Download or read book Neutronics Steady state and Transient Analyses for the Poland MARIA Reactor for Irradiation Testing of LEU Lead Test Fuel Assemblies from CERCA written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Republic of Poland is considering conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel assemblies (FA). The FA design in MARIA is rather unique; a suitable LEU FA has never been designed or tested. IAE has contracted with CERCA (the fuel supply portion of AREVA in France) to supply 2 lead test assemblies (LTA). The LTAs will be irradiated in MARIA to burnup level of at least 40% for both LTAs and to 60% for one LTA. IAE may decide to purchase additional LEU FAs for a full core conversion after the test irradiation. The Reactor Safety Committee within IAE and the National Atomic Energy Agency in Poland (PAA) must approve the LTA irradiation process. The approval will be based, in part, on IAE submitting revisions to portions of the Safety Analysis Report (SAR) which are affected by the insertion of the LTAs. (A similar process will be required for the full core conversion to LEU fuel.) The analysis required was established during working meetings between Argonne National Laboratory (ANL) and IAE staff during August 2006, subsequent email correspondence, and subsequent staff visits. The analysis needs to consider the current high-enriched uranium (HEU) core and 4 core configurations containing 1 and 2 LEU LTAs in various core positions. Calculations have been performed at ANL in support of the LTA irradiation. These calculations are summarized in this report and include criticality, burn-up, neutronics parameters, steady-state thermal hydraulics, and postulated transients. These calculations have been performed at the request of the IAE staff, who are performing similar calculations to be used in their SAR amendment submittal to the PAA. The ANL analysis has been performed independently from that being performed by IAE and should only be used as one step in the verification process.
Download or read book Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility written by and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited for future testing. TREAT is a thermal neutron spectrum, air-cooled, nuclear test facility that is designed to test nuclear fuels in transient scenarios. These specific scenarios range from simple temperature transients to full fuel melt accidents. DOE has expressed a desire to develop a simulation capability that will accurately model the experiments before they are irradiated at the facility. It is the aim for this capability to have an emphasis on effective and safe operation while minimizing experimental time and cost. The multi physics platform MOOSE has been selected as the framework for this project. The goals for this work are to identify the fundamental neutronics properties of TREAT and to develop an accurate steady state model for future multiphysics transient simulations. In order to minimize computational cost, the effect of spatial homogenization and angular discretization are investigated. It was found that significant anisotropy is present in TREAT assemblies and to capture this effect, explicit modeling of cooling channels and inter-element gaps is necessary. For this modeling scheme, single element calculations at 293 K gave power distributions with a root mean square difference of 0.076% from those of reference SERPENT calculations. The minimum critical core configuration with identical gap and channel treatment at 293 K resulted in a root mean square, total core, radial power distribution 2.423% different than those of reference SERPENT solutions.
Download or read book Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility written by Anthony L. Alberti and published by . This book was released on 2016 with total page 71 pages. Available in PDF, EPUB and Kindle. Book excerpt: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited for future testing. TREAT is a thermal neutron spectrum, air-cooled, nuclear test facility that is designed to test nuclear fuels in transient scenarios. These specific scenarios range from simple temperature transients to full fuel melt accidents. DOE desires a simulation capability that will accurately model the experiments before they are irradiated at the facility. It is the aim for this capability to have an emphasis on effective and safe operation while minimizing experimental time and cost. The multiphysics platform MOOSE has been selected as the framework for this project. The goals of this thesis are to investigate the fundamental neutronics properties of TREAT and to develop an accurate steady state model for future multiphysics transient simulations. To minimize computational cost, the effects of spatial and angular homogenization approaches were investigated. A high degree of anisotropy is present in TREAT assemblies and to capture this effect, explicit modeling of cooling channels and interassembly gaps is necessary. Single assembly calculations at 293 K gave power distributions 0.076% different than that of reference Monte Carlo (SERPENT) calculations. The minimum critical core configuration with identical gap and channel treatment at 293 K resulted in a root mean square, axially integrated radial power distribution difference of 0.22% compared to reference SERPENT solutions.
Download or read book RELAP5 MOD3 Model and Transient Analyses for Maria Research Reactor in Poland written by Jan Szczurek (energetyka) and published by . This book was released on 2003 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book History Development and Future of TRIGA Research Reactors written by and published by . This book was released on 2016 with total page 131 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Download or read book Pegasus Wing glove Experiment to Document Hypersonic Crossflow Transition written by Arild Bertelrud and published by . This book was released on 2000 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: In a recent flight experiment to study hypersonic crossflow transition, boundary layer characteristics were documented. A smooth steel glove was mounted on the first stage delta wing of Orbital Sciences Corporation's Pegasus® launch vehicle and was flown at speeds of up to Mach 8 and altitudes of up to 250,000 ft. The wing-glove experiment was flown as a secondary payload off the coast of Florida in October 1998. This paper describes the measurement system developed. Samples of the results obtained for different parts of the trajectory are included to show the characteristics and quality of the data. Thermocouples and pressure sensors (including Preston tubes, Stanton tubes, and a "probeless" pressure rake showing boundary layer profiles) measured the time-averaged flow. Surface hot-films and high-frequency pressure transducers measured flow dynamics. Because the vehicle was not recoverable, it was necessary to design a system for real-time onboard processing and transmission. Onboard processing included spectral averaging. The quality and consistency of data obtained was good and met the experiment requirements.
Download or read book Status of Accelerator Driven Systems Research and Technology Development written by International Atomic Energy Agency and published by IAEA Tecdoc. This book was released on 2015 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the greatest challenges for nuclear energy is how to properly manage the highly radioactive waste generated during irradiation in nuclear reactors. Accelerator Driven Systems (ADSs) may offer new prospects and advantages for the transmutation of such high level nuclear waste. ADS or accelerator driven transmutation of waste (ATW) consists of a high power proton accelerator, a heavy metal spallation target that produces neutrons when bombarded by the high power beam, and a sub-critical core that is neutronically coupled to the spallation target. This publication provides a comprehensive state of the art of the ADS technology by representing the different ADS concepts proposed worldwide in the last 15 years, as well as the related R&D activities and demonstration initiatives carried out at national international level.
Download or read book LMFBR Demonstration Plant written by and published by . This book was released on 1972 with total page 436 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Once and Future Partners written by William C. Potter and published by Routledge. This book was released on 2018-10-09 with total page 174 pages. Available in PDF, EPUB and Kindle. Book excerpt: Despite their Cold War rivalry, the United States and the Soviet Union frequently engaged in joint efforts to prevent the spread of nuclear weapons. Leaders in Washington and Moscow recognized that nuclear proliferation would serve neither country’s interests even when they did not see eye-to-eye in many other areas. They likewise understood why collaboration in mitigating this nuclear danger would serve both their own interests and those of the international community. This volume examines seven little known examples of US-Soviet cooperation for non-proliferation, including preventing South Africa from conducting a nuclear test, developing international safeguards and export control guidelines, and negotiating a draft convention banning radiological weapons. It uses declassified and recently-digitized archival material to explore in-depth the motivations for and modalities for cooperation under often adverse political circumstances. Given the current disintegration of Russian and US relations, including in the nuclear sphere, this history is especially worthy of review. Accordingly, the volume’s final chapter is devoted to discussing how non-proliferation lessons from the past can be applied today in areas most in need of US-Russian cooperation.
Download or read book U S Efforts Against the Spread of Chemical Weapons written by Reginald Bartholomew and published by . This book was released on 1989 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Single industry communities written by and published by . This book was released on 1977 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Radiography 3 written by Shigenori Fujine and published by Springer. This book was released on 1990-07-31 with total page 1046 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the Third World Conference held in Osaka, Japan, May 14-18, 1989
Download or read book Intense Neutron Sources written by U.S. Atomic Energy Commission and published by . This book was released on 1966 with total page 856 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water written by International Atomic Energy Agency and published by . This book was released on 2003 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state of the art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report, together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage.
