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This Safety Report updates IAEA Safety Series No. 39, Safe Handling of Plutonium (1974), and provides an overview of modern practices for handling and storing separated plutonium. It provides descriptions of plutonium and its properties, and of the biological effects on humans of plutonium. The principles underlying the safe design and operation of plutonium handling/storage facilities and the licensing of such facilities are also covered.
Safe and Secure Transport and Storage of Radioactive Materials reviews best practice and emerging techniques in this area. The transport of radioactive materials is an essential operation in the nuclear industry, without which the generation of nuclear power would not be possible. Radioactive materials also often need to be stored pending use, treatment, or disposal. Given the nature of radioactive materials, it is paramount that transport and storage methods are both safe and secure. A vital guide for managers and general managers in the nuclear power and transport industries, this book covers topics including package design, safety, security, mechanical performance, radiation protection and shielding, thermal performance, uranium ore, fresh fuel, uranium hexafluoride, MOX, plutonium, and more. - Uniquely comprehensive and systematic coverage of the packaging, transport, and storage of radioactive materials - Section devoted to spent nuclear fuels - Expert team of authors and editors
In 2018, the National Academies of Sciences, Engineering, and Medicine issued an Interim Report evaluating the general viability of the U.S. Department of Energy's National Nuclear Security Administration's (DOE-NNSA's) conceptual plans for disposing of 34 metric tons (MT) of surplus plutonium in the Waste Isolation Pilot Plant (WIPP), a deep geologic repository near Carlsbad, New Mexico. It provided a preliminary assessment of the general viability of DOE-NNSA's conceptual plans, focused on some of the barriers to their implementation. This final report addresses the remaining issues and echoes the recommendations from the interim study.
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.
With the end of the Cold War, new opportunities for interaction have opened up between the United States and the countries of the Former Soviet Union. Many of these important initiatives involve the US Department of Energy (DOE) and the Ministry of the Russian Federation for Atomic Energy (MINA TOM). Currently, collaboration is under way which involves reactor safety, the disposition of fissile materials from the weapons program, radioactive waste disposal, and the safety of nuclear warheads. Another fruitful area of interchange resulted from the radiochemical storage tank accident at the site of the Siberian Chemical Compound at Tomsk-7 in 1993. DOE and MINATOM agreed to meet and exchange information about the accident for the purposes of improving safety. A meeting on the Tomsk tank accident was held in Hanford, Washington in 1993, followed by a second meeting in st. Petersburg, Russia in 1994 in which the agenda expanded to include radiochemical processing safety. A third exchange took place in 1995 in Los Alamos, New Mexico, and additional papers were presented on nonreactor nuclear safety. Following a planning session in 1996 in Seattle, Washington, it was decided to hold a fourth technical exchange on the broader subject of nuclear materials safety management. Through a grant from the North Atlantic Treaty Organization (NATO) Disarmament Programme, the meeting took place on March 17- 21, 1997, in Amarillo, Texas as a NATO Advanced Research Workshop (ARW) through grant no. DISRM 961315.
The Waste Isolation Pilot Plant (WIPP) is a deep underground mined facility for the disposal of transuranic waste resulting from the nation's defense program. Transuranic waste is defined as waste contaminated with transuranic radionuclides with half-life greater than 20 years and activity greater than 100 nanocuries per gram. The waste mainly consists of contaminated protective clothing, rags, old tools and equipment, pieces of dismantled buildings, chemical residues, and scrap materials. The total activity of the waste expected to be disposed at the WIPP is estimated to be approximately 7 million curies, including 12,900 kilograms of plutonium distributed throughout the waste in very dilute form. The WIPP is located near the community of Carlsbad, in southeastern New Mexico. The geological setting is a 600-meter thick, 250 million-year-old saltbed, the Salado Formation, lying 660 meters below the surface. The National Research Council (NRC) has been providing the U.S. Department of Energy (DOE) scientific and technical evaluations of the WIPP since 1978. The committee's task is twofold: (1) to identify technical issues that can be addressed to enhance confidence in the safe and long-term performance of the repository and (2) to identify opportunities for improving the National Transuranic (TRU) Program for waste management, especially with regard to the safety of workers and the public. This is the first full NRC report issued following the certification of the facility by the U.S. Environmental Protection Agency (EPA) on May 18, 1998. An interim report was issued by the committee in April 2000 and is reproduced in this report. The main findings and recommendations from the interim report have been incorporated into the body of this report. The overarching finding and recommendation of this report is that the activity that would best enhance confidence in the safe and long-term performance of the repository is to monitor critical performance parameters during the long pre-closure phase of repository operations (35 to possibly 100 years). Indeed, in the first 50 to 100 years the rates of important processes such as salt creep, brine inflow (if any), and microbial activity are predicted to be the highest and will be less significant later. The committee recommends that the results of the on-site monitoring program be used to improve the performance assessment for recertification purposes. These results will determine whether the need for a new performance assessment is warranted. For the National TRU Program, the committee finds that the DOE is implementing many of the recommendations of its interim report. It is important that the DOE continue its efforts to improve the packaging, characterization, and transportation of the transuranic waste.
Plutonium is a controversial fuel for three reasons: it can be used to make nuclear weapons, causes cancer, and is extremely costly to produce. Yet, relatively little information has been publicly available regarding the main use of this fuel around the world, in traditional ("light water") nuclear power reactors. This book offers the first comprehensive global study of plutonium "mixed oxide" (MOX) fuel in those reactors. Field research was conducted in all seven countries that have commercially manufactured or used such MOX: Belgium, France, Germany, Japan, the Netherlands, Switzerland, and the United Kingdom. The chapters explain why five of the countries have decided to phase out MOX, due to concerns about security, economics, safety, the environment, and public acceptance. This volume should inform ongoing decision-making - in China, Japan, South Korea, the United States, and beyond - about whether to recycle plutonium for energy.
The Chemistry of the Actinide and Transactinide Elements is a contemporary and definitive compilation of chemical properties of all of the actinide elements, especially of the technologically important elements uranium and plutonium, as well as the transactinide elements. In addition to the comprehensive treatment of the chemical properties of each element, ion, and compound from atomic number 89 (actinium) through to 109 (meitnerium), this multi-volume work has specialized and definitive chapters on electronic theory, optical and laser fluorescence spectroscopy, X-ray absorption spectroscopy, organoactinide chemistry, thermodynamics, magnetic properties, the metals, coordination chemistry, separations, and trace analysis. Several chapters deal with environmental science, safe handling, and biological interactions of the actinide elements. The Editors invited teams of authors, who are active practitioners and recognized experts in their specialty, to write each chapter and have endeavoured to provide a balanced and insightful treatment of these fascinating elements at the frontier of the periodic table. Because the field has expanded with new spectroscopic techniques and environmental focus, the work encompasses five volumes, each of which groups chapters on related topics. All chapters represent the current state of research in the chemistry of these elements and related fields.