization in Peru, the Peruvian Institute of Nuclear Energy, and the main centers are described in the third chapter. The following chapters deals with peruvian advances in nuclear medicine, agriculture and food, nuclear application to industry, hydrology, earth sciences and environmental considerations. In the last chapter, the perspectives for nuclear science and technology in Peru are described from the inter institutional cooperation point of view. This book also includes appendix and bibliography. (author)

Design considerations for a pressure-driven multi-stage rocket

Science.gov (United States)

Sauerwein, Steven Craig

2002-01-01

The purpose of this study was to examine the feasibility of using propellant tank pressurization to eliminate the use of high-pressure turbopumps in multi-stage liquid-fueled satellite launchers. Several new technologies were examined to reduce the mass of such a rocket. Composite materials have a greater strength-to-weight ratio than metals and can be used to reduce the weight of rocket propellant tanks and structure. Catalytically combined hydrogen and oxygen can be used to heat pressurization gas, greatly reducing the amount of gas required. Ablatively cooled rocket engines can reduce the complexity and cost of the rocket. Methods were derived to estimate the mass of the various rocket components. These included a method to calculate the amount of gas needed to pressurize a propellant tank by modeling the behavior of the pressurization gas as the liquid propellant flows out of the tank. A way to estimate the mass and size of a ablatively cooled composite cased rocket engine. And a method to model the flight of such a rocket through the atmosphere in conjunction with optimization of the rockets trajectory. The results show that while a liquid propellant rocket using tank pressurization are larger than solid propellant rockets and turbopump driven liquid propellant rockets, they are not impractically large.

Strengthened International Nuclear Safeguards; burdens and Effects on Nuclear Technology Development

International Nuclear Information System (INIS)

Badawy, I.

2000-01-01

The present paper deals with the recent direction of strengthening the international nuclear safeguards and the effects on the development of nuclear technology for peaceful applications. The new basic principles for strengthening the international nuclear control in the direction of undeclared nuclear activities are elaborated, and the national obligations are indicated. The burdens on the development of nuclear technology are discussed. Approaches are proposed in this work for coping with the present and future situations

Rocket Science at the Nanoscale.

Science.gov (United States)

Li, Jinxing; Rozen, Isaac; Wang, Joseph

2016-06-28

Autonomous propulsion at the nanoscale represents one of the most challenging and demanding goals in nanotechnology. Over the past decade, numerous important advances in nanotechnology and material science have contributed to the creation of powerful self-propelled micro/nanomotors. In particular, micro- and nanoscale rockets (MNRs) offer impressive capabilities, including remarkable speeds, large cargo-towing forces, precise motion controls, and dynamic self-assembly, which have paved the way for designing multifunctional and intelligent nanoscale machines. These multipurpose nanoscale shuttles can propel and function in complex real-life media, actively transporting and releasing therapeutic payloads and remediation agents for diverse biomedical and environmental applications. This review discusses the challenges of designing efficient MNRs and presents an overview of their propulsion behavior, fabrication methods, potential rocket fuels, navigation strategies, practical applications, and the future prospects of rocket science and technology at the nanoscale.

An Effective Method For Nuclear Technology Transfer

International Nuclear Information System (INIS)

Jeon, Jan Pung

1987-01-01

Three basic entities involved in the implementation of nuclear projects are the Owner, Regulatory Authority and Nuclear Industry. Their ultimate objective is to secure the safe, reliable and economical nuclear energy. For s successful nuclear power program, the owner should maintain a good relationship with the other entities and pursue an optimization of the objectives. On the other hand, he should manage projects along the well - planned paths in order to effectively learn the nuclear technology. One of the problems in the nuclear projects of developing countries was the absence of long - term technology development program, a limited local participation and the technical incapability. For the effective technology transfer, a motivation of the technology supplier and a readiness of the recipient to accommodate such technologies are required. Advanced technology is usually developed at considerable expense with the expectation that the developer will use it in furthering his own business. Therefore, he tends to be reluctant to transfer it to the others, particularly, to the potential competitors. There is a disinclination against further technology transfer beyond the minimum contractual obligation or the requirements by Government Regulatory. So, an additional commercial incentive must be provided to the developer

Y-Notes; Introductory Sessions on Nuclear Technology

International Nuclear Information System (INIS)

2001-01-01

This chapter is divided into next parts: What is 'Y-Notes ; Young generation opening session; Nuclear education and transfer of know-how; Nuclear technology; Other applications of nuclear technology; Nuclear programs and technical cooperation; Political aspects; Environment and safety; Communication and public perception; Economics; Fuel cycle challenges; Video

Let nuclear technology create new brilliancy for china's sustainable development

International Nuclear Information System (INIS)

Du Xiangwan

2008-01-01

This paper summarizes the development and application directions of nuclear technology, including five aspects: nuclear technology and energy nuclear technology and medicine, nuclear anclear analysis technology, nuclear radiation technology, astronautics and voyage's nuclear power, etc. The paper discusses the importance of them to sustainable development and generalizes the development trilogy of nuclear science and technology and its prospect. (authors)

Nuclear technology databases and information network systems

International Nuclear Information System (INIS)

Iwata, Shuichi; Kikuchi, Yasuyuki; Minakuchi, Satoshi

1993-01-01

This paper describes the databases related to nuclear (science) technology, and information network. Following contents are collected in this paper: the database developed by JAERI, ENERGY NET, ATOM NET, NUCLEN nuclear information database, INIS, NUclear Code Information Service (NUCLIS), Social Application of Nuclear Technology Accumulation project (SANTA), Nuclear Information Database/Communication System (NICS), reactor materials database, radiation effects database, NucNet European nuclear information database, reactor dismantling database. (J.P.N.)

Interviews concerning topical questions in nuclear technology

International Nuclear Information System (INIS)

Segatz, U.; Schatz, A.; Stephany, M.; Michaelis, H.

1978-01-01

On the occasion of the Nuclex meeting, October 3-7, 1978, Basle/Switzerland, the editorial department of 'Atom und Strom' questioned some leading scientists in nuclear technology on particularly relevant topics. The following subjects were discussed: - How long can we do without nuclear energy, - Modern technology for nuclear power plants, - Nuclear fuel cycle and environment, - Nuclear energy and European Communities, - Nuclear energy and its risks (reflections on incidents). (orig./UA) [de

A Study on the Linkage between Nano Fusion Technology and Nuclear Technology

International Nuclear Information System (INIS)

Jeong, Ik; Lim, Chae Young; Lee, Jong Hee

2009-02-01

1) A survey of national energy policy trends in major nation - to secure renewal energy in the level of making a plan to supply national energy in the future - Tendency of energy policy based on Europe 2) A survey of the nano technology development - Status of major nano technology development - Developmental direction of nano technology related to nuclear energy 3) the nano technology development related with nuclear - high-temperature nuclear reactor by applying nano science and technology under quick development - materials required to high-level radioactive wastes treatment facility - develop materials of nuclear fusion facility in the long-term view 4) Innovation system of nano technology - Energy source -> conversion to energy -> distribution of energy -> energy storage -> energy use

History of nuclear technology development in Japan

Energy Technology Data Exchange (ETDEWEB)

Yamashita, Kiyonobu, E-mail: yamashita.kiyonobu@jaea.go.jp [Visiting Professor, at the Faculty of Petroleum and Renewable Energy Engineering, University Teknologi Malaysia Johor Bahru 81310 (Malaysia); General Advisor Nuclear HRD Centre, Japan Atomic Energy Agency, TOKAI-mura, NAKA-gun, IBARAKI-ken, 319-1195 (Japan)

2015-04-29

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

Science.gov (United States)

Yamashita, Kiyonobu

2015-04-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident.

History of nuclear technology development in Japan

International Nuclear Information System (INIS)

Yamashita, Kiyonobu

2015-01-01

Nuclear technology development in Japan has been carried out based on the Atomic Energy Basic Act brought into effect in 1955. The nuclear technology development is limited to peaceful purposes and made in a principle to assure their safety. Now, the technologies for research reactors radiation application and nuclear power plants are delivered to developing countries. First of all, safety measures of nuclear power plants (NPPs) will be enhanced based on lesson learned from TEPCO Fukushima Daiichi NPS accident

On use of hybrid rocket propulsion for suborbital vehicles

Science.gov (United States)

Okninski, Adam

2018-04-01

While the majority of operating suborbital rockets use solid rocket propulsion, recent advancements in the field of hybrid rocket motors lead to renewed interest in their use in sounding rockets. This paper presents results of optimisation of sounding rockets using hybrid propulsion. An overview of vehicles under development during the last decade, as well as heritage systems is provided. Different propellant combinations are discussed and their performance assessment is given. While Liquid Oxygen, Nitrous Oxide and Nitric Acid have been widely tested with various solid fuels in flight, Hydrogen Peroxide remains an oxidiser with very limited sounding rocket applications. The benefits of hybrid propulsion for sounding rockets are given. In case of hybrid rocket motors the thrust curve can be optimised for each flight, using a flow regulator, depending on the payload and mission. Results of studies concerning the optimal burn duration and nozzle selection are given. Specific considerations are provided for the Polish ILR-33 "Amber" sounding rocket. Low regression rates, which up to date were viewed as a drawback of hybrid propulsion may be used to the benefit of maximising rocket performance if small solid rocket boosters are used during the initial flight period. While increased interest in hybrid propulsion is present, no up-to-date reference concerning use of hybrid rocket propulsion for sounding rockets is available. The ultimate goal of the paper is to provide insight into the sensitivity of different design parameters on performance of hybrid sounding rockets and delve into the potential and challenges of using hybrid rocket technology for expendable suborbital applications.

Economy and technology roles played by nuclear power

International Nuclear Information System (INIS)

Yamada, Eiji

1985-01-01

On the basis of the survey analysis made by Atomic Energy Commission on the roles in economy and technology played in the nuclear energy development and utilization, the following are described: economic roles in nuclear energy development and utilization (the present state of nuclear power industry in Japan and the economy effects); technological roles in the same (the present state of nuclear power technology in Japan and the technology effects). The economy effects in other areas are on higher level than in other industries etc. Then, in the technology effects, system technology and quality control in the nuclear power possess significant effects in other areas. While the nuclear energy development and utilization is important in Japan's energy security, it is contributing largely to the economy and society in Japan. (Mori, K.)

Nuclear Malaysia Strategic Approach Towards Public Acceptance on Nuclear Technology

International Nuclear Information System (INIS)

Hasfazilah Hassan; Redzuan Mohamad; Abdul Halim Jumat; Sabariah Kader Ibrahim

2016-01-01

Full text: This paper describes the strategic approach taken by Malaysian Nuclear Agency in carrying out public information and public acceptance on nuclear technology activities. The main objective of this study is to ensure that public and stake holders are continuously getting correct information from credible sources. Through the feedback received, comprehensive and holistic approach provides the desired impact. Obtaining the correct information from credible sources culture should always be inculcate to ensure that the benefits of nuclear technologies can be practiced and accepted by civil society without prejudice. Through strategic approach and activities implemented, monitoring and review, and measurement of the effectiveness of ongoing programs are expected to increase public awareness of the importance and contribution of nuclear technology in Malaysia. (author)

Assessment of the advantages and feasibility of a nuclear rocket

International Nuclear Information System (INIS)

Howe, S.D.

1985-01-01

The feasibility of rebuilding and testing a nuclear thermal rocket (NTR) for the Mars mission has been investigated. Calculations indicate that an NTR would substantially reduce the earth-orbit assembled mass compared to LOX/LH 2 systems. The mass savings were 36% and 65% for the cases of total aerobraking and of total propulsive braking respectively. Consequently, the cost savings for a single mission of using an NTR, if aerobraking is feasible, are probably insufficient to warrant the NTR development. If multiple missions are planned or if propulsive braking is desired at Mars and/or at Earth, then the savings of about $7B will easily pay for the NTR development. Estimates of the cost of rebuilding a NTR were based on the previous NERVA program's budget plus additional costs to develop a flight ready engine. The total cost to build the engine would be between $4 to 5B. The concept of developing a full-power test stand at Johnston Atoll in the Pacific appears very feasible. The added expense of building facilities on the island should be less than $1.4B

Nuclear Science and Technology for Thai Society

International Nuclear Information System (INIS)

Thailand Institute of Nuclear Technology, Bangkok

2009-07-01

Full text: Full text: The 11th conference on the nuclear science and technology was held on 2-3 July 2009 in Bangkok. This conference contain paper on non-power applications of nuclear technology in medicine, agriculture and industry. These application include irradiation of food for the infestation tram technologies used in diagnosis and therapy and radiation chemistry important to industrial processes. Some technologies which evolved from the development of nuclear power industry are also discussed

Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

2009-01-01

Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

Rockets for Extended Source Soft X-ray Spectroscopy

Science.gov (United States)

McEntaffer, Randall

The soft X-ray background surrounds our local galactic environment yet very little is known about the physical characteristics of this plasma. A high-resolution spectrum could unlock the properties of this million degree gas but the diffuse, low intensity nature of the background have made it difficult to observe, especially with a dispersive spectrograph. Previous observations have relied on X-ray detector energy resolution which produces poorly defined spectra that are poorly fit by complex plasma models. Here we propose a series of suborbital rocket flights that will begin the characterization of this elusive source through high-resolution X-ray grating spectroscopy. The rocket-based spectrograph can resolve individual emission lines over the soft X-ray band and place tight constraints on the temperature, density, abundance, ionization state and age of the plasma. These payloads will draw heavily from the heritage gained from previous rocket missions, while also benefiting from related NASA technology development programs. The Pennsylvania State University (PSU) team has a history of designing and flying spectrometer components onboard rockets while also being scientific leaders in the field of diffuse soft X-ray astronomy. The PSU program will provide hands-on training of young scientists in the techniques of instrumental and observational X-ray astronomy. The proposed rocket program will also expose these researchers to a full experiment cycle: design, fabrication, tolerance analysis, assembly, flight-qualification, calibration, integration, launch, and data analysis; using a combination of technologies suitable for adaptation to NASA's major missions. The PSU program in suborbital X-ray astronomy represents an exciting mix of compelling science, heritage, cutting-edge technology development, and training of future scientists.

NASA's Hydrogen Outpost: The Rocket Systems Area at Plum Brook Station

Science.gov (United States)

Arrighi, Robert S.

2016-01-01

"There was pretty much a general knowledge about hydrogen and its capabilities," recalled former researcher Robert Graham. "The question was, could you use it in a rocket engine? Do we have the technology to handle it? How will it cool? Will it produce so much heat release that we can't cool the engine? These were the questions that we had to address." The National Aeronautics and Space Administration's (NASA) Glenn Research Center, referred to historically as the Lewis Research Center, made a concerted effort to answer these and related questions in the 1950s and 1960s. The center played a critical role transforming hydrogen's theoretical potential into a flight-ready propellant. Since then NASA has utilized liquid hydrogen to send humans and robots to the Moon, propel dozens of spacecraft across the universe, orbit scores of satellite systems, and power 135 space shuttle flights. Rocket pioneers had recognized hydrogen's potential early on, but its extremely low boiling temperature and low density made it impracticable as a fuel. The Lewis laboratory first demonstrated that liquid hydrogen could be safely utilized in rocket and aircraft propulsion systems, then perfected techniques to store, pump, and cleanly burn the fuel, as well as use it to cool the engine. The Rocket Systems Area at Lewis's remote testing area, Plum Brook Station, played a little known, but important role in the center's hydrogen research efforts. This publication focuses on the activities at the Rocket Systems Area, but it also discusses hydrogen's role in NASA's space program and Lewis's overall hydrogen work. The Rocket Systems Area included nine physically modest test sites and three test stands dedicated to liquid-hydrogen-related research. In 1962 Cleveland Plain Dealer reporter Karl Abram claimed, "The rocket facility looks more like a petroleum refinery. Its test rigs sprout pipes, valves and tanks. During the night test runs, excess hydrogen is burned from special stacks in the best

Recommended numerical nuclear physics data for cutting-edge nuclear technology applications

International Nuclear Information System (INIS)

Ganesan, S.; Srivenkatesan, R.; Anek Kumar; Murthy, C.S.R.C.; Dhekne, P.S.

2005-01-01

This paper introduces some aspects of online nuclear data services at Mumbai as part of today's technology of sharing knowledge of the recommended numerical nuclear physics data for nuclear applications. The physics foundation for cutting-edge technology applications is significantly strengthened by such knowledge generation and sharing techniques. A BARC server is presently mirroring the nuclear data services of the IAEA, Vienna. The users can get all the nuclear data information much faster from the BARC nuclear data mirror website that is now fully operational. The nuclear community is encouraged to develop the habit of accessing the website for recommended values of nuclear data for use in research and applications. The URL is: www-nds.indcentre.org.in (author)

Consideration on the interaction between society and nuclear technology

International Nuclear Information System (INIS)

Shinoda, Yoshihiko

2007-01-01

A social conflict over nuclear technology arises from the different interactions between society and nuclear technology. The purpose of this review is to grasp the essential points of this social conflict from a social viewpoint. These essential points can be discerned by interpreting results of polls about nuclear technology and the future of society in general. As a result, attitudes towards nuclear technology can be explained in terms of differences of general views on society such as social order or social progress. The attitudes of people toward nuclear technology were divided into strong agreement, weak agreement, weak objection and strong objection in order to obtain useful information for clarification of social conflict on this issue. Results of polls of people who have weak agreement for nuclear technology reveal their ambivalence about nuclear technology. This raises concern that further implementation of nuclear technology might cause these people to shift their views to objection. (author)

Localization of nuclear power plant technology

International Nuclear Information System (INIS)

Stiteler, F.Z.; Rudek, T.G.

1998-01-01

Asia, and particularly China, has an enormous need for power and must deal with the practicalities of building large base load units. In China, as in other countries, there are limitations on the use of large quantities of fossil fuel. This raises the possibility of turning to nuclear power to satisfy their energy needs. Other issues tend to point to the nuclear option for these growing economies, including economic considerations, environmental concerns, energy independence and raising the technological capabilities of the country. When a country embarks on a nuclear power program with the intention of localizing the technology, a long-term commitment is necessary to achieve this objective. Localization of nuclear technology is not a new phenomenon. The nature of the industry from the early beginnings has always involved transfer of technology when a new country initiated a nuclear power construction program. In fact, most previous experiences with this localization process involved heavy governmental, political and financial support to drive the success of the program. Because of this strong governmental support, only the receiving nation's companies were generally allowed to participate in the local business operations of the technology recipient. What is new and different today is the retreat from heavy financial support by the receiving country's government. This change has created a strong emphasis on cost-effectiveness in the technology transfer process and opportunities for foreign companies to participate in local business activities. ABB is a world-wide company with two parent companies that have been very active over many years in establishing cost-justified local operations throughout the world. Today, ABB has become the largest electrical engineering company in the world with respected local operations in nearly every country. Lessons learned by ABB in their world-wide localization initiatives are being applied to the challenge of cost

Current Abstracts Nuclear Reactors and Technology

Energy Technology Data Exchange (ETDEWEB)

Bales, J.D.; Hicks, S.C. [eds.

1993-01-01

This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

Nuclear Proliferation Technology Trends Analysis

Energy Technology Data Exchange (ETDEWEB)

Zentner, Michael D.; Coles, Garill A.; Talbert, Robert J.

2005-10-04

A process is underway to develop mature, integrated methodologies to address nonproliferation issues. A variety of methodologies (both qualitative and quantitative) are being considered. All have one thing in common, a need for a consistent set of proliferation related data that can be used as a basis for application. One approach to providing a basis for predicting and evaluating future proliferation events is to understand past proliferation events, that is, the different paths that have actually been taken to acquire or attempt to acquire special nuclear material. In order to provide this information, this report describing previous material acquisition activities (obtained from open source material) has been prepared. This report describes how, based on an evaluation of historical trends in nuclear technology development, conclusions can be reached concerning: (1) The length of time it takes to acquire a technology; (2) The length of time it takes for production of special nuclear material to begin; and (3) The type of approaches taken for acquiring the technology. In addition to examining time constants, the report is intended to provide information that could be used to support the use of the different non-proliferation analysis methodologies. Accordingly, each section includes: (1) Technology description; (2) Technology origin; (3) Basic theory; (4) Important components/materials; (5) Technology development; (6) Technological difficulties involved in use; (7) Changes/improvements in technology; (8) Countries that have used/attempted to use the technology; (9) Technology Information; (10) Acquisition approaches; (11) Time constants for technology development; and (12) Required Concurrent Technologies.

Fuel/propellant mixing in an open-cycle gas core nuclear rocket engine

International Nuclear Information System (INIS)

Guo, X.; Wehrmeyer, J.A.

1997-01-01

A numerical investigation of the mixing of gaseous uranium and hydrogen inside an open-cycle gas core nuclear rocket engine (spherical geometry) is presented. The gaseous uranium fuel is injected near the centerline of the spherical engine cavity at a constant mass flow rate, and the hydrogen propellant is injected around the periphery of the engine at a five degree angle to the wall, at a constant mass flow rate. The main objective is to seek ways to minimize the mixing of uranium and hydrogen by choosing a suitable injector geometry for the mixing of light and heavy gas streams. Three different uranium inlet areas are presented, and also three different turbulent models (k-var-epsilon model, RNG k-var-epsilon model, and RSM model) are investigated. The commercial CFD code, FLUENT, is used to model the flow field. Uranium mole fraction, axial mass flux, and radial mass flux contours are obtained. copyright 1997 American Institute of Physics

Analysis of startup strategies for a particle bed reactor nuclear rocket engine

Science.gov (United States)

Suzuki, D. E.

1993-06-01

This paper develops and analyzes engine system startup strategies for a particle bed reactor (PBR) nuclear rocket engine. The strategies are designed to maintain stable flow through the PBR fuel element while reaching the design conditions as quickly as possible. The analyses are conducted using a computer model of a representative particle bed reactor and engine system. Elements of the startup strategy considered include: the coordinated control of reactor power and coolant flow; turbine inlet temperature and flow control; and use of an external starter system. The simulation results indicate that the use of an external starter system enables the engine to reach design conditions very quickly while maintaining the flow well away from the unstable regime. If a bootstrap start is used instead, the transient does not progress as fast and approaches closer to the unstable flow regime, but allows for greater engine reusability. These results can provide important information for engine designers and mission planners.

The Application of Nuclear Technology for a Better World

International Nuclear Information System (INIS)

Ita, E.B.

2015-01-01

Nuclear Technology is widely used in different areas and sector of our economy to better man kind and his environment. Peaceful applications of nuclear technology have several benefits to the world today. It is widely believed that nuclear technology is mainly used mainly for the production of electricity (Nuclear Power Plants – NPPs). Many are not aware of the other numerous benefits of nuclear technology. Nuclear technology can be applied in different fields for numerous benefits. Different sectors Nuclear Technology application can improve the living standard of man and his environment: – Food and Agriculture; – Medicine; – Industrial; – Energy; – Education; — Research and Development; – Environment. The benefits of the application of nuclear technology cannot be over emphasised. These benefits range from the improved quality of purified water we drink, the textiles we wear, improved quality of stored grains for preservation of foods, water analyses, improved transportation system work, drugs production, medical tests and analysis, clean environment through radioisotope techniques etc. The application of nuclear technology also gives a safer, greener, healthier and pollution free environment and atmosphere for human habitation. In my poster, the numerous benefits of the various applications of Nuclear Technology will be clearly enumerated and heighted. (author)

COBALT: Development of a Platform to Flight Test Lander GN&C Technologies on Suborbital Rockets

Science.gov (United States)

Carson, John M., III; Seubert, Carl R.; Amzajerdian, Farzin; Bergh, Chuck; Kourchians, Ara; Restrepo, Carolina I.; Villapando, Carlos Y.; O'Neal, Travis V.; Robertson, Edward A.; Pierrottet, Diego;

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1976-01-01

Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1972-01-01

Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle.Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear poin

International Nuclear Science and Technology Conference 2016

International Nuclear Information System (INIS)

2017-01-01

Conference Nuclear technology has played an important role in many aspects of our lives, including agriculture, medicine and healthcare, materials, environment, forensics, energy, and frontier advancement. The International Nuclear Science and Technology Conference (INST) aims to bring together scientists, engineers, academics and students to share knowledge and experiences about all aspects of nuclear sciences. INST2016 was the second of the INST conference series organized by Thailand Institute of Nuclear Technology. INST has evolved from a national conference series on nuclear science and technology that was held every two years in Bangkok for over a twenty-year period. INST2016 was held from 4 - 6 August 2016 in Bangkok, Thailand, under the central theme “Nuclear for Better Life”. The conference working language was English. The oral and poster research presentations covered seven major topics: • Nuclear physics and engineering (PHY) • Nuclear and radiation safety (SAF) • Medical and nutritional applications (MED) • Environmental applications (ENV) • Radiation processing and industrial applications (IND) • Agriculture and food applications (AGR) • Instrumentation and other related topics (INS) The welcome addresses, committees, program of the conference and the list of presentations can be found in the PDF. (paper)

Nuclear Technology Review 2013. Report by the Director General

International Nuclear Information System (INIS)

2013-01-01

In response to requests by Member States, the Secretariat produces a comprehensive Nuclear Technology Review each year. Attached is this year's report, which highlights notable developments principally in 2012. The Nuclear Technology Review 2013 covers the following areas: power applications, atomic and nuclear data, accelerators and research reactors, and nuclear sciences and applications. Additional documentation associated with the Nuclear Technology Review 2013 is available on the Agency's website1 in English on nuclear hydrogen production technology and preliminary lessons learned from the Fukushima Daiichi accident for advanced nuclear power plant technology development. Information on the IAEA's activities related to nuclear science and technology can also be found in the IAEA's Annual Report 2012 (GC(57)/3), in particular the Technology section, and the Technical Cooperation Report for 2012 (GC(57)/INF/4). The document has been modified to take account, to the extent possible, of specific comments by the Board of Governors and other comments received from Member States. (author)

A study on the nuclear technology policy

International Nuclear Information System (INIS)

Yang, M. H.; Kim, H. J.; Chung, W. S.; Lee, T. J.; Yun, S. W.; Jeong, Ik

2002-01-01

This study was carried out as a part of institutional activities of KAERI. This study suggested the effective and systematic alternatives for the development of domestic industry through nuclear long-term R and D program while timely responding to the environmental change in local and global sense. First of all, this study investigated the current status and prospect of nuclear power supply, the global technological change of nuclear fuel cycle, the nuclear policy changes of major countries and the role of nuclear energy in East Asian countries. Second, some policy alternatives are suggested in association with the role of national R and D in enhancing industrial competitiveness, the effective management of nuclear long-term R and D program to facilitate technological innovation and the way to enlarge the utilization of nuclear R and D results and radiation technology

The transfer of nuclear technology: necessities and limitations

International Nuclear Information System (INIS)

Haunschild, H.-H.

1978-01-01

Political and economical importance of the transfer of nuclear technologies to less developed countries is examined. Energy needs of the world create the necessity of technology transfer. Three levels are distinguished: 1) Basic elements of cooperation are agreed between the two Governments, 2) scientific cooperation and 3) industrial cooperation. Technology transfer is more than mere technology export. Limitations of nuclear technology transfer are: the lack of infrastructure, the high price of a nuclear power station but above all the problem of proliferation. In conclusion the solution of international problems of nuclear energy is the concept of cooperation on the basis of equal rights

Can nuclear power be enough for future technology?

International Nuclear Information System (INIS)

Serizawa, Akimi

2017-01-01

This paper focused on the report 'Can nuclear power be future technology?' published on September 28, 2008 by the Leading R and D Committee of Japan Society for the Promotion of Science. It took up part of the discussions at the general discussion session, and those of two working groups mainly by young committee members, and summarized and compiled them. Regarding 'maturity of nuclear technology as future technology,' this paper summarized and discussed from the technical viewpoint the current situation and problems of nuclear power in consideration of the future. Major topics include (1) nuclear safety and disaster prevention, (2) decommissioning of rectors (normal reactors, and accident reactors), (3) back end, (4) effects of low-level radiation, (5) technology trends, (6) economic efficiency, and (7) human resource development. Regarding 'social acceptability of nuclear energy,' the following were discussed: (1) basic human rights such as 'moral rights' and nuclear technologies, (2) risk communication and its problems, and (3) measures to improve the reliability of stakeholders involved in nuclear power. Regarding 'nuclear accident responding team,' this paper covered the nuclear accident responding unit founded in France after the nuclear accident in Japan, and nuclear accident responding unit founded in Japan. (A.O.)

Ricardo Dyrgalla (1910-1970), pioneer of rocket development in Argentina

Science.gov (United States)

de León, Pablo

2009-12-01

One of the most important developers of liquid propellant rocket engines in Argentina was Polish-born Ricardo Dyrgalla. Dyrgalla immigrated to Argentina from the United Kingdom in 1946, where he had been studying German weapons development at the end of the Second World War. A trained pilot and aeronautical engineer, he understood the intricacies of rocket propulsion and was eager to find practical applications to his recently gained knowledge. Dyrgalla arrived in Argentina during Juan Perón's first presidency, a time when technicians from all over Europe were being recruited to work in various projects for the recently created Argentine Air Force. Shortly after immigrating, Dyrgalla proposed to develop an advanced air-launched weapon, the Tábano, based on a rocket engine of his design, the AN-1. After a successful development program, the Tábano was tested between 1949 and 1951; however, the project was canceled by the government shortly after. Today, the AN-1 rocket engine is recognized as the first liquid propellant rocket to be developed in South America. Besides the AN-1, Dyrgalla also developed several other rockets systems in Argentina, including the PROSON, a solid-propellant rocket launcher developed by the Argentine Institute of Science and Technology for the Armed Forces (CITEFA). In the late 1960s, Dyrgalla and his family relocated to Brazil due mostly to the lack of continuation of rocket development in Argentina. There, he worked for the Institute of Aerospace Technology (ITA) until his untimely death in 1970. Ricardo Dyrgalla deserves to be recognized among the world's rocket pioneers and his contribution to the science and engineering of rocketry deserves a special place in the history of South America's rocketry and space flight advocacy programs.

Analysis on Japanese nuclear industrial technologies and their military implications

Energy Technology Data Exchange (ETDEWEB)

Kim, H S; Yang, M H; Kim, H J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

Analysis on Japanese nuclear industrial technologies and their military implications

International Nuclear Information System (INIS)

Kim, H. S.; Yang, M. H.; Kim, H. J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months

Research on process management of nuclear power technological innovation

International Nuclear Information System (INIS)

Yang Hua; Zhou Yu

2005-01-01

Different from the other technological innovation processes, the technological innovation process of nuclear power engineering project is influenced deeply by the extensive environmental factors, the technological innovation of nuclear power engineering project needs to make an effort to reduce environmental uncertainty. This paper had described the mechanism of connection technological innovation process of nuclear power engineering project with environmental factors, and issued a feasible method based on model of bargaining to incorporate technological innovation process management of nuclear power engineering project with environmental factors. This method has realistic meanings to guide the technological innovation of nuclear power engineering project. (authors)

Implementation digital technologies in nuclear utilities

Energy Technology Data Exchange (ETDEWEB)

Wiegand, C.; Maselli, A.J., E-mail: Tony.Maselli@Invensys.com [Invensys Operations Management, London (United Kingdom)

2012-07-01

The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

Implementation digital technologies in nuclear utilities

International Nuclear Information System (INIS)

Wiegand, C.; Maselli, A.J.

2012-01-01

The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

Nuclear Systems (NS): Technology Demonstration Unit (TDU)

Data.gov (United States)

National Aeronautics and Space Administration — The Nuclear Systems Project demonstrates nuclear power technology readiness to support the goals of NASA's Space Technology Mission Directorate. To this end, the...

Kazakhstan innovation projects in nuclear technologies field

International Nuclear Information System (INIS)

Shkol'nik, V.S.; Tukhvatulin, Sh.T.

2005-01-01

At present in the Republic of Kazakhstan in preparation and realization stage there are several innovation projects related with use of advanced nuclear technologies. Projects are as follows: 'Implementation of Kazakhstan thermonuclear reactor tokamak (KTM)'; 'Implementation at the L.N. Gumilev Eurasian National University the inter-disciplinary research complex on the heavy ions accelerator base'; 'Development of the Technological Park 'Nuclear Technologies Center in Kurchatov city'; 'Development the first in the Central-Asian region Center of Nuclear Medicine and Biophysics'. The initiator and principal operator of these projects is the National Nuclear Center of the Republic of Kazakhstan

Nuclear technology. All in good hands

International Nuclear Information System (INIS)

Mueller, Michaela

2011-01-01

Babcock Noell GmbH (BNG) has more than 40 years of practical experience and fundamental know-how in the field of nuclear technology and thus is well equipped to meet future challenges. This applies to building new nuclear power plants, upgrading and decommissioning existing facilities as well as to conditioning and storage of radioactive waste. BNG is a supplier of, among other things, components for machine technology, personnel and materials transfer locks, safety enclosures and pool liners. Outstanding, technically demanding reference projects have demonstrated BNG's capabilities. BNG is a reliable service and assembly partner to the operators of nuclear power plants and nuclear facilities. This sector of activities has as its backbone a separate team of experienced service and assembly personnel. The synergies of engineering and service competence intensively utilized by Babcock Noell GmbH are employed, inter alia, in the development and advanced development, respectively, of nuclear technology products fit for practical use, such as personnel and materials transfer locks. (orig.)

Infrasound from the 2009 and 2017 DPRK rocket launches

Science.gov (United States)

Evers, L. G.; Assink, J. D.; Smets, P. SM

2018-06-01

Supersonic rockets generate low-frequency acoustic waves, that is, infrasound, during the launch and re-entry. Infrasound is routinely observed at infrasound arrays from the International Monitoring System, in place for the verification of the Comprehensive Nuclear-Test-Ban Treaty. Association and source identification are key elements of the verification system. The moving nature of a rocket is a defining criterion in order to distinguish it from an isolated explosion. Here, it is shown how infrasound recordings can be associated, which leads to identification of the rocket. Propagation modelling is included to further constrain the source identification. Four rocket launches by the Democratic People's Republic of Korea in 2009 and 2017 are analysed in which multiple arrays detected the infrasound. Source identification in this region is important for verification purposes. It is concluded that with a passive monitoring technique such as infrasound, characteristics can be remotely obtained on sources of interest, that is, infrasonic intelligence, over 4500+ km.

Analysis on Japanese nuclear industrial technologies and their military implications

Energy Technology Data Exchange (ETDEWEB)

Kim, H. S.; Yang, M. H.; Kim, H. J. and others

2000-10-01

This study covered the following scopes : analysis of Japan's policy trend on the development and utilization of nuclear energy, international and domestic viewpoint of Japan's nuclear weapon capability, Japan's foreign affairs and international cooperation, status of Japan's nuclear technology development and its level, status and level of nuclear core technologies such as nuclear reactor and related fuel cycle technologies. Japan secures the whole spectrum of nuclear technologies including core technologies through the active implementation of nuclear policy for the peaceful uses of nuclear energy during the past five decades. Futhermore, as the result of the active cultivation of nuclear industry, Japan has most nuclear-related facilities and highly advanced nuclear industrial technologies. Therefore, it is reasonable that Japan might be recognized as one of countries having capability to get nuclear capability in several months.

Effective Methods of Nuclear Power Technology Transfer

International Nuclear Information System (INIS)

Shave, D. F.; Kent, G. F.; Giambusso, A.

1987-01-01

An effective technology transfer program is a necessary and significant step towards independence in nuclear power technology. Attaining success in the conduct of such a program is a result of a) the donor and recipient jointly understanding the fundamental concepts of the learning process, b) sharing a mutual philosophy involving a partnership relationship, c) joint and careful planning, d) rigorous adherence to proven project management techniques, and e) presence of adequate feedback to assure continuing success as the program proceeds. Several years ago, KEPCO President Park, Jung-KI presented a paper on technology in which he stated, 'Nuclear technology is an integration of many unit disciplines, and thus requires extensive investment and training in order to establish the base for efficient absorption of transferred technology.' This paper addresses President Park's observations by discussing the philosophy, approach, and mechanisms that are necessary to support an efficient and effective process of nuclear power technology transfer. All technical content and presentation methods discussed are based on a technology transfer program developed by Stone and Webster, as an Engineer/Constructor for nuclear power plants, and are designed and implemented to promote the primary program goal - the ability of the trainees and the organization to perform specific nuclear power related multi-discipline function independently and competitively

International nuclear technology transfer

International Nuclear Information System (INIS)

Cartwright, P.; Rocchio, J.P.

1978-01-01

Light water reactors (LWRs), originally developed in the United States, became the nuclear workhorses for utilities in Europe and Japan largely because the U.S. industry was willing and able to transfer its nuclear know-how abroad. In this international effort, the industry had the encouragement and support of the U.S. governement. In the case of the boiling water reactor (BWR) the program for technology transfer was developed in response to overseas customer demands for support in building local designs and manufacturing capabilities. The principal vehicles have been technology exchange agreements through which complete engineering and manufacturing information is furnished covering BWR systems and fuel. Agreements are held with companies in Germany, Japan, Italy, and Sweden. In recent years, a comprehensive program of joint technology development with overseas manufacturers has begun. The rapidly escalating cost of nuclear research and development make it desirable to minimize duplication of effort. These joint programs provide a mechanism for two or more parties jointly to plan a development program, assign work tasks among themselves, and exchange test results. Despite a slower-than-hoped-for start, nuclear power today is playing a significant role in the economic growth of some developing countries, and can continue to do so. Roughly half of the 23 free world nations that have adopted LWRs are developing countries

Chemistry and nuclear technology

International Nuclear Information System (INIS)

De Wet, W.J.

1977-01-01

The underlying principles of nuclear sciece and technology as based on the two basic phenomena, namely, radioactivity and nuclear reactions, with their relatively large associated energy changes, are outlined. The most important contributions by chemists in the overall historical development are mentioned and the strong position chemistry has attained in these fields is indicated. It is concluded that chemistry as well as many other scientific discplines (apart from general benefits) have largely benefitted from these nuclear developments [af

Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

International Nuclear Information System (INIS)

Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

2002-02-01

The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

Technology in the policy process - controlling nuclear power

International Nuclear Information System (INIS)

Collingridge, D.

1983-01-01

The discussion in this book is built around nuclear power. The technology of nuclear power is shown to have features which make it inflexible in the sense that, once built, it is difficult and expensive to control. If inflexible technology is to be avoided, it is crucially important to be able to identify this failing at an early stage in the technology's development, before it has acquired an immunity to political control. Again, this problem is approached through the example of nuclear power, in particular the breeder reactor. The breeder is shown to be even less flexible than today's nuclear technology, because it will have higher capital costs, be of greater capital intensity, longer lead time, larger unit size, and will require more infrastructure for its operation. If this is developed, the breeder will be even less open to political control than the nuclear plant of the present. To put it another way, its planning will be even more open to errors and whatever errors are made will be even more costly than for existing nuclear technology. It is therefore even less of a socially and economically acceptable technology than today's nuclear power. (author)

Advanced technology for nuclear powerplants

International Nuclear Information System (INIS)

Rohm, H.H.

1987-01-01

Advanced technology offers significant potential benefit to the nuclear industry. Improvements can be anticipated in plant performance, reliability, and overall plant safety as well as reduced life cycle costs. Utilizing artificial intelligence and expert systems, robotics, advanced instruments and controls, and modularization technologies can enhance plant operations and provide new insights and perspectives to plant risk and thus focus resources to areas of importance. Plant reliability, operability, availability, accident interdiction and limitation, and plant recovery are expected to improve. However, utilizing these technologies is not an automatic process. In addition to the actual costs associated with developing and implementing the technologies, operator training and acceptance represents a potential significant problem. Traditional plant operators have little or no experience with computer technology. There has already been some difficulty getting nuclear plant operators to accept and use the new technologies that have been implemented to accept and use the new technologies that have been implemented thus far

LOX/Methane Regeneratively-Cooled Rocket Engine Development

Data.gov (United States)

National Aeronautics and Space Administration — The purpose of this project is to advance the technologies required to build a subcritical regeneratively cooled liquid oxygen/methane rocket combustion chamber for...

Impact of Nuclear Technology to the National Socio-Economy: Technical Support by Nuclear Malaysia

International Nuclear Information System (INIS)

Hazmimi Kasim; Ainul Hayati Daud; Jamal Khaer Ibrahim; Alawiah Musa

2011-01-01

In Malaysia, the development of nuclear technology began in the year 1972. More than 30 years of application, today, the technology made impact to the national socio-economy through contribution to GDP and; improving quality of life and enhanced societal well-being. The application of nuclear technology both in public and private agencies in industrial, medical and agricultural sectors were considered. In 2008, the impact of nuclear technology shows the contribution of 0.032% to the total GDP. Industry sector shows an increasing trend and is the highest contributor, while agriculture sector remains the lowest. In this regard, Malaysian Nuclear Agency (Nuclear Malaysia) played an important role as a technical support agency in nuclear technology, as a supplier and provider for the service, training and research for the industrial, medical and agricultural sectors. (author)

Where is high technology taking nuclear medicine

International Nuclear Information System (INIS)

Veall, N.

1985-01-01

The question is posed as to whether high technology in nuclear medicine might lead to the nuclear medicine practitioner possibly finishing up working for the machine rather than the improvement of health care in its widest sense. A brief examination of some pros and cons of high technology nuclear medicine is given. (U.K.)

Impact of rocket propulsion technology on the radiation risk in missions to Mars

Energy Technology Data Exchange (ETDEWEB)

Durante, M. [GSI Helmholtzzentrum fur Schwerionenforschung, Biophysics Department, Darmstadt (Germany); Technical University of Darmstadt, Department of Condensed Matter Physics, Darmstadt (Germany); Bruno, C. [Dipartimento di Meccanica e Aeronautica, Universita -La Sapienza-, Roma (Italy)

2010-10-15

Exposure to cosmic radiation is today acknowledged as a major obstacle to human missions to Mars. In fact, in addition to the poor knowledge on the late effects of heavy ions in the cosmic rays, simple countermeasures are apparently not available. Shielding is indeed very problematic in space, because of mass problems and the high-energy of the cosmic rays, and radio-protective drugs or dietary supplements are not effective. However, the simplest countermeasure for reducing radiation risk is to shorten the duration time, particularly the transit time to Mars, where the dose rate is higher than on the planet surface. Here we show that using nuclear electric propulsion (NEP) rockets, the transit time could be substantially reduced to a point where radiation risk could be considered acceptable even with the current uncertainty on late effects. (authors)

Nuclear power flies high

International Nuclear Information System (INIS)

Friedman, S.T.

1983-01-01

Nuclear power in aircraft, rockets and satellites is discussed. No nuclear-powered rockets or aircraft have ever flown, but ground tests were successful. Nuclear reactors are used in the Soviet Cosmos serles of satellites, but only one American satellite, the SNAP-10A, contained a reactor. Radioisotope thermoelectric generators, many of which use plutonium 238, have powered more than 20 satellites launched into deep space by the U.S.A

Air-Powered Rockets.

Science.gov (United States)

Rodriguez, Charley; Raynovic, Jim

This document describes methods for designing and building two types of rockets--rockets from paper and rockets from bottles. Devices used for measuring the heights that the rockets obtain are also discussed. (KHR)

Performance Criteria of Nuclear Space Propulsion Systems

Science.gov (United States)

Shepherd, L. R.

Future exploration of the solar system on a major scale will require propulsion systems capable of performance far greater than is achievable with the present generation of rocket engines using chemical propellants. Viable missions going deeper into interstellar space will be even more demanding. Propulsion systems based on nuclear energy sources, fission or (eventually) fusion offer the best prospect for meeting the requirements. The most obvious gain coming from the application of nuclear reactions is the possibility, at least in principle, of obtaining specific impulses a thousandfold greater than can be achieved in chemically energised rockets. However, practical considerations preclude the possibility of exploiting the full potential of nuclear energy sources in any engines conceivable in terms of presently known technology. Achievable propulsive power is a particularly limiting factor, since this determines the acceleration that may be obtained. Conventional chemical rocket engines have specific propulsive powers (power per unit engine mass) in the order of gigawatts per tonne. One cannot envisage the possibility of approaching such a level of performance by orders of magnitude in presently conceivable nuclear propulsive systems. The time taken, under power, to reach a given terminal velocity is proportional to the square of the engine's exhaust velocity and the inverse of its specific power. An assessment of various nuclear propulsion concepts suggests that, even with the most optimistic assumptions, it could take many hundreds of years to attain the velocities necessary to reach the nearest stars. Exploration within a range of the order of a thousand AU, however, would appear to offer viable prospects, even with the low levels of specific power of presently conceivable nuclear engines.

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Hodong; Choi, Iljae

2013-04-01

The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The demonstration of pyroprocess technology which is proliferation resistance nuclear fuel cycle technology can reduce spent fuel and recycle effectively. Through this, people's trust and support on nuclear power would be obtained. Deriving the optimum nuclear fuel cycle alternative would contribute to establish a policy on back-end nuclear fuel cycle in the future, and developing the nuclear transparency-related technology would contribute to establish amendments of the ROK-U. S. Atomic Energy Agreement scheduled in 2014

China nuclear science and technology reports

International Nuclear Information System (INIS)

1987-01-01

114 abstracts of nuclear science and technology reports, which were published in 1986-1987 in China, are collected. The subjects inclucled are: nuclear physics, nuclear medicine, radiochemistry, isotopes and their applications, reactors and nuclear power plants, radioactive protection, nuclear instruments etc... They are arranged in accordance with the INIS subject categories, and a report number index is annexed

Legal aspects of the transfer of nuclear technology

International Nuclear Information System (INIS)

Sartorelli, C.

1980-03-01

The paper stresses the importance of nuclear technology transfer and describes the legal instruments for transfer of technical and scientific technology, particularly from the contractual viewpoint. A description follows of the setting-up of national joint ventures for nuclear power plant projects with emphasis on technological know-how to enable operation of plants in compliance with safety standards. The possibility is discussed of the export of nuclear technology, and finally mention is made of a proposal for a 'code of conduct' on such transfers in the framework of the United Nations, having regard to the 'London agreements' on nuclear exports. (NEA) [fr

Innovations in and by nuclear technology - review and perspectives

International Nuclear Information System (INIS)

Barthelt, K.

1984-01-01

An innovative technology like nuclear technology does not make progress by itself once it has to prove its profitability. It was a long way from technical to economic perfection which took courageous managemental descisions. Since nuclear fission was discovered, its exploitation as an energy source has been perfected. Now it is not only technically safe, reliable and ecological; it has also proved to be economically efficient as compared with the competing primary energies. As with other great innovations, the innovative force of nuclear technology is characterized by two directions: its assimilating capacity and its expanding capacity. Further issues are the so-called technological spin-off of nuclear technology and the fresh impetus nuclear technology gives to other fields. Another aspect beyond technological spin-off affecting all of our society: It was the first large technology requiring risk analyses to be carried out. Discussion broke out in public on the question: ''How safe is nuclear technology''. To sum up, the basic innovation of nuclear technology is now an important economic factor. It came just in time. It is capable of providing relief to the world's energy problems. It is up to us to use it in an intelligent way in the future despite any short-breathed complaints. (orig./HSCH) [de

Development of nuclear fuel cycle technology

International Nuclear Information System (INIS)

Kawahara, Akira; Sugimoto, Yoshikazu; Shibata, Satoshi; Ikeda, Takashi; Suzuki, Kazumichi; Miki, Atsushi.

1990-01-01

In order to establish the stable supply of nuclear fuel as an important energy source, Hitachi ltd. has advanced the technical development aiming at the heightening of reliability, the increase of capacity, upgrading and the heightening of performance of the facilities related to nuclear fuel cycle. As for fuel reprocessing, Japan Nuclear Fuel Service Ltd. is promoting the construction of a commercial fuel reprocessing plant which is the first in Japan. The verification of the process performance, the ensuring of high reliability accompanying large capacity and the technical development for recovering effective resources from spent fuel are advanced. Moreover, as for uranium enrichment, Laser Enrichment Technology Research Association was founded mainly by electric power companies, and the development of the next generation enrichment technology using laser is promoted. The development of spent fuel reprocessing technology, the development of the basic technology of atomic process laser enrichment and so on are reported. In addition to the above technologies recently developed by Hitachi Ltd., the technology of reducing harm and solidification of radioactive wastes, the molecular process laser enrichment and others are developed. (K.I.)

Nuclear power technologies. Abstracts of reports

International Nuclear Information System (INIS)

Koltysheva, G.I.; Mukusheva, M.K.; Perepelkin, I.G.

2000-01-01

In May 14-17, 2000, and on the initiative of the Ministry of Science and High Education of the Republic of Kazakstan with cooperation of Department of Energy US, International Seminar on Nuclear Power Technologies was held in Astana, Kazakhstan. More than 70 reports of scientists from different countries (USA, Russia, Japan and Kazakhstan) were presented during the Seminar. Representatives from different international organizations (European Commission Delegation, IAEA), from organizations of Kazakstan, Russia, USA, Japan took part in the Seminar. In all at the Seminar there were more then 100 participants. The Seminar included Plenary Session, two sections: 1) Nuclear Safety and Nuclear Technologies; 2) Material Investigations for Nuclear and Thermonuclear Power; Workshop: Nuclear Facilities Decommissioning and Decontamination; and Posters

Rocket Based Combined Cycle (RBCC) Engine

Science.gov (United States)

2004-01-01

Pictured is an artist's concept of the Rocket Based Combined Cycle (RBCC) launch. The RBCC's overall objective is to provide a technology test bed to investigate critical technologies associated with opperational usage of these engines. The program will focus on near term technologies that can be leveraged to ultimately serve as the near term basis for Two Stage to Orbit (TSTO) air breathing propulsions systems and ultimately a Single Stage To Orbit (SSTO) air breathing propulsion system.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1973-01-01

Advances in Nuclear Science and Technology, Volume 7 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of irradiation-induced void swelling in austenitic stainless steels. This text then examines the importance of various transport processes for fission product redistribution, which depends on the diffusion data, the vaporization properties, and the solubility in the fuel matrix. Other chapters co

Progress report on nuclear science and technology in China (Vol.2). Proceedings of academic annual meeting of China Nuclear Society in 2011, No.7--Nuclear electronics and nuclear detection technology sub-volume

International Nuclear Information System (INIS)

2012-10-01

Progress report on nuclear science and technology in China (Vol. 2) includes 698 articles which are communicated on the second national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about Nuclear electronics and nuclear detection technology

Current status of Chinese nuclear power industry and technology

International Nuclear Information System (INIS)

Kim, Hyun Min; Kim, Min; Jeong, Hee Jong; Hwang, Jeong Ki; Cho, Chung Hee

1996-10-01

China has been carrying out active international cooperation aiming to be a country where is to be an economical super power and an advanced country in nuclear power technology by the year early 2000, and China also has begun to be recognized as the largest potential market for the construction of nuclear power plants(NPPs) expecting to construct more than thirty nuclear power units by the year 2020. China has advanced technology in the basic nuclear science including liquid metal breeder reactor technology, nuclear material, medium and small size power plants, and isotope production technology, and also China has complete nuclear fuel cycle technology. However, China still has low NPP technology. Therefore, it is expected that China may have complementary cooperative relationship with China, it is expected that Korea may have an access to the advanced Chinese nuclear science technology, and may have a good opportunity to explore the Chinese market actively exporting excellent Korean NPP technology, and further may have a good position to the neighboring Asian countries' NPP markets. From this perspective, general Chinese social status, major nuclear R and D activity status, and correct NPP and technology status have been analyzed in this report, and this report is expected to be a useful resource for cooperating with China in future. 10 tabs., 6 figs., 16 refs. (Author)

Briefings on nuclear technology in India

International Nuclear Information System (INIS)

Iyengar, P.K.

2009-01-01

Few scientists one knows of, have gone out of their way to educate the public-especially those involved in making policies at the government level-on what nuclear energy is all about and how it is produced. One might begin at the beginning and ask what the basic principles of scientific research are, how they are developed and what the methodology of converting science into technology is. Equally relevantly, how can one sensitise the administration, not to speak of the average citizen, in supporting science and technology. This work is divided into nine chapters. The first one discusses what science really is. The second introduces the reader to nuclear science and technology. The third progressively deals with Indian effort in developing nuclear science and the astounding amount of organisational effort involved. The fourth refers to nuclear testing, a somewhat controversial subject. The fifth addresses itself to the problem of nuclear non-proliferation, yet another controversial subject, but which Dr Iyengar deals with commendable objectivity. The last three chapters concern administrative reforms

Nuclear industry technology boomerang

International Nuclear Information System (INIS)

Scholler, R.W.

1987-01-01

The benefits to the medical, pharmaceutical, semiconductor, computer, video, bioscience, laser, defense, and numerous high-tech industries from nuclear technology development fallout are indeed numerous and increase every day. Now those industries have made further progress and improvements that, in return, benefit the nuclear industry. The clean-air and particle-free devices and enclosures needed for protection and decontamination are excellent examples

Nuclear technology for the year 2000

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

Eighteen papers and abstracts are presented under the following session headings: space nuclear power, health physics and dosimetry, nuclear design and thermal hydraulics, nuclear diagnostics, and fusion technology and plasma physics. The papers were processed separately for the data base. (DLC)

Nuclear technology for the year 2000

International Nuclear Information System (INIS)

1987-01-01

Eighteen papers and abstracts are presented under the following session headings: space nuclear power, health physics and dosimetry, nuclear design and thermal hydraulics, nuclear diagnostics, and fusion technology and plasma physics. The papers were processed separately for the data base

Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.7--Nuclear electronics and nuclear detection technology sub-volume

International Nuclear Information System (INIS)

2014-05-01

Progress report on nuclear science and technology in China (Vol. 3) includes 57 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about Nuclear electronics and nuclear detection technology sub-volume

Success in nuclear technology transfer: A Canadian perspective

International Nuclear Information System (INIS)

Lawson, D.S.; Stevens, J.E.S.; Boulton, J.

1986-10-01

Technology transfer has played a significant part in the expansion of nuclear power to many countries of the world. Canada's involvement in nuclear technology transfer spans four decades. The experience gained through technology transfer, initially to Canadian industry and then to other countries in association with the construction of CANDU nuclear power plants, forms a basis from which to assess the factors which contribute to successful technology transfer. A strong commitment from all parties, in terms of both financial and human resources, is essential to success. Detailed planning of both the scope and timing of the technology transfer program is also required together with an assessment of the impact of the introduction of nuclear power on other sectors of the economy. (author)

2012 annual meeting on nuclear technology. Workshop on 'Preservation of competence in nuclear technology'

International Nuclear Information System (INIS)

Steinwarz, Wolfgang

2012-01-01

Within the 2-day workshop on 'Preservation of Competence in Nuclear Technology,' 31 young scientists competed for the 'Competence Prize' awarded by Siempelkamp Nukleartechnik for the 14th time. They reported about their papers focusing on nuclear technology, reactor technology, innovative reactor systems, radioactive waste management, radiological protection and energy supply systems. The jury composed of Prof. J. Starflinger (Universitaet Stuttgart, IKE), Prof. M.K. Koch (Ruhr-Universitaet Bochum, LEE), and Dr. W. Steinwarz (Siempelkamp Nukleartechnik) assessed the advance compacts as well as the oral presentations. The winner of the 2012 Competence Prize is Dipl.-Ing.(M.S.) Thomas M. Fesich (University Stuttgart). Dr.-Ing. Oliver Czaikowski (Techn. University Clausthal) and Dipl.-Ing. Mario Kuschewski (Universitaet Stuttgart) won the second and third prizes. (orig.)

Nuclear energy technology transfer: the security barriers

International Nuclear Information System (INIS)

Rinne, R.L.

1975-08-01

The problems presented by security considerations to the transfer of nuclear energy technology are examined. In the case of fusion, the national security barrier associated with the laser and E-beam approaches is discussed; for fission, the international security requirements, due to the possibility of the theft or diversion of special nuclear materials or sabotage of nuclear facilities, are highlighted. The paper outlines the nuclear fuel cycle and terrorist threat, examples of security barriers, and the current approaches to transferring technology. (auth)

Science and technology as strategic way for nuclear activities

International Nuclear Information System (INIS)

Paiano, Silvestre

2000-01-01

The article brings few instructive examples on the interaction between nuclear energy and other areas of science and technology, Microelectronics, computer technology, and new materials are among the many technologies which are crucial for developing nuclear energy technology. On the other way round, nuclear energy presents also a wide range of new demands and opportunities for several areas of science and technology. The problem is that such a relationship is not well understood by the society, and to a large extent it brings about the very process of legitimating the use of nuclear energy (author)

Nuclear science and technology education and training in Indonesia

International Nuclear Information System (INIS)

Karsono

2007-01-01

Deployment of nuclear technology requires adequate nuclear infrastructure which includes governmental infrastructure, science and technology infrastructure, education and training infrastructure, and industrial infrastructure. Governmental infrastructure in nuclear, i.e. BATAN (the National Nuclear Energy Agency) and BAPETEN (the Nuclear Energy Control Agency), need adequate number of qualified manpower with general and specific knowledge of nuclear. Science and technology infrastructure is mainly contained in the R and D institutes, education and training centers, scientific academies and professional associations, and national industry. The effectiveness of this infrastructure mainly depends on the quality of the manpower, in addition to the funding and available facilities. Development of human resource needed for research, development, and utilization of nuclear technology in the country needs special attention. Since the national industry is still in its infant stage, the strategy for HRD (human resource development) in the nuclear field addresses the needs of the following: BATAN for its research and development, promotion, and training; BAPETEN for its regulatory functions and training; users of nuclear technology in industry, medicine, agriculture, research, and other areas; radiation safety officers in organizations or institutions licensed to use radioactive materials; the education sector, especially lecturers and teachers, in tertiary and secondary education. Nuclear science and technology is a multidisciplinary and a highly specialized subject. It includes areas such as nuclear and reactor physics, thermal hydraulics, chemistry, material science, radiation protection, nuclear safety, health science, and radioactive waste management. Therefore, a broad nuclear education is absolutely essential to master the wide areas of science and technology used in the nuclear domain. The universities and other institutions of higher education are the only

EPRI nuclear power plant decommissioning technology program

International Nuclear Information System (INIS)

Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

2011-01-01

The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

Laser Ignition Technology for Bi-Propellant Rocket Engine Applications

Science.gov (United States)

Thomas, Matthew E.; Bossard, John A.; Early, Jim; Trinh, Huu; Dennis, Jay; Turner, James (Technical Monitor)

2001-01-01

The fiber optically coupled laser ignition approach summarized is under consideration for use in igniting bi-propellant rocket thrust chambers. This laser ignition approach is based on a novel dual pulse format capable of effectively increasing laser generated plasma life times up to 1000 % over conventional laser ignition methods. In the dual-pulse format tinder consideration here an initial laser pulse is used to generate a small plasma kernel. A second laser pulse that effectively irradiates the plasma kernel follows this pulse. Energy transfer into the kernel is much more efficient because of its absorption characteristics thereby allowing the kernel to develop into a much more effective ignition source for subsequent combustion processes. In this research effort both single and dual-pulse formats were evaluated in a small testbed rocket thrust chamber. The rocket chamber was designed to evaluate several bipropellant combinations. Optical access to the chamber was provided through small sapphire windows. Test results from gaseous oxygen (GOx) and RP-1 propellants are presented here. Several variables were evaluated during the test program, including spark location, pulse timing, and relative pulse energy. These variables were evaluated in an effort to identify the conditions in which laser ignition of bi-propellants is feasible. Preliminary results and analysis indicate that this laser ignition approach may provide superior ignition performance relative to squib and torch igniters, while simultaneously eliminating some of the logistical issues associated with these systems. Further research focused on enhancing the system robustness, multiplexing, and window durability/cleaning and fiber optic enhancements is in progress.

Promoting the acceptance of nuclear technology

International Nuclear Information System (INIS)

Rueckl, E.

1998-01-01

Restoring the public acceptance of nuclear technology requires optimized public relations work and an enhanced interaction among the nuclear industry and schools and universities. Thinking in contexts needs to be promoted, also in order to improve knowledge of mass flows. Specific terms often mean different things to experts and to the public. This can be corrected by careful use of language and precision in public relations work. The young generation is more openminded towards technology now than it was in the seventies and eighties. This is a point of departure in winning young people also for nuclear technology. For this to happen, science education in schools needs to be improved and the appropriate courses need to be introduced. (orig.) [de

Proceedings of 8. national conference on nuclear electronic and nuclear detection technology: Pt.1

International Nuclear Information System (INIS)

1996-01-01

The 8th National Conference on Nuclear Electronics and Nuclear Detection Technology was held during 2-7, 12, 1996 in Zhuhai, Guangdong, China. 184 pieces of papers were collected in the conference proceedings. The contents of the conference proceedings are: nuclear electronics, nuclear detectors, nuclear instruments and its application, nuclear medical electronics, computer applications in nuclear sciences and technology, measurement of nuclear monitoring and nuclear explosion, radiation hardened electronics, liquid scintillation counting techniques and miscellaneous. Reported hereafter is the first part of the proceedings

2005 annual nuclear technology conference

International Nuclear Information System (INIS)

Anon.

2005-01-01

This year's Annual Nuclear Technology Conference of the Deutsches Atomforum and Kerntechnische Gesellschaft was held in Nuremberg on May 10-12, 2005. More than 1 100 participants from eighteen countries make this specialized event one of the largest international conventions in the field of the peaceful uses of nuclear power, whose attendance has steadily increased over the past few years. The first day of the conference was devoted to plenary lectures traditionally dealing mainly with political and economic problems of the use of nuclear power. The partner country of JK 2005 was Switzerland. Traditionally, the program of the three-day conference was organized in the proven format of plenary sessions on the first day, followed by technical sessions, specialized sessions, poster sessions, and special events on the following days. For the third time, the ''Nuclear Campus'' was organized which successfully made the world of nuclear technology transparent to high school and university students in lectures and an exhibition. The meeting was accompanied by a technical exhibition with meeting points of manufacturers, suppliers, and service industries. (orig.)

Nuclear technology in research and everyday life

International Nuclear Information System (INIS)

2015-12-01

The paper.. discusses the impact of nuclear technology in research and everyday life covering the following issues: miniaturization of memory devices, neutron radiography in material science, nuclear reactions in the universe, sterilization of food, medical applies, cosmetics and packaging materials using beta and gamma radiation, neutron imaging for radioactive waste analysis, microbial transformation of uranium (geobacter uraniireducens), nuclear technology knowledge preservation, spacecrafts voyager 1 and 2, future fusion power plants, prompt gamma activation analysis in archeology, radiation protection and radioecology and nuclear medicine (radiotherapy).

Serving human needs. Nuclear technologies in the marketplace

International Nuclear Information System (INIS)

Qian Jihui; Burkart, Werner

2001-01-01

Many peaceful nuclear technologies today stand firmly established. They are being widely applied and accepted around the world in such fields as health care, food production, manufacturing, electricity generation, and environmental protection. Among the IAEA's 132 Member States, interest in constructively applying the tools of nuclear science and technology - especially outside the energy sector - remains high, although priorities, needs, and policies have changed over time. For the IAEA - whose specific mandate is to 'accelerate and enlarge the contribution of atomic energy to peace, health, and prosperity' - the changing and challenging global picture has strengthened efforts to enhance the contribution of nuclear science and technologies in key fields of human development. A multi-faceted programme of technical cooperation serves as the main vehicle for the transfer of nuclear science and technology to developing countries. The programme's emphasis is on supporting projects that respond to the priority needs of each country, produce an economic or social impact, and reflect the distinct advantages of nuclear technology over other approaches

Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

International Nuclear Information System (INIS)

Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

2003-08-01

The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. The aims of seminar is to exchange and disseminate information about Safety and Nuclear Power Plant Technology and Nuclear Facilities consist of Technology High Temperature Reactor and Application for National Development Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

Nuclear technology international 1987

International Nuclear Information System (INIS)

Geary, Neville

1987-01-01

A total of 59 articles cover a wide range of subjects within the scope of nuclear power generation. The first 13 are concerned with the design and construction of nuclear reactors - PWRs, AGRs, Magnox reactors, fast reactors. The final article in this section is on reactor decommissioning. The next 33 papers all concern services to the nuclear power industry. These include the supply of uranium, uranium enrichment, fuel fabrication, reprocessing, spent fuel storage, robotics and remote handling and radioactive waste disposal. The 13 articles in the safety and public acceptability section concern fears over the Chernobyl accident, safety aspects of nuclear power including risk assessment, fire protection, quality assurance, earthquake tolerance, non-proliferation of nuclear weapons and finally, general problems of balancing advances in nuclear technology and economic desirability against a lack of public confidence in the industry. All reactor and fuel types are represented. Most of the articles concern nuclear power in Europe or North America. All are indexed separately. (UK)

A study on the international nuclear Co-operation and the nuclear technology self-reliance strategy

International Nuclear Information System (INIS)

Kim, Hwa Sup

1993-02-01

To setup a basement for the national nuclear technology strategy, the reorganization of the world structure and the environmental issues are analyzed. And with regards to the self-reliance of nuclear technology, the method for the settlement of the national nuclear infrastructure and the method to strengthen our role in international nuclear community through the co-operation with IAEA is suggested. Also the status and strategy of major nuclear pushing countries are investigated. And followed by this, national nuclear technology status and strategy are analyzed. (Author)

Gas core nuclear thermal rocket engine research and development in the former USSR

International Nuclear Information System (INIS)

Koehlinger, M.W.; Bennett, R.G.; Motloch, C.G.; Gurfink, M.M.

1992-09-01

Beginning in 1957 and continuing into the mid 1970s, the USSR conducted an extensive investigation into the use of both solid and gas core nuclear thermal rocket engines for space missions. During this time the scientific and engineering. problems associated with the development of a solid core engine were resolved. At the same time research was undertaken on a gas core engine, and some of the basic engineering problems associated with the concept were investigated. At the conclusion of the program, the basic principles of the solid core concept were established. However, a prototype solid core engine was not built because no established mission required such an engine. For the gas core concept, some of the basic physical processes involved were studied both theoretically and experimentally. However, no simple method of conducting proof-of-principle tests in a neutron flux was devised. This report focuses primarily on the development of the. gas core concept in the former USSR. A variety of gas core engine system parameters and designs are presented, along with a summary discussion of the basic physical principles and limitations involved in their design. The parallel development of the solid core concept is briefly described to provide an overall perspective of the magnitude of the nuclear thermal propulsion program and a technical comparison with the gas core concept

Review of fuel element development for nuclear rocket engines

International Nuclear Information System (INIS)

Taub, J.M.

1975-06-01

The Los Alamos Scientific Laboratory (LASL) entered the nuclear propulsion field in 1955 and began work on all aspects of a nuclear propulsion program involving uranium-loaded graphite fuels, hydrogen propellant, and a target exhaust temperature of approximately 2500 0 C. A very extensive uranium-loaded graphite fuel element technology evolved from the program. Selection and composition of raw materials for the extrusion mix had to be coupled with heat treatment studies to give optimum element properties. The highly enriched uranium in the element was incorporated as UO 2 , pyrocarbon-coated UC 2 , or solid solution UC . ZrC particles. An extensive development program resulted in successful NbC or ZrC coatings on elements to withstand hydrogen corrosion at elevated temperatures. Hot gas, thermal shock, thermal stress, and NDT evaluation procedures were developed to monitor progress in preparation of elements with optimum properties. Final evaluation was made in reactor tests at NRDS. Aerojet-General, Westinghouse Astronuclear Laboratory, and the Oak Ridge Y-12 Plant of Union Carbide Nuclear Company entered the program in the early 1960's, and their activities paralleled those of LASL in fuel element development. (U.S.)

ISO: international standards development for nuclear technology

International Nuclear Information System (INIS)

Becker, K.

1981-01-01

The importance of internationally recognized standards for nuclear technology and safety is rapidly increasing for technical as well as economical and political reasons such as public acceptance and nuclear technology transfer to developing countries. The need for such standards is also evident because of the large number of nuclear installations sited close to international borders, and the export of nuclear installations from relatively few supplier countries to a large number of user countries. It is the purpose of this report to describe briefly the history, organizational structures and procedures, goals, accomplishments, problems, and future needs of the relevant activities of the International Organization for Standardization (ISO). ISO is composed of the partly governmental, partly non-governmental national standards bodies of 86 countries including China. The work of its Technical Committee (TC) 85 'Nuclear Energy' is mostly concerned with industrial applications, contractual aspects and international communication, for the benefit of both developed and developing countries. It works in close liaison with IAEA, which develops Codes and Guides addressed mainly to the regulatory aspects of nuclear power plants in developing countries. ISO/TC 85 has four sub-committees dealing with: (a) Terminology, Definitions, Units and Symbols (Secretariat USA, four working groups (WGs)); (b) Radiation Protection (Secretariat France, ten WGs); (c) Power Reactor Technology (Secretariat Sweden, nine WGs); (d) Nuclear Fuel Technology (Secretariat F.R. Germany, seven WGs). (author)

Advanced Vortex Hybrid Rocket Engine (AVHRE), Phase I

Data.gov (United States)

National Aeronautics and Space Administration — Orbital Technologies Corporation (ORBITEC) proposes to develop a unique Advanced Vortex Hybrid Rocket Engine (AVHRE) to achieve a highly-reliable, low-cost and...

Preliminary nuclear power reactor technology qualitative assessment for Malaysia

International Nuclear Information System (INIS)

Shamsul Amri Sulaiman

2011-01-01

Since the worlds first nuclear reactor major breakthrough in December 02, 1942, the nuclear power industry has undergone tremendous development and evolution for more than half a century. After surpassing moratorium of nuclear power plant construction caused by catastrophic accidents at Three-mile island (1979) and Chernobyl (1986), today, nuclear energy is back on the policy agendas of many countries, both developed and developing, signaling nuclear revival or nuclear renaissance. Selection of suitable nuclear power technology has thus been subjected to primary attention. This short paper attempts to draw preliminary technology assessment for the first nuclear power reactor technology for Malaysia. Methodology employed is qualitative analysis collating recent finding of tnb-kepco preliminary feasibility study for nuclear power program in peninsular malaysia and other published presentations and/or papers by multiple experts. The results suggested that pressurized water reactor (PWR) is the prevailing technology in terms of numbers and plant performances, and while the commercialization of generation IV reactors is remote (e.g. Not until 2030), generation III/ III+ NPP models are commercially available on the market today. Five (5) major steps involved in reactor technology selection were introduced with a focus on introducing important aspects of selection criteria. Three (3) categories for the of reactor technology selection were used for the cursory evaluation. The outcome of these analyses shall lead to deeper and full analyses of the recommended reactor technologies for a comprehensive feasibility study in the near future. Recommendations for reactor technology option were also provided for both strategic and technical recommendations. The paper shall also implore the best way to select systematically the first civilian nuclear power reactor. (Author)

Fuzzy Logic and Intelligent Technologies in Nuclear Science

International Nuclear Information System (INIS)

Da Ruan

1998-01-01

FLINS is the acronym for Fuzzy Logic and Intelligent Technologies in Nuclear Science. The main task for FLINS is to solve intricate problems pertaining to the nuclear environment by using modern technologies as additional tools and to bridge the gap between novel technologies and the industrial nuclear world. In 1997, major efforts went to the specific prototyping of Fuzzy Logic Control of SCK-CEN's BR1 research Reactor. Progress and achievements are reported

Towards a nuclear energy technology roadmap. A new service to the nuclear community

International Nuclear Information System (INIS)

Van Den Durpel, Luc; Thomas, Chris Creighton

2005-01-01

The role of nuclear energy in a future sustainable energy mix has been the subject of debates over the past few years. The future for nuclear energy will not only depend on this energy market development and the socio-political environment, but also on the innovation potential of the nuclear community to cope with the ever shorter business cycles in the energy market and the inherently longer term horizon needed in developing nuclear energy at its potential. Today's nuclear R and D community is in a transition phase, i.e. from former 'national' R and D-organisational structure to a truly international research area based on partnerships between organisations and companies creating networks-of-excellence. Several studies in the recent past have indicated the need for a shared vision in guiding this process. Identification of shared R and D-programmes, mergers and acquisitions of organizations and companies, knowledge gap analysis and the strategic mapping for each organization or company active in this nuclear R and D community. Technology Roadmapping is the appropriate tool to respond to these needs. Several stand-alone nuclear roadmap activities have been undertaken but lacked the possibility to analyse and make use of the synergies and interactions inherent to this technology development. The development has started of a master nuclear roadmap portal covering all the roadmap and technology foresight information in one so-called master nuclear roadmap. This master nuclear roadmap is implemented in an electronic online format allowing easy access, easy updating and lots of functionalities which may not be offered by traditional snap-shot roadmap reports. The paper will bring an overview on the role that technology roadmapping is playing in various industry sectors and the added value it may bring in the nuclear technology sector on a organizational as well as technology sector level. The paper will highlight the current status of this new initiative. (author)

Nuclear power strategy: requirements for technology

International Nuclear Information System (INIS)

Orlov, V.V.; Rachkov, V.I.

2001-01-01

The possible role of nuclear power in sustainable development demands answers to at least three questions: Is large-scale nuclear power essential to future development? - Is it feasible to have modern nuclear power transformed for large-scale deployment? - When will large-scale nuclear power be practically needed? The questions are analysed with the requirements to be fulfilled concerning present-day technologies

Nuclear technology and the export control laws

International Nuclear Information System (INIS)

Munroe, J.L.; Pankratz, M.C.; Hogsett, V.H.; Lundy, A.S.

1988-01-01

Three basic US laws regulate the export of commodities, services, and technical data. People working in nuclear fields need to know of these laws and their impact on professional endeavors. Export of technical data means the communication of any information by oral, written, or any other means to foreign nationals within or outside the US. The medium for the communication may be a model, blueprint, sketch, or any other device that can convey information. If the data relates to items on one of the control lists, a license must be sought from the appropriated federal agency. The Militarily Critical Technologies List (MCTL), though not itself a control list, plays a major role in determining what technical data will require a validated license. The US Department of Energy (DOE), through Technical Working Gorup (TWG) 11, is responsible for the Nuclear Technology chapter of the MCTL. TWG 11 also prepares the Nuclear Technology Reference Book (NTRB), a classified guide to sensitive nuclear technology

Prospective of the nuclear energy, technological tendency

International Nuclear Information System (INIS)

Cruz F, G. De la; Salaices A, M.

2004-01-01

The world's concern about the energy supply in the near future, has had as an answer diverse proposals in which two multinational initiatives are highlighted, that of the International Project on Nuclear Innovative Reactors and Fuel Cycles (INPRO) and that of the Generation-l V International Forum (GIF). Both initiatives direct their efforts to the development of new technologies in nuclear energy that would satisfy the energy requirements of the future. In this article, an analysis based on a) the available information on these technologies, b) a joint study (IEA/OECD/IAEA) on the new technologies regarding its capacity to confront the current challenges of the nuclear energy, and c) the authors' experience and knowledge about the phenomenology, design and security of nuclear facilities, is presented. Moreover, the technologies that, in the authors' opinion, will have the better possibilities to compete successfully in the energy markets and could be one of the viable options to satisfy the energy demands of the future, are described. (Author)

Paraffin-based hybrid rocket engines applications: A review and a market perspective

Science.gov (United States)

Mazzetti, Alessandro; Merotto, Laura; Pinarello, Giordano

2016-09-01

Hybrid propulsion technology for aerospace applications has received growing attention in recent years due to its important advantages over competitive solutions. Hybrid rocket engines have a great potential for several aeronautics and aerospace applications because of their safety, reliability, low cost and high performance. As a consequence, this propulsion technology is feasible for a number of innovative missions, including space tourism. On the other hand, hybrid rocket propulsion's main drawback, i.e. the difficulty in reaching high regression rate values using standard fuels, has so far limited the maturity level of this technology. The complex physico-chemical processes involved in hybrid rocket engines combustion are of major importance for engine performance prediction and control. Therefore, further investigation is ongoing in order to achieve a more complete understanding of such phenomena. It is well known that one of the most promising solutions for overcoming hybrid rocket engines performance limits is the use of liquefying fuels. Such fuels can lead to notably increased solid fuel regression rate due to the so-called "entrainment phenomenon". Among liquefying fuels, paraffin-based formulations have great potentials as solid fuels due to their low cost, availability (as they can be derived from industrial waste), low environmental impact and high performance. Despite the vast amount of literature available on this subject, a precise focus on market potential of paraffins for hybrid propulsion aerospace applications is lacking. In this work a review of hybrid rocket engines state of the art was performed, together with a detailed analysis of the possible applications of such a technology. A market study was carried out in order to define the near-future foreseeable development needs for hybrid technology application to the aforementioned missions. Paraffin-based fuels are taken into account as the most promising segment for market development

Annual meeting on nuclear technology '92. Technical session 'Nuclear energy discussion'

International Nuclear Information System (INIS)

1992-05-01

The report contains the six special papers red at the 1992 annual conference on nuclear engineering at Karlsruhe, all of which are individually retrievable from the database. They deal with the following subjects: historical development of the basic trends of technology criticism; communication problems in connection with the conveying of technical facts; psycho-sociological patterns of technology anxiety-mental infection or risk consciousness; field of tension between technology and journalism; handling of insecurities; ethical justifiability of nuclear energy use. (HSCH) [de

New Technologies for Seawater Desalination Using Nuclear Energy

International Nuclear Information System (INIS)

2015-01-01

As seawater desalination technologies are rapidly evolving and more States are opting for dual purpose integrated power plants (i.e. cogeneration), the need for advanced technologies suitable for coupling to nuclear power plants and leading to more efficient and economic nuclear desalination systems is obvious. The Coordinated Research Programme (CRP) New Technologies for Seawater Desalination using Nuclear Energy was organized in the framework of the Technical Working Group on Nuclear Desalination (TWG-ND). The TWGND was established in 2008 with the purpose of advising the IAEA Deputy Director General and promoting the exchange of technical information on national programmes in the field of seawater desalination using nuclear energy. This CRP project was conducted within the Nuclear Power Technology Development Section of the IAEA. It was launched in 2009 and completed by 2011, with research proposals received from nine Member States: Algeria, Egypt, France, India, Indonesia, Pakistan, the Syrian Arab Republic, the United Kingdom and the United States of America. The project aimed to review innovative technologies for seawater desalination which could be coupled to main types of existing nuclear power plant. Such coupling is expected to help making nuclear desalination safer and more economical, and hence more attractive for newcomer States interested in nuclear desalination. The project also aimed to collect ideas and suggestions necessary to update the IAEA desalination economic evaluation program (DEEP) software to become more robust and versatile. The specific objectives of the project were the introduction of innovative technologies and their economic viability, which could help make nuclear desalination a globally viable option for the safe and sustainable production of fresh water. The technologies under scrutiny in this CRP involve the low temperature horizontal tube multi-effect distillation, heat recovery systems using heat pipe based heat exchangers

Remote handling technology for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

1997-01-01

Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

48{sup th} Annual meeting on nuclear technology (AMNT 2017). Workshop: Preserving competence in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Steinwarz, Wolfgang

2017-10-15

On the 19{sup th} workshop ''Preserving Competence in Nuclear Technology'' 17 young scientists presented the results from their thesis work for a diploma, mastership or a PhD covering a broad spectrum of technical areas. This demonstrated again the strong engagement of the younger generation for the nuclear technology and the significant support by the involved German institutions. The jury awarded Thomas Schaefer (Helmholtz-Zentrum Dresden- Rossendorf) with the Siempelkamp Competence Price 2017.

Transfer of industry-oriented nuclear technology at NUCOR

International Nuclear Information System (INIS)

De Jesus, A.S.M.

1983-10-01

The transfer of industry-oriented nuclear technology at the Nuclear Development Corporation of South Africa (Pty) Ltd (NUCOR) is centred in a few divisions only, as most of the NUCOR's program is internally oriented. The industry-oriented activities include radiation technology, production of radioisotopes and application of nuclear techniques in solving problems of industry. The study is concerned mainly with the last of these activities. The general problem of transferring innovative technology is reviewed and a systems approach is used to analyse the transfer process at NUCOR, in terms of the organisation itself and its environment. Organisational strengths and weaknesses are identified and used as a basis to determine opportunities and threats. Possible objectives are formulated and a strategy to meet them is suggested. 'Demand-pull' as opposed to 'technology-push' is advanced as the main triggering mechanism in the transfer of industry-oriented nuclear technology. The importance of marketing this technology, as well as its commercialization, are discussed

China's nuclear technology for economy growth

Energy Technology Data Exchange (ETDEWEB)

Lu, Yanxiao [China Nuclear Information Center (China)

1998-07-01

The transfer of nuclear technology to practical applications in energy, agriculture, food, industries and others has made important contributions to the prosperity of the national economy and the improvement of living standard of Chinese people in the past 40 years. Facing the great challenges in upcoming years, sustained efforts are needed to promote industrialization, commercialization and internationalization of nuclear technology. Rapid economic growth is providing the golden opportunities for the development of nuclear technology in China. With the trends to globalization of economic development, civilian applications of nuclear technology will have to be involved in international co-operation and competitive world markets to narrow the gap between China and other developed countries in the world in the next century. (author)

The regulations of the Nuclear Technology Committee

International Nuclear Information System (INIS)

Schwarzer, W.

1984-01-01

The work of the Nuclear Technology Committee (NTC) is characterised by the key words 'safety related regulations' and 'nuclear technology'. The rationalisation effect desired from regulations and the not unlimited number of experts qualified for working out regulations, make it necessary to establish priorities. The NTC has almost exclusively worked out regulations for nuclear powerstations and mainly for light water reactors. The program defined at present seems to cover the most important areas. Future developments can be foreseen in the execution of the part of the program not yet concluded, the maintenance of the regulations and, depending on the development of nuclear technology, the greater inclusion of the HTR and possibly the expansion of the regulations to fast breeder reactors and plant of the fuel circuit. (orig./HSCH) [de

Semantic Technologies for Nuclear Knowledge Modelling and Applications

International Nuclear Information System (INIS)

Beraha, D.; Gladyshev, M.

2016-01-01

Full text: The IAEA has been engaged in working with Member States to preserve and enhance nuclear knowledge, and in supporting wide dissemination of safety related technical and technological information enhancing nuclear safety. The knowledge organization systems (ontologies, taxonomies, thesauri, etc.) provide one of the means to model and structure a given knowledge domain. The significance of knowledge organization systems (KOS) has been greatly enhanced by the evolution of the semantic technologies, enabling machines to “understand” the concepts described in a KOS, and to use them in a variety of applications. Over recent years semantic technologies have emerged as efficient means to improve access to information and knowledge. The Semantic Web Standards play an important role in creating an infrastructure of interoperable data sources based on principles of Linked Data. The status of utilizing semantic technologies in the nuclear domain is shortly reviewed, noting that such technologies are in their early stage of adoption, and considering some aspects which are specific to nuclear knowledge management. Several areas are described where semantic technologies are already deployed, and other areas are indicated where applications based on semantic technologies will have a strong impact on nuclear knowledge management in the near future. (author

Technology Road-map - Nuclear Energy. 2015 edition

International Nuclear Information System (INIS)

Houssin, Didier; Dujardin, Thierry; Cameron, Ron; Tam, Cecilia; Paillere, Henri; Baroni, Marco; Bromhead, Amos; Baritaud, Manual; Cometto, Marco; Gaghen, Rebecca; Herzog, Antoine; Remme, Uwe; Urso, Maria-Elena; Vance, Robert

2015-01-01

Since the release in 2010 of Technology Road-map: Nuclear Energy (IEA/NEA, 2010), a number of events have had a significant impact on the global energy sector and on the outlook for nuclear energy. They include the Fukushima Daiichi nuclear power plant (NPP) accident in March 2011, the global financial and economic crises that hit many industrialised countries during the period 2008-10 and failings in both electricity and CO 2 markets. Despite these additional challenges, nuclear energy still remains a proven low-carbon source of base-load electricity, and many countries have reaffirmed the importance of nuclear energy within their countries' energy strategies. To achieve the goal of limiting global temperature increases to just 2 deg. C by the end of the century, a halving of global energy-related emissions by 2050 will be needed. A wide range of low-carbon energy technologies will be needed to support this transition, including nuclear energy. This edition of the nuclear road-map prepared jointly by the IEA and NEA take into account recent challenges facing the development of this technology. The 2015 edition of the Nuclear Energy Technology Road-map aims to: Outline the current status of nuclear technology development and the need for additional R and D to address increased safety requirements and improved economics. Provide an updated vision of the role that nuclear energy could play in a low-carbon energy system, taking into account changes in nuclear policy in various countries, as well as the current economics of nuclear and other low-carbon electricity technologies. Identify barriers and actions needed to accelerate the development of nuclear technologies to meet the Road-map vision. Share lessons learnt and good practices in nuclear safety and regulation, front- and back-end fuel cycle practices, construction, decommissioning, financing, training, capacity building and communication. Key findings: Nuclear power is the largest source of low

Proceedings of the 7. Nuclear Science and Technology Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

The 7. conference on nuclear science and technology was held on 1-2 December 1998 in Bangkok. This conference contain papers on non-power applications of nuclear technology in medicine, agriculture and industry. These application include irradiation of food for disinfestation; tram technologies used in diagnosis and therapy and radiation chemistry important to industrial processes. Some technologies which evolved from the development of nuclear power industry are also discussed

Nuclear technology and society

International Nuclear Information System (INIS)

Suzuki, Tatsujiro; Tanaka, Yutaka; Taniguchi, Taketoshi; Oyama, Kosuke

1999-01-01

This special issue of Journal of the Atomic Energy Society of Japan deals with the relation between nuclear technology and society, and is composed of four papers: (1) Nuclear energy and international politics - sociotechnics around plutonium utilization; (2) Risk recognition and benefit recognition of nuclear facilities and social acceptance; (3) Environmental risk management and radioactive waste problem; and, (4) Public administration around the relation between nuclear energy and society. (1) describes the historical development of nuclear energy since its birth, focusing on how the leading countries tried to control nuclear proliferation. Peaceful utilization of nuclear energy is closely connected with the Non-proliferation problem. (1) also discusses the relation of plutonium utilization of Japan with international society. (2) discusses how nuclear facilities can be accepted by society, analyzing the background of risk recognition, in particular, of psychological character of mass society. (3) introduces an new approach (risk-based or risk-informed regulation) of environmental risk management for radioactive waste disposal problem, focusing on HLW (high-level waste). (4) explains the approach from public administration to nuclear energy and general energy policy and introduces PPA (participatory policy analysis) as a means for policy making. (M.M.)

Nuclear Symbiosis - A Means to Achieve Sustainable Nuclear Growth while Limiting the Spread of Sensitive Nuclear Technology

International Nuclear Information System (INIS)

Shropshire, David

2009-01-01

Global growth of nuclear energy in the 21st century is creating new challenges to limit the spread of nuclear technology without hindering adoption in countries now considering nuclear power. Independent nuclear states desire autonomy over energy choices and seek energy independence. However, this independence comes with high costs for development of new indigenous fuel cycle capabilities. Nuclear supplier states and expert groups have proposed fuel supply assurance mechanisms such as fuel take-back services, international enrichment services and fuel banks in exchange for recipient state concessions on the development of sensitive technologies. Nuclear states are slow to accept any concessions to their rights under the Non-Proliferation Treaty. To date, decisions not to develop indigenous fuel cycle capabilities have been driven primarily by economics. However, additional incentives may be required to offset a nuclear state's perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with 'symbiotic' links to indigenous economic opportunities. This paper also describes a practical tool called the 'Nuclear Materials Exchange' for identifying these opportunities.

Nuclear Symbiosis - A Means to Achieve Sustainable Nuclear Growth while Limiting the Spread of Sensititive Nuclear Technology

Energy Technology Data Exchange (ETDEWEB)

David Shropshire

2009-09-01

Global growth of nuclear energy in the 21st century is creating new challenges to limit the spread of nuclear technology without hindering adoption in countries now considering nuclear power. Independent nuclear states desire autonomy over energy choices and seek energy independence. However, this independence comes with high costs for development of new indigenous fuel cycle capabilities. Nuclear supplier states and expert groups have proposed fuel supply assurance mechanisms such as fuel take-back services, international enrichment services and fuel banks in exchange for recipient state concessions on the development of sensitive technologies. Nuclear states are slow to accept any concessions to their rights under the Non-Proliferation Treaty. To date, decisions not to develop indigenous fuel cycle capabilities have been driven primarily by economics. However, additional incentives may be required to offset a nuclear state’s perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with “symbiotic” links to indigenous economic opportunities. This paper also describes a practical tool called the “Nuclear Materials Exchange” for identifying these opportunities.

Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

International Nuclear Information System (INIS)

Hayakawa, Masahiko

1981-01-01

The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

JAERI Nuclear Engineering School and technology transfer

International Nuclear Information System (INIS)

Nishimura, Kazuaki; Kawaguchi, Chiyoji

1978-01-01

A method is introduced to evaluate the degree of nuclear technology transfer; that is, the output powers of Japanese nuclear reactors constructed in these 20 years are chronologically plotted in a semi-log figure. All reactors plotted are classified into imported and domestic ones according to a value of domestication factor. A space between two historical trajectories of reactor construction may be interpreted as one of the measures indicating the degree of nuclear technology transfer. In connection with this method, historical change of educational and training courses in Nuclear Engineering School of Japan Atomic Energy Research Institute is reviewed in this report. (author)

Nuclear power reactor technology

International Nuclear Information System (INIS)

1978-09-01

Risoe National Laboratory was established more than twenty years ago with research and development of nuclear reactor technology as its main objective. The Laboratory has by now accumulated many years of experience in a number of areas vital to nuclear reactor technology. The work and experience of, and services offered by the Laboratory within the following fields are described: Health physics site supervision; Treatment of low and medium level radioactive waste; Core performance evaluation; Transient analysis; Accident analysis; Fuel management; Fuel element design, fabrication and performance evaluation; Non-destructive testing of nuclear fuel; Theoretical and experimental structural analysis; Reliability analysis; Site evaluation. Environmental risk and hazard calculation; Review and analysis of safety documentation. Risoe has already given much assistance to the authorities, utilities and industries in such fields, carrying out work on both light and heavy water reactors. The Laboratory now offers its services to others as a consultant, in education and training of staff, in planning, in qualitative and quantitative analysis, and for the development and specification of fabrication techniques. (author)

New technologies for monitoring nuclear materials

International Nuclear Information System (INIS)

Moran, B.W.

1993-01-01

This paper describes new technologies for monitoring the continued presence of nuclear materials that are being evaluated in Oak Ridge, Tennessee, to reduce the effort, cost, and employee exposures associated with conducting nuclear material inventories. These technologies also show promise for the international safeguarding of process systems and nuclear materials in storage, including spent fuels. The identified systems are based on innovative technologies that were not developed for safeguards applications. These advanced technologies include passive and active sensor systems based on optical materials, inexpensive solid-state radiation detectors, dimensional surface characterization, and digital color imagery. The passive sensor systems use specialized scintillator materials coupled to optical-fiber technologies that not only are capable of measuring radioactive emissions but also are capable of measuring or monitoring pressure, weight, temperature, and source location. Small, durable solid-state gamma-ray detection devices, whose components are estimated to cost less than $25 per unit, can be implemented in a variety of configurations and can be adapted to enhance existing monitoring systems. Variations in detector design have produced significantly different system capabilities. Dimensional surface characterization and digital color imaging are applications of developed technologies that are capable of motion detection, item surveillance, and unique identification of items

Communicating with the public: space of nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Maffei, Patricia Martinez; Aquino, Afonso Rodrigues; Gordon, Ana Maria Pinho Leite; Oliveira, Rosana Lagua de; Padua, Rafael Vicente de; Vieira, Martha Marques Ferreira; Vicente, Roberto, E-mail: pmaffei@ipen.br, E-mail: araquino@usp.br, E-mail: amgordon@ipen.br, E-mail: rloliveira@ipen.br, E-mail: rpadua@ipen.br, E-mail: mmvieira@ipen.br, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

For two decades the Nuclear and Energy Research Institute (IPEN) has been developing activities for popularization of its R and D activities in the nuclear field. Some of the initiatives already undertaken by IPEN are lectures at schools, guided visits to IPEN facilities, printed informative material, FAQ page in the Web, and displays in annual meetings and technology fairs highlighting its achievements. In order to consolidate these initiatives, IPEN is planning to have a permanent Space of Nuclear Technology (SNT), aiming at introducing students, teachers and the general public to the current applications of nuclear technology in medicine, industry, research, electric power generation, etc. It is intended as an open room to the public and will have a permanent exhibit with historical, scientific, technical and cultural developments of nuclear technology and will also feature temporary exhibitions about specific themes. The space will display scientific material in different forms to allow conducting experiments to demonstrate some of the concepts associated with the properties of nuclear energy, hands-on programs and activities that can be customized to the students' grade level and curriculum. (author)

Communicating with the public: space of nuclear technology

International Nuclear Information System (INIS)

Maffei, Patricia Martinez; Aquino, Afonso Rodrigues; Gordon, Ana Maria Pinho Leite; Oliveira, Rosana Lagua de; Padua, Rafael Vicente de; Vieira, Martha Marques Ferreira; Vicente, Roberto

2011-01-01

For two decades the Nuclear and Energy Research Institute (IPEN) has been developing activities for popularization of its R and D activities in the nuclear field. Some of the initiatives already undertaken by IPEN are lectures at schools, guided visits to IPEN facilities, printed informative material, FAQ page in the Web, and displays in annual meetings and technology fairs highlighting its achievements. In order to consolidate these initiatives, IPEN is planning to have a permanent Space of Nuclear Technology (SNT), aiming at introducing students, teachers and the general public to the current applications of nuclear technology in medicine, industry, research, electric power generation, etc. It is intended as an open room to the public and will have a permanent exhibit with historical, scientific, technical and cultural developments of nuclear technology and will also feature temporary exhibitions about specific themes. The space will display scientific material in different forms to allow conducting experiments to demonstrate some of the concepts associated with the properties of nuclear energy, hands-on programs and activities that can be customized to the students' grade level and curriculum. (author)

Annual conference on nuclear technology. Nuclear power 2001: option for the future

International Nuclear Information System (INIS)

Anon.

2001-01-01

The Dresden Palace for Culture was the venue of the ANNUAL MEETING ON NUCLEAR TECHNOLOGY on May 15-17, 2001, the first to be held in Dresden and the first also to be held in one of the new German federal states. Although no nuclear plant is in operation in East Germany after the Greifswald Nuclear Power Station was decommissioned, nuclear technology continues to play an important role especially in research and university teaching in this part of Germany. The organizers of the conference, Deutsches Atomforum e.V. (DAtF) and Kerntechnische Gesellschaft e.V. (KTG), welcomed more than 1000 participants from nineteen countries. The three-day program, with its traditional, proven structure, featured plenary sessions on the first day, and specialized sessions, technical sessions, poster sessions, and other events on the following days. The partner country at the Annual Meeting on Nuclear Technology was Russia, with a session specially devoted to selected topics of the country. The conference was accompanied by a technical exhibition with company meeting points of vendors, suppliers, and service industries. A video film forum was arranged for the interested public which featured contributions about nuclear research, nuclear power plant operation, transport and storage as well as decommissioning. Another major event was a workshop on 'Preserving Competence in Nuclear Technology'. The plenary day is described in this summary report, while the results of the technical sessions as seen by the rapporteurs are printed elsewhere in this issue of atw 8/9, 2001. (orig.) [de

ICT based training on nuclear technology applications in Tanzania

Energy Technology Data Exchange (ETDEWEB)

Mdoe, S.L. [Nuclear Technology Applications Directorate, Tanzania Atomic Energy Commission, P.O. Box 743, Arusha (Tanzania)]. E-mail: slcmdoe@yahoo.com; Kimaro, E. [Nuclear Technology Applications Directorate, Tanzania Atomic Energy Commission, P.O. Box 743, Arusha (Tanzania)]. E-mail: taec@habari.co.tz

2006-07-01

Peaceful application of nuclear technology has contributed to socio-economic resource development in Tanzania. The Tanzania Atomic Energy Commission has taken some active steps for the incorporation and or adoption of ICT-based training modules in nuclear science and technology and its applications. The overall objective of this programme is to establish a sustainable national capability for using the potential of information communication technologies (ICTs) for training and education in the field of nuclear science and technology. This paper reviews some of the experience which the authors gained in the area of ICT based training in nuclear technology applications, it describes some of the challenges experienced, and some proposals to address the issues involved. (author)

ICT based training on nuclear technology applications in Tanzania

International Nuclear Information System (INIS)

Mdoe, S.L.; Kimaro, E.

2006-01-01

Peaceful application of nuclear technology has contributed to socio-economic resource development in Tanzania. The Tanzania Atomic Energy Commission has taken some active steps for the incorporation and or adoption of ICT-based training modules in nuclear science and technology and its applications. The overall objective of this programme is to establish a sustainable national capability for using the potential of information communication technologies (ICTs) for training and education in the field of nuclear science and technology. This paper reviews some of the experience which the authors gained in the area of ICT based training in nuclear technology applications, it describes some of the challenges experienced, and some proposals to address the issues involved. (author)

Pursuit of nuclear science and technology education

International Nuclear Information System (INIS)

Rangacharyulu, C.

2009-01-01

While it is quite encouraging to note that there is a nuclear renaissance underway around the world, there is a growing concern that the knowledge-base of nuclear technologies will be lost. Several international organizations are making concerted efforts to avert this situation by establishing collaborative workshops etc. In Western Canada, our challenges and opportunities are many-fold. As a uranium mining region, we can engage our economy in the full life-cycle of the nuclear energy industry. It is also important that we maintain and augment nuclear technologies. We need to develop the infrastructure to jump-start the education and training of the youth. We are taking a multi-prong approach to this end. We are initiating specializations in undergraduate programs which emphasize nuclear radiation physics and technology. We are collaborating with Canadian organizations such as University Network of Excellence in Nuclear Engineering (UNENE) and University of Ontario Institute of Technology (UOIT). We are organizing collaborations with our colleagues at foreign institutions in Europe and Asia to provide an international component. We are also working with local industry and health organizations to provide a wide-range of learning opportunities to students by engaging them in research projects of immediate interest to professionals. My presentation will focus on these developments and we will also seek thoughts and suggestions for future collaborations.

Expanding Nuclear Power Programmes - Romanian experience: Master - Nuclear Materials and Technologies Educational Plan

International Nuclear Information System (INIS)

Valeca, S.; Valeca, M.

2012-01-01

The main objectives of the Master Nuclear Materials and Technologies Educational Plan are: 1. To deliver higher education and training in the following specific domains, such as: Powders Technology and Ceramic Materials, Techniques of Structural Analysis, Composite Materials, Semiconductor Materials and Components, Metals and Metallic Alloys, Optoelectronic Materials and Devices, Nuclear Materials, The Engineering of Special Nuclear Materials, 2. To train managers of the Nuclear Waste Products and Nuclear Safety, 3. To qualify in ICT Systems for Nuclear Process Guidance, 4. To qualify in Environmental Protection System at the Level of Nuclear Power Stations, 5. To train managers for Quality Assurance of Nuclear Energetic Processes, 6. To deliver higher education and training regarding the International Treatises, Conventions and Settlements in force in the field of nuclear related activities. (author)

Experimental investigation of solid rocket motors for small sounding rockets

Science.gov (United States)

Suksila, Thada

2018-01-01

Experimentation and research of solid rocket motors are important subjects for aerospace engineering students. However, many institutes in Thailand rarely include experiments on solid rocket motors in research projects of aerospace engineering students, mainly because of the complexity of mixing the explosive propellants. This paper focuses on the design and construction of a solid rocket motor for total impulse in the class I-J that can be utilised as a small sounding rocket by researchers in the near future. Initially, the test stands intended for measuring the pressure in the combustion chamber and the thrust of the solid rocket motor were designed and constructed. The basic design of the propellant configuration was evaluated. Several formulas and ratios of solid propellants were compared for achieving the maximum thrust. The convenience of manufacturing and casting of the fabricated solid rocket motors were a critical consideration. The motor structural analysis such as the combustion chamber wall thickness was also discussed. Several types of nozzles were compared and evaluated for ensuring the maximum thrust of the solid rocket motors during the experiments. The theory of heat transfer analysis in the combustion chamber was discussed and compared with the experimental data.

Russian Meteorological and Geophysical Rockets of New Generation

Science.gov (United States)

Yushkov, V.; Gvozdev, Yu.; Lykov, A.; Shershakov, V.; Ivanov, V.; Pozin, A.; Afanasenkov, A.; Savenkov, Yu.; Kuznetsov, V.

2015-09-01

To study the process in the middle and upper atmosphere, ionosphere and near-Earth space, as well as to monitor the geophysical environment in Russian Federal Service for Hydrology and Environmental Monitoring (ROSHYDROMET) the development of new generation of meteorological and geophysical rockets has been completed. The modern geophysical research rocket system MR-30 was created in Research and Production Association RPA "Typhoon". The basis of the complex MR-30 is a new geophysical sounding rocket MN-300 with solid propellant, Rocket launch takes place at an angle of 70º to 90º from the launcher, which is a farm with a guide rail type required for imparting initial rotation rocket. The Rocket is spin stabilized with a spin rate between 5 and 7 Hz. Launch weight is 1564 kg, and the mass of the payload of 50 to 150 kg. MR-300 is capable of lifting up to 300 km, while the area of dispersion points for booster falling is an ellipse with parameters 37x 60 km. The payload of the rocket MN-300 consists of two sections: a sealed, located below the instrument compartment, and not sealed, under the fairing. Block of scientific equipment is formed on the platform in a modular layout. This makes it possible to solve a wide range of tasks and conduct research and testing technologies using a unique environment of space, as well as to conduct technological experiments testing and research systems and spacecraft equipment. New Russian rocket system MERA (MEteorological Rocket for Atmospheric Research) belongs to so called "dart" technique that provide lifting of small scientific payload up to altitude 100 km and descending with parachute. It was developed at Central Aerological Observatory jointly with State Unitary Enterprise Instrument Design Bureau. The booster provides a very rapid acceleration to about Mach 5. After the burning phase of the buster the dart is separated and continues ballistic flight for about 2 minutes. The dart carries the instrument payload+ parachute

International Nuclear Management Academy Requirements for University Master’s Programmes in Nuclear Technology Management

International Nuclear Information System (INIS)

Grosbois, J. de; Hirose, H.; Adachi, F.; Liu, L.; Hanamitsu, K.; Kosilov, A.; Roberts, J.

2016-01-01

Full text: The development of any national nuclear energy programme is dependent on the successful development of qualified human resources, through a sustainable nuclear education and training programmes supported by government and industry. Among the broad range of specialists needed for the continued safe and economic utilization of nuclear technology for peaceful purposes, are a most vital component—managers. The International Nuclear Management Academy (INMA) is an IAEA facilitated collaboration framework in which universities provide master’s degree programmes focusing on the management aspect for the nuclear sector. INMA master’s programmes in Nuclear Technology Management (NTM) specify a common set of competency requirements that graduates should acquire to prepare them to become competent managers. This paper presents an overview of the INMA collaboration framework and the requirements for partner universities to implement master’s programmes in Nuclear Technology Management. (author

Nuclear propulsion control and health monitoring

Science.gov (United States)

Walter, P. B.; Edwards, R. M.

1993-11-01

An integrated control and health monitoring architecture is being developed for the Pratt & Whitney XNR2000 nuclear rocket. Current work includes further development of the dynamic simulation modeling and the identification and configuration of low level controllers to give desirable performance for the various operating modes and faulted conditions. Artificial intelligence and knowledge processing technologies need to be investigated and applied in the development of an intelligent supervisory controller module for this control architecture.

Overview of Nuclear Reactor Technologies Portfolio

International Nuclear Information System (INIS)

O’Connor, Thomas J.

2012-01-01

Office of Nuclear Energy Roadmap R&D Objectives: • Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of current reactors; • Develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; • Develop sustainable nuclear fuel cycles; • Develop capabilities to reduce the risks of nuclear proliferation and terrorism

''Perspectives in nuclear technology'': recruiting young scientists and engineers

International Nuclear Information System (INIS)

Wasgindt, V.

2003-01-01

Securing competence in nuclear technology is a topic of great interest especially because the preservation and promotion of scientific and technical know-how in Germany are particularly important under conditions of an opt-out of the use of nuclear power. In the light of decreasing numbers of graduates from courses in nuclear science and technology, positive action is indicated. For the first time, the Deutsches Atomforum e.V., together with major partners in cooperation, therefore organized a colloquy last year on 'Perspectives in Nuclear Technology'. Young students of various disciplines were given an opportunity to obtain in-depth information about nuclear power as part of the entire field of energy supply by attending lectures, round-table discussions, and on-site events. Because of the positive response elicited by that first event, another 'Perspectives in Nuclear Technology' colloquy will be held in 2003. (orig.)

Spent Nuclear Fuel Alternative Technology Decision Analysis

International Nuclear Information System (INIS)

Shedrow, C.B.

1999-01-01

The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology

Consideration of ultra-high temperature nuclear heat sources for MHD conversion systems

International Nuclear Information System (INIS)

Holman, R.R.; Tobin, J.M.; Young, W.E.

1975-01-01

The nuclear technology reactors developed and tested in the Nuclear Engine Rocket Vehicle Application (NERVA) program operated with fuel exit gas temperatures in excess of 2600 K. This experience provided a significant ultra-high temperature technology base and design insight for commercial power applications. Design approaches to accommodate fission product retention and other key prevailing requirements are examined in view of the basic overriding functional requirements, and some interesting reconsiderations are suggested. Predicted overall system performance potentials for a 2000 K MHD conversion system and reactor parameter requirements are compared and related to existing technology status. Needed verification and development efforts are suggested. A reconsideration of basic design approaches is suggested that could open the door for immediate development of ultrahigh temperature nuclear heat sources for advanced energy systems

Nuclear Human Resource Development in Tokyo Institute of Technology

International Nuclear Information System (INIS)

Satio, Masaki; Igashira, Masayuki; Obara, Toru; Kikura, Hironari; Kawahara, Akira; Ujita, Hiroshi

2012-01-01

Nuclear engineering education has been initiated in 1957 at the graduate school of Tokyo Institute of Technology. Higher Educational activities have been conducted for more than half century. More than 1000 Master students and 200 Doctoral students graduated from the Department of Nuclear Engineering in Tokyo Institute if Technology. Many of them are working in nuclear industries and institutes. International course of nuclear engineering was initiated in 1994, and 130 students from 20 overseas countries have graduated from Master and Doctoral Programs. In the present paper, the current nuclear educational activities in Tokyo Institute of Technology are summarized

IEA Energy Technology Essentials: Nuclear Power

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-03-15

The IEA Energy Technology Essentials series offers concise four-page updates on the different technologies for producing, transporting and using energy. Nuclear power is the topic covered in this edition.

Physics and technology of nuclear materials

CERN Document Server

Ursu, Ioan

2015-01-01

Physics and Technology of Nuclear Materials presents basic information regarding the structure, properties, processing methods, and response to irradiation of the key materials that fission and fusion nuclear reactors have to rely upon. Organized into 12 chapters, this book begins with selectively several fundamentals of nuclear physics. Subsequent chapters focus on the nuclear materials science; nuclear fuel; structural materials; moderator materials employed to """"slow down"""" fission neutrons; and neutron highly absorbent materials that serve in reactor's power control. Other chapters exp

Study on international publicity and export strategy establishment of nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Lee, Ji Bok; Choi, C.O.; Park, K. B.; Chang, M. H.; Kim, K. K.; Yang, M. S.; Jung, I. H.; Kim, K. P.; Wu, J. S.; Jang, C. I.; Han, B. O.; Sim, J. H.; Chung, M.; Chung, J.K

1999-05-01

The objective of this study is to devise a proper measure for international publicity and technology export strategy. Analysed and summaries in detail are other countries nuclear policy trend and the current technology development status of Korea Standard Nuclear Plant that we developed on our own technology, design and construction technology for research reactor, System-integrated Modular Advanced Reactor of which design is in progress, Direct use of Spent PWR Fuel in CANDU Reactors, and Radioisotopes. Based on that, the measures are proposed for the export industrialization of nuclear technology and establishment of the export basis. Also the international nuclear cooperation and publicity strategy are suggested to support the technology export basis. By surveying the world nuclear status, the direction for the international cooperation and publicity is settled and the specific publicity strategy is proposed for the cooperation with IAEA and multi-countries and the establishment of the nuclear technology export basis. As part of this project, the panel on major technologies such as Korea Standard Nuclear Plant, HANARO, and System-integrated Modular Advanced Reactor was displayed successfully at the IAEA meeting, which contribute much to the publicity of our nuclear technology to the international nuclear society. (author)

The challenge of making nuclear technologies acceptable, accessible and affordable

International Nuclear Information System (INIS)

Ramamurthy, V.S.

2009-01-01

Full text: It is more than five decades since the first successful demonstration of nuclear power for commercial electricity production. The same decades have also seen the successful demonstration of several other applications of nuclear technologies that can contribute directly to human development, as for example, in the Food and Agriculture, Human and animal Health, Environment and Water sectors. In spite of several successful demonstrations and applications in these fields, it is somewhat strange that their full potential is yet to be realized. More importantly, their availability to populations across the world is highly skewed. Three barriers have been identified for the wide spread use of nuclear technologies for development- Acceptability, Accessibility and Affordability. It is an unfortunate twist of fate that the first public demonstration of nuclear technology was its destructive power. The following demonization of anything nuclear was further compounded by the discussions on the unresolved questions on tackling long lived radioactive wastes, our inability to arrive at a global consensus on nuclear disarmament and issues of nuclear proliferation. These have certainly had a negative impact on the public acceptance of nuclear technologies across the board. While the recent concerns on the global climate change following the emission of carbon-di-oxide from excessive hydrocarbon burning for meeting our increasing energy needs have revived the interest in nuclear energy, a lot needs to be done to de-demonize nuclear technologies in public mind leading to increased acceptance of nuclear technologies for development. Lack of resources, infrastructure and trained man power also have a negative impact on the accessibility and affordability of the nuclear technologies for development. It is argued that only education holds the key for this. The role of international partnerships is also highlighted in realizing the full potential of nuclear technologies for

Development of nuclear technology transfer - Korea as a recipient

International Nuclear Information System (INIS)

Sung, N.C.

1988-01-01

Korea, as a recipient of nuclear technology transfer, has good experience of progressively building up its indigenous capability of nuclear technology through three stages of technology transfer, namely: technology transfer under the turn-key approach, component approach, and integrated technology transfer with a local prime contractor. Here, each stage of experience of technology transfer, with Korea as a recipient, is presented

Wireless Technology Application to Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Jeong Kweon; Jeong, See Chae; Jeong, Ki Hoon; Oh, Do Young; Kim, Jae Hack

2009-01-01

Wireless technologies are getting widely used in various industrial processes for equipment condition monitoring, process measurement and other applications. In case of Nuclear Power Plant (NPP), it is required to review applicability of the wireless technologies for maintaining plant reliability, preventing equipment failure, and reducing operation and maintenance costs. Remote sensors, mobile technology and two-way radio communication may satisfy these needs. The application of the state of the art wireless technologies in NPPs has been restricted because of the vulnerability for the Electromagnetic Interference and Radio Frequency Interference (EMI/RFI) and cyber security. It is expected that the wireless technologies can be applied to the nuclear industry after resolving these issues which most of the developers and vendors are aware of. This paper presents an overview and information on general wireless deployment in nuclear facilities for future application. It also introduces typical wireless plant monitoring system application in the existing NPPs

Development of nuclear equipment qualification technology

Energy Technology Data Exchange (ETDEWEB)

Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

1999-03-01

In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

Nuclear technology review 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-08-15

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

Nuclear technology review 2004

International Nuclear Information System (INIS)

2004-08-01

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

A study on nuclear technology policy

International Nuclear Information System (INIS)

Yang, M. H.; Kim, H. J.; Chung, W. S.; Yun, S. W.; Kim, H. S.

2001-01-01

This study was carried out as a part of institutional activities of KAERI. Major research area are as follows; Future directions and effects for national nuclear R and D to be resulted from restructuring of electricity industry are studied. Comparative study was carried out between nuclear energy and other energy sources from the point of views of environmental effects by introducing life cycle assessment(LCA) method. Japanese trends of reestablishment of nuclear policy such as restructuring of nuclear administration system and long-term plan of development and use of nuclear energy are also investigated, and Russian nuclear development program and Germany trends for phase-out of nuclear electricity generation are also investigated. And trends of the demand and supply of energy in eastern asian countries in from the point of view of energy security and tension in the south china sea are analyzed and investigation of policy trends of Vietnam and Egypt for the development and use of nuclear energy for the promotion of nuclear cooperation with these countries are also carried out. Due to the lack of energy resources and high dependence of imported energy, higher priority should be placed on the use of localized energy supply technology such as nuclear power. In this connection, technological development should be strengthened positively in order to improve economy and safety of nuclear energy and proliferation resistance of nuclear fuel cycle and wide ranged use of radiation and radioisotopes and should be reflected in re-establishment of national comprehensive promotion plan of nuclear energy in progress

A study on nuclear technology policy

Energy Technology Data Exchange (ETDEWEB)

Yang, M H; Kim, H J; Chung, W S; Yun, S W; Kim, H S

2001-01-01

This study was carried out as a part of institutional activities of KAERI. Major research area are as follows; Future directions and effects for national nuclear R and D to be resulted from restructuring of electricity industry are studied. Comparative study was carried out between nuclear energy and other energy sources from the point of views of environmental effects by introducing life cycle assessment(LCA) method. Japanese trends of reestablishment of nuclear policy such as restructuring of nuclear administration system and long-term plan of development and use of nuclear energy are also investigated, and Russian nuclear development program and Germany trends for phase-out of nuclear electricity generation are also investigated. And trends of the demand and supply of energy in eastern asian countries in from the point of view of energy security and tension in the south china sea are analyzed and investigation of policy trends of Vietnam and Egypt for the development and use of nuclear energy for the promotion of nuclear cooperation with these countries are also carried out. Due to the lack of energy resources and high dependence of imported energy, higher priority should be placed on the use of localized energy supply technology such as nuclear power. In this connection, technological development should be strengthened positively in order to improve economy and safety of nuclear energy and proliferation resistance of nuclear fuel cycle and wide ranged use of radiation and radioisotopes and should be reflected in re-establishment of national comprehensive promotion plan of nuclear energy in progress.

Developing countries' motivation to use nuclear technology

International Nuclear Information System (INIS)

Ratsch, U.

1990-01-01

Governments of various developing countries see nuclear energy as an important tool for at least three political goals: Firstly, the expected rise in future energy demand, so they argue, can only be met if nuclear electricity production in the Third World is expanded. Fossil sources are supposed to become increasingly scarce and expensive, and they are also seen to be ecologically damaging. Technologies to harness renewable energy sources are not yet mature and still too costly. Secondly, nuclear technology is seen as one of the most advanced technologies. Mastering of it might help to diminish the technological gap between the First and the Third World. Thirdly, scientific progress in developing countries is hoped to be accelerated by operating research reactors in these countries. All of these arguments ought to be taken as serious motivations. (orig./HSCH) [de

20 Engineering Technologies Which Changed The World

International Nuclear Information System (INIS)

Lee, In Sik; Shin, Dong Won; Mun, Jung Yang and others

2004-07-01

This book deals with 20 engineering technologies which changed the world, these are about a, compass, papermaking, a lens, gunpowder, machine watch, printing technique, vaccine, a suspension bridge, a railroad, a loom, photograph, petroleum, automobile, electricity, wireless communications, synthetic medicine, a jet engine and a rocket, nuclear bombs, ENIAC, and polymerase chain reaction method. Each skill is introduced with history and the detailed reports by other persons.

Nuclear science and technology in Polish People's Republic

International Nuclear Information System (INIS)

Bijak, J.; Valis, L.; Vincel, G.; Goffman, P.; Deptula, C.; Krepsztul, H.; Michalik, E.; Siekierski, S.; Soltan, A.; Pomczak, M.; Chwaszczewski, S.; Szterk, L.; Szulc, P.

1979-01-01

History of development of nuclear science and technology in Poland is stated. List is given of main directions of activity of scientific establishments in the field of nuclear science and technology, as well as of directions of international co-operation. Directions are stated of fundamental researches in the field of atomic nuclear physics and elementary particles physics, and lists given of scientific research institutes engaged in these investigations. The results are presented of main works in the field of nuclear reactor physics, as well as list is given of installations being used in these investigations. Program is stated of development of nuclear energetics in Poland. The results are given of investigations in the field of processing of different types of uranium ores with low content of uranium, as well as directions are stated of works in the field of nuclear fuel technology. The results of works are stated on transuranium elements production; fission products separation; production of radionuclides and labelled compounds, in particular, for application in nuclear medicine. Description is given of directions of activity in the field of production of nuclear instrumentation and of application of isotopes and radiation in the people's economy. Main methods are given of application of isotopes and radiations in industry for control and for production of materials with new properties or for influence on the course of technological processes [ru

The flight of uncontrolled rockets

CERN Document Server

Gantmakher, F R; Dryden, H L

1964-01-01

International Series of Monographs on Aeronautics and Astronautics, Division VII, Volume 5: The Flight of Uncontrolled Rockets focuses on external ballistics of uncontrolled rockets. The book first discusses the equations of motion of rockets. The rocket as a system of changing composition; application of solidification principle to rockets; rotational motion of rockets; and equations of motion of the center of mass of rockets are described. The text looks at the calculation of trajectory of rockets and the fundamentals of rocket dispersion. The selection further focuses on the dispersion of f

Nuclear technology and Latin America

International Nuclear Information System (INIS)

Raja Mohan, C.

1980-01-01

Developments in nuclear technology in Latin American countries, particularly in Argentina and Brazil, have been surveyed. In their efforts to acquire self-reliance in the nuclear field independently i.e. without seeking help from U.S.A., Argentina and Brazil came to accept stringent foreign controls on their nuclear programmes which envisage having a complete nuclear fuel cycle. Their struggle against the discriminatory nature of the NPT has become more or less theoretical. Moreover, the Latin American countries have signed the Tlatelolco treaty which prohibits testing, use, manufacture or acquisition of nuclear weapons. An encouraging feature is, however, growing bilateral and multilateral cooperation in the nuclear energy sector. It is illustrated by citing the example of the Argentina-Brazil nuclear cooperation agreement. The political significance of this development for the third world is discussed. (M.G.B.)

A project in support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho [and others

2005-12-15

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.

A project in support of Nuclear Technology Cooperation

International Nuclear Information System (INIS)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho

2005-12-01

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate

C-NET: the Centre for Nuclear Energy Technology

International Nuclear Information System (INIS)

Roberts, J.W.

2011-01-01

The Centre for Nuclear Energy Technology was established as part of the Dalton Nuclear Institute at The University of Manchester in 2009 to focus the UK research on front-end nuclear technologies. This includes plant-life extension, new build, naval propulsion and next generation reactors. Building on £4M of government funding through the North West Development Agency (NWDA), C-NET will act as a hub for nuclear research in the North West of England collaborating with both universities and industry. (author)

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1962-01-01

Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants.Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider

Graduate diplomas in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Bereznai, G. [Univ. of Ontario Inst. of Tech., Oshawa, Ontario (Canada)

2009-07-01

The University of Ontario Institute of Technology (UOIT) offers a graduate diploma program in nuclear technology that consists of a suite of six sub-specialties: Fuel, Materials and Chemistry; Reactor Systems; Operation and Maintenance; Safety, Licensing and Regulatory Affairs; Health Physics; and Radiological Applications. Four courses selected from a list that covers the knowledge and skill set of each sub-specialty have to be completed in order to gain a graduate diploma in the specific area. The program is designed to accommodate the needs of people working in the nuclear industry to upgrade their knowledge and skills, to promote career advancement and to provide a framework for lifelong learning. (author)

Nuclear technology and materials science

International Nuclear Information System (INIS)

Olander, D.R.

1992-01-01

Current and expected problems in the materials of nuclear technology are reviewed. In the fuel elements of LWRs, cladding waterside corrosion, secondary hydriding and pellet-cladding interaction may be significant impediments to extended burnup. In the fuel, fission gas release remains a key issue. Materials issues in the structural alloys of the primary system include stress-corrosion cracking of steel, corrosion of steam generator tubing and pressurized thermal shock of the reactor vessel. Prediction of core behavior in severe accidents requires basic data and models for fuel liquefaction, aerosol formation, fission product transport and core-concrete interaction. Materials questions in nuclear waste management and fusion technology are briefly reviewed. (author)

Revolution of Nuclear Power Plant Design Through Digital Technology

International Nuclear Information System (INIS)

Zhang, L.; Shi, J.; Chen, W.

2015-01-01

In the digital times, digital technology has penetrated into every industry. As the highest safety requirement standard, nuclear power industry needs digital technology more to breed high quality and efficiency. Digital power plant is derived from digital design and the digitisation of power plant transfer is an inevitable trend. This paper introduces the technical solutions and features of digital nuclear power plant construction by Shanghai Nuclear Engineering Research & Design Institute, points out the key points and technical difficulties that exist in the process of construction and can serve as references for further promoting construction of digital nuclear power plant. Digital technology is still flourishing. Although many problems will be encountered in construction, it is believed that digital technology will make nuclear power industry more safe, cost-effective and efficient. (author)

ISO standardization in nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Brabec, D [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Cermak, O [Urad pro Normalizaci a Mereni, Prague (Czechoslovakia)

1984-10-01

The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

Training at the Australian School of Nuclear Technology

International Nuclear Information System (INIS)

Culley, D.; Fredsall, J.R.; Toner, B.

1987-01-01

The Australian School of Nuclear Technology was founded in 1964 as a joint enterprise of the Australian Atomic Energy Commission and the University of New South Wales to support nuclear developments primarily in Australia. However, ASNT has developed into an important centre for nuclear science and technology training within the South East Asian Region with participants also attending from countries outside this Region. (author)

Training at the Australian School of Nuclear Technology

International Nuclear Information System (INIS)

Culley, D.; Fredsall, J.R.; Toner, B.

1987-04-01

The Australian School of Nuclear Technology (ASNT) was founded in 1964 as a joint enterprise of the Australian Atomic Energy Commission and the University of New South Wales to support nuclear developments primarily in Australia. However, ASNT has developed into an important centre for nuclear science and technology training within the South East Asian Region with participants also attending from countries outside this Region

AFRA Network for Education in Nuclear Science and Technology

International Nuclear Information System (INIS)

Hashim, O.N.; Wanjala, F.

2017-01-01

The Africa Regional Cooperative Agreement for Research Development and Training related to Science and Technology (AFRA) established the AFRA Network for Education in Nuclear Science and Technology (AFRA-NEST) in order to implement AFRA strategy on Human Resource Development (HRD) and Nuclear Knowledge Management (NKM). The strategies for implementing the objectives are: to use ICT for web-based education and training; recognition of Regional Designated Centres (RDCs) for professional nuclear education in nuclear science and technology, and organization of harmonized and accredited programs at tertiary levels and awarding of fellowships/scholarships to young and brilliant students for teaching and research in the various nuclear disciplines

Nuclear technology for a sustainable future

International Nuclear Information System (INIS)

2012-06-01

The IAEA helps its Member States to use nuclear technology for a broad range of applications, from generating electricity to increasing food production, from fighting cancer to managing fresh water resources and protecting the world's seas and oceans. Despite the Fukushima Daiichi accident in March 2011, nuclear power will remain an important option for many countries. Use of nuclear power will continue to grow in the next few decades, although growth will be slower than was anticipated before the accident. The factors contributing to the continuing interest in nuclear power include increasing global demand for energy, as well as concerns about climate change, volatile fossil fuel prices and security of energy supply. It will be difficult for the world to achieve the twin goals of ensuring sustainable energy supplies and curbing greenhouse gases without nuclear power. It is up to each country to choose its optimal energy mix. The IAEA helps countries which opt for nuclear power to use it safely and securely. Every day, millions of people throughout the world benefit from the use of nuclear technology. The IAEA helps to make these benefits available to developing countries through its extensive Technical Cooperation programme. For instance, we provide assistance in areas such as human health (through our Programme of Action for Cancer Therapy), animal health (we were active partners in the successful global campaign to eradicate the deadly cattle disease rinderpest), food, water and the environment. The IAEA contributes to the development of global policies to address the energy, food, water and environmental challenges the world faces. We look forward to helping to make Rio+20 a success. This brochure provides an overview of the many ways in which nuclear technology is contributing to building the future we want.

Role of high technology in the nuclear industry

International Nuclear Information System (INIS)

Cain, D.G.

1986-01-01

A discussion of high technology identifies the characteristics which distinguish it from conventional technologies, and the impact high technology will have in the nuclear power industry in the near future. The basic theme is that high technology is an ensemble of competing technological developments that shifts with time and technological innovation. The attributes which current distinguish high technology are compactness, plasticity, convergence, and intelligence. These high technology attributes are presented as a prelude to some examples of high technology developments which are just beginning to penetrate the nuclear industry. Concluding remarks address some of the challenges which must be faced in order to assure that high technology is successfully adapted and used

Spent Nuclear Fuel Alternative Technology Decision Analysis

Energy Technology Data Exchange (ETDEWEB)

Shedrow, C.B.

1999-11-29

The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

Changing relations between civil and military nuclear technology

International Nuclear Information System (INIS)

Walker, W.B.

1999-01-01

Nuclear energy has inhabited two distinct environments since its inception - the environments of nuclear deterrence and of electricity supply. The relationships between the technologies and institutions inhabiting these environments have been both intimate and troublesome. As both nuclear weapons and nuclear power rely upon the fission energy of uranium and plutonium, and as both generate harmful by-products, they are bound to have technologies, materials and liabilities in common. However, nuclear deterrence belongs in the realm of high politics, whilst electricity production is part of the commercial world rooted in civil society. Establishing a political, industrial and regulatory framework that allows nuclear activities to develop safely and acceptably in both domains has been a difficult and contentious task. In this paper I wish to make some observations about the relations between military and civil nuclear technology at the end of this century, and about their likely character in years ahead. My main contention is that developments in the military sector and in international security will remain influential, but that their consequences will be of a different kind than in the past. (orig.)

Lessons from half a century experience of Japanese solid rocketry since Pencil rocket

Science.gov (United States)

Matogawa, Yasunori

2007-12-01

50 years have passed since a tiny rocket "Pencil" was launched horizontally at Kokubunji near Tokyo in 1955. Though there existed high level of rocket technology in Japan before the end of the second World War, it was not succeeded by the country after the War. Pencil therefore was the substantial start of Japanese rocketry that opened the way to the present stage. In the meantime, a rocket group of the University of Tokyo contributed to the International Geophysical Year in 1957-1958 by developing bigger rockets, and in 1970, the group succeeded in injecting first Japanese satellite OHSUMI into earth orbit. It was just before the launch of OHSUMI that Japan had built up the double feature system of science and applications in space efforts. The former has been pursued by ISAS (the Institute of Space and Astronautical Science) of the University of Tokyo, and the latter by NASDA (National Space Development Agency). This unique system worked quite efficiently because space activities in scientific and applicational areas could develop rather independently without affecting each other. Thus Japan's space science ran up rapidly to the international stage under the support of solid propellant rocket technology, and, after a 20 year technological introduction period from the US, a big liquid propellant launch vehicle, H-II, at last was developed on the basis of Japan's own technology in the early 1990's. On October 1, 2003, as a part of Governmental Reform, three Japanese space agencies were consolidated into a single agency, JAXA (Japan Aerospace Exploration Agency), and Japan's space efforts began to walk toward the future in a globally coordinated fashion, including aeronautics, astronautics, space science, satellite technology, etc., at the same time. This paper surveys the history of Japanese rocketry briefly, and draws out the lessons from it to make a new history of Japan's space efforts more meaningful.

Nuclear technology review 2002

International Nuclear Information System (INIS)

2002-08-01

The unifying theme of the Nuclear Technology Review 2002 (NTR-2002) is the importance of innovation. Innovation makes it possible to step beyond incremental evolutionary improvements constrained by diminishing returns. For crop production and public health, for example, the sterile insect technique created a whole new path for future improvements, distinctly different from applying ever larger amounts of pesticides. Nuclear techniques offer a new and safer approach to removing the world's estimated 60,000,000 abandoned land mines. New precision techniques create the potential for ever less intrusive and more effective radiation treatments for cancer. For nuclear power continuing innovation will be a key factor in closing the projection gap between long term global energy scenarios in which nuclear power expands substantially and near term scenarios with only modest expansion or even decline. While the NTR-2002 presents a worldwide review of the state-of-the-art of nuclear science and technology, and not an annual report on IAEA activities, it notes areas where the Agency has a particularly important role to play. Part I of the NTR-2002 'Fundamentals of Nuclear Development', reviews developments in the field of nuclear, atomic and molecular data. Research reactors remain essential to progress in nuclear science and technology. Part I reviews advances in radioisotope production, the use of accelerators and neutron activation analysis relevant to applications ranging from medicine particularly the light against cancer to industry. Part I also reviews developments in nuclear instrumentation and nuclear fusion, particularly in connection with the International Thermonuclear Experimental Reactor. Part II begins with a summary of nuclear power production in 2001. At the end of 2001 there were 438 nuclear power plants (NPPs) in operation, corresponding to a total capacity of 353 GW(e), more than 10000 reactor-years of cumulative operating experience and about 16% of global

Basic research for nuclear energy. y Study on the nuclear materials technology

Energy Technology Data Exchange (ETDEWEB)

Kuk, I H; Lee, H S; Jeong, Y H; Sung, K W; Han, J H; Lee, J T; Lee, H K; Kim, S J; Kang, H S; An, D H; Kim, K R; Park, S D; Han, C H; Jung, M K; Oh, Y J; Kim, K H; Kim, S H; Back, J H; Kim, C H; Lim, K S; Kim, Y Y; Na, J W; Ku, J H; Lee, D H

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs.

Basic research for nuclear energy. y Study on the nuclear materials technology

International Nuclear Information System (INIS)

Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs

Current Status of Advanced Nuclear Fuel Cycle technologies

International Nuclear Information System (INIS)

Hwang, Yong Soo; Lee, Jong Hyun

2009-07-01

To expand the use of nuclear energy, SNF from nuclear power plants must be managed in a safe and environmental friendly and the problem of decreasing uranium should be solved. To resolve this, a dry processing technology Pyroprocessing is focused on. The government started to develop of Pyroprocessing technology in 1997. According to the decision of government based of Atomic Energy Commission in December 2008, the Korea Atomic Energy Research Institute will construct PRIDE (Pyroprocess Integrated Inactive DEmonstration Facility) by 2011 to prove a consistent process. If Pyroprocessing technology will be developed in the near future, the size of radioactive waste disposal site can be reduced to 100 times compared to the direct disposal. When this technology will be connected to Fast Reactor. high level nuclear waste management of Hundreds of thousands of years may be reduced to hundreds years. However for the commercialization of Pyroprocessing technology, there are some problems to solve. First, because of none commercial facilities in the world of executive experience, so that the facility design, measurement. management and material flow, the critical need for data accumulation. Second, High-level nuclear waste have been known to generate more than the wet methods, it should continue to reduce technology development. In addition, a careful consideration of the residual uranium generating on process also can maximize the efficiency of reducing. The new concept is being developed in Korea Atomic Energy Research Institute Pyroprocessing technology and nuclear waste processing technology to overcome these drawbacks sUQQested a way

A project in support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho (and others)

2005-12-15

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.

The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology

International Nuclear Information System (INIS)

Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R E.

2005-01-01

The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory were 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs

The Nuclear Education and Staffing Challenge: Rebuilding Critical Skills in Nuclear Science and Technology

International Nuclear Information System (INIS)

Wogman, Ned A.; Bond, Leonard J.; Waltar, Alan E.; Leber, R E.

2005-01-01

The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory where 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of Nuclear Legacies, Global Security, Nonproliferation, Homeland Security and National Defense, Radiobiology and Nuclear Energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. This paper presents the current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs

The nuclear education and staffing challenge: Rebuilding critical skills in nuclear science and technology

International Nuclear Information System (INIS)

Wogman, N.A.; Bond, L.J.; Waltar, A.E.; Leber, R.E.

2005-01-01

The United States, the Department of Energy (DOE) and its National Laboratories, including the Pacific Northwest National Laboratory (PNNL), are facing a serious attrition of nuclear scientists and engineers and their capabilities through the effects of aging staff. Within the DOE laboratories, 75% of nuclear personnel will be eligible to retire by 2010. It is expected that there will be a significant loss of senior nuclear science and technology staff at PNNL within five years. PNNL's nuclear legacy is firmly rooted in the DOE Hanford site, the World War II Manhattan Project, and subsequent programs. Historically, PNNL was a laboratory where 70% of its activities were nuclear/radiological, and now just under 50% of its current business science and technology are nuclear and radiologically oriented. Programs in the areas of nuclear legacies, global security, nonproliferation, homeland security and national defense, radiobiology and nuclear energy still involve more than 1,000 of the 3,800 current laboratory staff, and these include more than 420 staff who are certified as nuclear/radiological scientists and engineers. Current challenges faced by PNNL that require an emerging strategy to solve the nuclear staffing issues through the maintenance and replenishment of the human nuclear capital needed to support PNNL nuclear science and technology programs are presented. (author)

Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology

International Nuclear Information System (INIS)

Suhaemi, Tj.; Sudarno; Sunaryo, G. R.; Supriatna, P.; Antariksawan, A. R.; Sumijanto; Febrianto; Histori; Aliq

2000-01-01

The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 2000 and was presented on June 28, 2000. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

Prospective application of laser plasma propulsion in rocket technology

International Nuclear Information System (INIS)

Lu Xin; Zhang Jie; Li Yingjun

2002-01-01

Interest in laser plasma propulsion is growing intensively. The interaction of high intensity short laser pulses with materials can produce plasma expansion with a velocity of hundreds of km/s. The specific impulse of ablative laser propulsion can be many tens of times greater than that of chemical rockets. The development and potential application of laser plasma propulsion are discussed

Transfer of nuclear technology from Spain

International Nuclear Information System (INIS)

Madrid, G.

1985-01-01

Technology transfer from Spain is possible in several fields of nuclear technology ranging from the head end of the fuel cycle (ENUSA) to the back end (ENRESA). The advantages of such a transfer are emphasized

National Blue Ocean Strategy in Nuclear Technology Visibility

International Nuclear Information System (INIS)

Hasfazilah Hassan; Sabariah Kader Ibrahim; Mohamad Radzuan Othman; Abdul Halim Jumat; Abdul Halim Mohd Ali

2016-01-01

This paper describes the strategic approach taken by Malaysian Nuclear Agency in carrying out public information and public acceptance on nuclear technology activities. The main objective of this study is to ensure that public and stake holders are continuously getting correct information from credible sources. Through the feedback received, comprehensive and holistic approach provides the desired impact. Obtaining the correct information from credible sources culture should always be inculcate to ensure that the benefits of nuclear technologies can be practiced and accepted by civil society without prejudice. Through strategic approach and activities implemented, monitoring and review, and measurement of the effectiveness of ongoing programs are expected to increase public awareness of the importance and contribution of nuclear technology in Malaysia. (author)

Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.7--pulse power technology

International Nuclear Information System (INIS)

2010-11-01

Progress report on nuclear science and technology in China (Vol. 1) includes 889 articles which are communicated on the first national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about nuclear electronics, nuclear detecting technology, pulse power technology, nuclear fusion and plasma

The sustainable nuclear energy technology platform. A vision report

International Nuclear Information System (INIS)

2007-01-01

Nuclear fission energy can deliver safe, sustainable, competitive and practically carbon-free energy to Europe's citizens and industries. Within the framework of the Strategic Energy Technology Plan (SET Plan), the European Commission's stakeholders in this field have formulated a collective vision of the contributions this energy could make towards Europe's transition to a low-carbon energy mix by 2050, with the aim of integrating and expanding R and D capabilities in order to further this objective. The groundwork has been prepared by the stakeholders listed in Annex II, within the framework of two EURATOM FP6 (Sixth Framework Programme) Coordination Actions, namely SNF-TP (Sustainable Nuclear Fission Technology Platform) and PATEROS (Partitioning and Transmutation European Road-map for Sustainable Nuclear Energy), with contributions from Europe's technical safety organisations. This vision report prepares the launch of the European Technology Platform on Sustainable Nuclear Energy (SNE-TP). It proposes a vision for the short-, medium- and long-term development of nuclear fission energy technologies, with the aim of achieving a sustainable production of nuclear energy, a significant progress in economic performance, and a continuous improvement of safety levels as well as resistance to proliferation. In particular, this document proposes road-maps for the development and deployment of potentially sustainable nuclear technologies, as well as actions to harmonize Europe's training and education, whilst renewing its research infrastructures. Public acceptance is also an important issue for the development of nuclear energy. Therefore, research in the fields of nuclear installation safety, protection of workers and populations against radiation, management of all types of waste, and governance methodologies with public participation will be promoted. The proposed road-maps provide the backbone for a strategic research agenda (SRA) to maintain Europe's leadership in

Industrial applications of nuclear technology

International Nuclear Information System (INIS)

Vargas, Celso

2010-01-01

Industrial applications of nuclear technology have been very diverse worldwide. This type of technology has begun to introduce in Costa Rica to evaluate and improve different industrial processes. These applications have been classified into two or three categories, according to the criteria used. Nucleonic control systems, the gamma logging and radiotracers are determined. (author) [es

The Off-plane Grating Rocket Experiment

Science.gov (United States)

Donovan, Benjamin

2018-01-01

The next generation of X-ray spectrometers necessitate significant increases in both resolution and effective area to achieve the science goals set forth in the 2010 Decadal Survey and the 2013 Astrophysics Roadmap. The Off-plane Grating Rocket Experiment (OGRE), an X-ray spectroscopy suborbital rocket payload currently scheduled for launch in Q3 2020, will serve as a testbed for several key technologies which can help achieve the desired performance increases of future spectrometers. OGRE will be the first instrument to fly mono-crystalline silicon X-ray mirrors developed at NASA Goddard Space Flight Center. The payload will also utilize an array of off-plane gratings manufactured at The Pennsylvania State University. Additionally, the focal plane will be populated with an array of four electron-multiplying CCDs developed by the Open University and XCAM Ltd. With these key technologies, OGRE hopes to achieve the highest resolution on-sky soft X-ray spectrum to date. We discuss the optical design, expected performance, and the current status of the payload.

National symposium on electrochemistry in nuclear technology

International Nuclear Information System (INIS)

1994-01-01

A National Symposium on Electrochemistry in Nuclear Technology (NASENT-94) was held at Kalpakkam, India during January 5-7, 1994. The subjects covered a wide range of topics in electrochemistry, such as electrochemical production, refining, analysis and corrosion of metals, electrochemical monitors and sensors, solid state electrochemistry, applications of electrochemical processes and measurement techniques in nuclear technology etc. Papers relevant to INIS are indexed separately

Nuclear energy for technology and industry

International Nuclear Information System (INIS)

Kemeny, L.G.

1987-01-01

It is a sad commentary on the complete lack of informed realism of the Government and people of Australia that, after thirty years of vacillation and political chicanery, nuclear technology, one of this nation's potential ''sunrise industries'' is in its death throes. Whilst our third world neighbours, in particular Indonesia, Malaysia, the Philippines, the People's Republic of China and even impoverished Bangladesh are making giant strides to develop an autonomous expertise Australia's potential has been dissipated and its opportunities for leadership and technology transfer lost. By chance this paper was written some weeks before the nuclear accident at Chernobyl (U.S.S.R.) and many years after accidents at the Three Mile Island nuclear power plant (U.S.A.) and the plutonium production reactor at Windscale (U.K.). None of these incidents alter the basic arguments or conclusions contained in this manuscript. (See Appendix). The year 1986 might represent the final opportunity for concerned professionals to seek to improve the quality of public education and information to end ''the war against the atom''. It will be necessary to re-motivate the public and private sector of a demoralised technology and to launch it on a road of responsible and successful expansion unshackled by beaurocratic interference. It is the purpose of this paper to examine why the first three decades of nuclear technology in Australia have been so singularly unsuccessful and to discuss a coherent and rational implementation of plans and policies for the future. (author)

Proliferation Persuasion. Coercive Bargaining with Nuclear Technology

Energy Technology Data Exchange (ETDEWEB)

Volpe, Tristan A. [George Washington Univ., Washington, DC (United States)

2015-08-31

Why do states wait for prolonged periods of time with the technical capacity to produce nuclear weapons? Only a handful of countries have ever acquired the sensitive nuclear fuel cycle technology needed to produce fissile material for nuclear weapons. Yet the enduring trend over the last five decades is for these states to delay or forgo exercising the nuclear weapons option provided by uranium enrichment or plutonium reprocessing capabilities. I show that states pause at this threshold stage because they use nuclear technology to bargain for concessions from both allies and adversaries. But when does nuclear latency offer bargaining benefits? My central argument is that challengers must surmount a dilemma to make coercive diplomacy work: the more they threaten to proliferate, the harder it becomes to reassure others that compliance will be rewarded with nuclear restraint. I identify a range of mechanisms able to solve this credibility problem, from arms control over breakout capacity to third party mediation and confidence building measures. Since each step towards the bomb raises the costs of implementing these policies, a state hits a sweet spot when it first acquires enrichment and/or reprocessing (ENR) technology. Subsequent increases in proliferation capability generate diminishing returns at the bargaining table for two reasons: the state must go to greater lengths to make a credible nonproliferation promise, and nuclear programs exhibit considerable path dependency as they mature over time. Contrary to the conventional wisdom about power in world politics, less nuclear latency thereby yields more coercive threat advantages. I marshal new primary source evidence from archives and interviews to identify episodes in the historical record when states made clear decisions to use ENR technology as a bargaining chip, and employ this theory of proliferation persuasion to explain how Japan, North Korea, and Iran succeeded and failed to barter concessions from the

Proceedings of the 5th nuclear science and technology conference

Energy Technology Data Exchange (ETDEWEB)