National Acid Precipitation Assessment Program [microform] : hearing before the Subcommittee on Natural Resources, Agriculture Research, and Environment of the Committee on Science, Space, and Technology, U.S. House of Representatives, One Hundredth Congress, second session, April 27, 1988.

"No. 125."

Program administration and installation design of the nuclear reactor project at North Carolina State College,

Mode of access: Internet.

Developing a state resource conservation and recovery program /

Mode of access: Internet.

Food stamp program : implementation of electronic benefit transfer systems : report to the ranking minority member, Committee on Agriculture, Nutrition, and Forestry, U.S. Senate /

"GAO-02-332."

Summary of FY 79 progress on Refill Effects Program : quarterly progress report, July 1 - September 30, 1979 /

"Date published: March 1980."

A three region steam drum model for a nuclear power plant simulator (BRENDA) /

"Date published: August 1981."

Manpower requirements in the nuclear power industry, 1982-1991 /

"Prepared for Office of Nuclear Power Systems, Assistant Secretary for Nuclear Energy, U.S. Department of Energy and the Institute of Nuclear Power Operations."

Proceedings of the U.S. Nuclear Regulatory Commission Thirteenth Water Reactor Safety Research Information Meeting, held at National Bureau of Standards, Gaithersburg, Maryland, October 22-25, 1985 /

Includes bibliographies.

The nitrate to ammonia and ceramic (NAC) process for the denitration and immobilization of low-level radioactive liquid waste (LLW)

Hazardous radioactive liquid waste is the legacy of more than 50 years of plutonium production associated with the United States' nuclear weapons program. It is estimated that more than 245,000 tons of nitrate wastes are stored at facilities such as the single-shell tanks (SST) at the Hanford Site in the state of Washington, and the Melton Valley storage tanks at Oak Ridge National Laboratory (ORNL) in Tennessee. In order to develop an innovative, new technology for the destruction and immobilization of nitrate-based radioactive liquid waste, the United State Department of Energy (DOE) initiated the research project which resulted in the technology known as the Nitrate to Ammonia and Ceramic (NAC) process. However, inasmuch as the nitrate anion is highly mobile and difficult to immobilize, especially in relatively porous cement-based grout which has been used to date as a method for the immobilization of liquid waste, it presents a major obstacle to environmental clean-up initiatives. Thus, in an effort to contribute to the existing body of knowledge and enhance the efficacy of the NAC process, this research involved the experimental measurement of the rheological and heat transfer behaviors of the NAC product slurry and the determination of the optimal operating parameters for the continuous NAC chemical reaction process. Test results indicate that the NAC product slurry exhibits a typical non-Newtonian flow behavior. Correlation equations for the slurry's rheological properties and heat transfer rate in a pipe flow have been developed; these should prove valuable in the design of a full-scale NAC processing plant. The 20-percent slurry exhibited a typical dilatant (shear thickening) behavior and was in the turbulent flow regime due to its lower viscosity. The 40-percent slurry exhibited a typical pseudoplastic (shear thinning) behavior and remained in the laminar flow regime throughout its experimental range. The reactions were found to be more efficient in the lower temperature range investigated. With respect to leachability, the experimental final NAC ceramic waste form is comparable to the final product of vitrification, the technology chosen by DOE to treat these wastes. As the NAC process has the potential of reducing the volume of nitrate-based radioactive liquid waste by as much as 70 percent, it not only promises to enhance environmental remediation efforts but also effect substantial cost savings. ^

Nuclear power and Japan's collective future: Understanding beliefs about how nuclear policies will affect society

Despite ongoing controversies regarding possible directions for the nuclear plants program throughout Japan since the Fukushima disaster, little has been researched about people's belief structure about future society and what may affect their attitudes toward different policy options. Beyond policy debates, the present study focused on how people see a future society according to the assumptions of different policy options. A total of 125 students at Japanese universities were asked to compare a future society with society today in which one of alternative policies was adopted (i.e., shutdown or expansion of nuclear reactors) in terms of characteristics of individuals and society in general. While perceived dangerousness of nuclear power predicted attitudes and behavioural intentions to make personal sacrifices for nuclear power policies, beliefs about the social consequences of the policies, especially on economic development and dysfunction, appeared to play stronger roles in predicting those measures. The importance of sociological dimensions in understanding how people perceive the future of society regarding alternative nuclear power policies, and the subtle discrepancies between attitudes and behavioural intentions, are discussed.

Hydro-mechanical characterization of Barmer 1 bentonite from Rajasthan, India

The conceptual model for deep geological disposal of high level nuclear waste (HLW) is based on multiple barrier system consisting of natural and engineered barriers. Buffer/backfill material is regarded as the most important engineered barrier in HLW repositories. Due to large swelling ability, cation adsorption capacity, and low permeability bentonite is considered as suitable buffer material in HLW repositories. Japan has identified Kunigel VI bentonite, South Korea - Kyungju bentonite, China - GMZ bentonite, Belgium - FoCa clay, Sweden - MX-80 bentonite, Spain - FEBEX bentonite and Canada - Avonseal bentonite as candidate bentonite buffer for deep geological repository program. An earlier study on Indian bentonites by one of the authors suggested that bentonite from Barmer district of Rajasthan (termed Barmer 1 bentonite), India is suited for use as buffer material in deep geological repositories. However, the hydro-mechanical properties of the Barmer 1 bentonite are unavailable. This paper characterizes Barmer 1 bentonite for hydro-mechanical properties, such as, swell pressure, saturated permeability, soil water characteristic curve (SWCC) and unconfined compression strength at different dry densities. The properties of Barmer 1 bentonite were compared with bentonite buffers reported in literature and equations for designing swell pressure and saturated permeability coefficient of bentonite buffers were arrived at. (C) 2013 Elsevier B.V. All rights reserved.

A combined nonfertile and UO2 PWR fuel assembly for actinide waste minimization

A new combined Non Fertile and Uranium (CONFU) fuel assembly is proposed to limit the actinides that need long-term high-level waste storage from the pressurized water reactor (PWR) fuel cycle. In the CONFU assembly concept, ∼20% of the UO2 fuel pins are replaced with fertile free fuel hosting the transuranic elements (TRUs) generated in the previous cycle. This leads to a fuel cycle sustainable with respect to net TRU generation, and the amount and radiotoxicity of the nuclear waste can be significantly reduced in comparison with the conventional once-through UO2 fuel cycle. It is shown that under the constraints of acceptable power peaking limits, the CONFU assembly exhibits negative reactivity feedback coefficients comparable in values to those of the reference UO2 fuel. Feasibility of the PWR core operation and control with complete TRU recycle has been shown based on full-core three-dimensional neutronic simulation. However, gradual buildup of small amounts of Cm and Cf challenges fuel reprocessing and fabrication due to the high spontaneous fission rates of these nuclides and heat generation by some Pu, Am, and Cm isotopes. Feasibility of the processing steps becomes more attainable if the time between discharge and reprocessing is 20 yr or longer.

Numerical modelling of radionuclide migration in near-surface systems

Em todo o mundo são usados, hoje em dia, modelos numéricos hidrogeoquímicos para simular fenómenos naturais e fenómenos decorrentes de actividades antrópicas. Estes modelos ajudam-nos a compreender o ambiente envolvente, a sua variabilidade espacial e evolução temporal. No presente trabalho apresenta-se o desenvolvimento de modelos numéricos hidrogeoquímicos aplicados no contexto do repositório geológico profundo para resíduos nucleares de elevada actividade. A avaliação da performance de um repositório geológico profundo inclui o estudo da evolução geoquímica do repositório, bem como a análise dos cenários de mau funcionamento do repositório, e respectivas consequências ambientais. Se se escaparem acidentalmente radionuclídeos de um repositório, estes poderão atravessar as barreiras de engenharia e barreiras naturais que constituem o repositório, atingindo eventualmente, os ecosistemas superficiais. Neste caso, os sedimentos subsuperficiais constituem a última barreira natural antes dos ecosistemas superficiais. No presente trabalho foram desenvolvidos modelos numéricos que integram processos biogeoquímicos, geoquímicos, hidrodinâmicos e de transporte de solutos, para entender e quantificar a influência destes processos na mobilidade de radionuclídeos em sistemas subsuperficiais. Os resultados alcançados reflectem a robustez dos instrumentos numéricos utilizados para desenvolver simulações descritivas e predictivas de processos hidrogeoquímicos que influenciam a mobilidade de radionuclídeos. A simulação (descritiva) de uma experiência laboratorial revela que a actividade microbiana induz a diminuição do potencial redox da água subterrânea que, por sua vez, favorece a retenção de radionuclídeos sensíveis ao potencial redox, como o urânio. As simulações predictivas indicam que processos de co-precipitação com minerais de elementos maioritários, precipitação de fases puras, intercâmbio catiónico e adsorção à superfície de minerais favorecem a retenção de U, Cs, Sr e Ra na fase sólida de uma argila glaciar e uma moreia rica em calcite. A etiquetagem dos radionuclídeos nas simulações numéricas permitiu concluir que a diluição isotópica joga um papel importante no potencial impacte dos radionuclídeos nos sistemas subsuperficiais. A partir dos resultados das simulações numéricas é possivel calcular coeficientes de distribuição efectivos. Esta metodologia proporciona a simulação de ensaios de traçadores de longa duração que não seriam exequíveis à escala da vida humana. A partir destas simulações podem ser obtidos coeficientes de retardamento que são úteis no contexto da avaliação da performance de repositórios geológicos profundos.

Radiological protection and nuclear engineering studies in multi-MW target systems

Tese de doutoramento, Física, Universidade de Lisboa, Faculdade de Ciências, 2014

Plan de empresa para TECO: modelo de impacto social, autosostenibilidad financiera y de minimización de la huella del e-waste en Bogotá

La red TECO es una iniciativa que integra elementos ya conocidos en el mundo de la publicidad y de la gestión RAEE, en un nuevo modelo de negocio. Esto le permite competir de manera efectiva en un segmento de mercado que si bien no está saturado, requiere de cambios estructurales para poder cumplir su objetivo. El éxito del modelo de TECO radicará en la capacidad de generar su propio flujo de dinero, lo que le garantiza su auto sostenimiento, mientras minimiza la barrera del pensamiento tradicional en la comunidad respecto al miedo de desechar el e-waste (a través de la educación). De igual manera ayudará a todos los participantes de la red a mejorar su reputación y posicionar sus marcas. En última instancia el gran ganador de esta iniciativa es el medio ambiente. Al juntar todos los segmentos de mercado, de entre los cuales TECO podrá participar en su mercado objetivo de mil empresas en Bogotá, estos suman alrededor de ochocientos treinta y ocho mil millones. De esta cifra global nada despreciable, TECO podrá aspirar a cerca de un 0.19% de participación. Más concretamente, en lo que respecta a la categoría de presupuestos destinados a programas posconsumo RAEE y Green Businesses orientados a la publicidad institucional, TECO espera obtener un 6.13% del share.