Westinghouse Modular Grinding Process: Improvement for Follow on Processes

2013 ◽  
Author(s):  
Henning Fehrmann
Keyword(s):  
Particle Size ◽  
Nuclear Power ◽  
Power Plants ◽  
Waste Treatment ◽  
Grinding Process ◽  
Beneficial Effects ◽  
Treatment Processes ◽  
Minimize Radiation Exposure ◽  
Negative Impacts ◽  
Westinghouse Electric

In nuclear power plants (NPP) ion exchange (IX) resins are used in several systems for water treatment. The resins can be in bead or powdered form. For waste treatment of spent IX resins, two methods are basically used: • Direct immobilization (e.g. with cement, bitumen, polymer or High Integrity Container (HIC)) • Thermal treatment (e.g. drying, oxidation or pyrolysis) Bead resins have some properties (e.g. particle size and density) that can have negative impacts on following waste treatment processes. Negative impacts could be: • Floatation of bead resins in cementation process • Sedimentation in pipeline during transportation • Poor compaction properties for Hot Resin Supercompaction (HRSC) Reducing the particle size of the bead resins can have beneficial effects enhancing further treatment processes and overcoming prior mentioned effects. Westinghouse Electric Company has developed a modular grinding process to crush/grind the bead resins. This modular process is designed for flexible use and enables a selective adjustment of particle size to tailor the grinding system to the customer needs. The system can be equipped with a crusher integrated in the process tank and if necessary a colloid mill. The crusher reduces the bead resins particle size and converts the bead resins to a pump able suspension with lower sedimentation properties. With the colloid mill the resins can be ground to a powder. Compared to existing grinding systems this equipment is designed to minimize radiation exposure of the worker during operation and maintenance. Using the crushed and/or ground bead resins has several beneficial effects like facilitating cementation process and recipe development, enhancing oxidation of resins, improving the Hot Resin Supercompaction volume reduction performance.

scholarly journals The correlations of the particle size, calorific value, moisture- and ash content of waste derived fuel, and examination of its heavy metal content

2020 ◽  
Vol 14 (1) ◽  
pp. 109-117
Author(s):  
Csaba Leitol ◽  
Alexandra Győrfi ◽  
Tibor Kiss
Keyword(s):  
Heavy Metal ◽  
Particle Size ◽  
Metal Content ◽  
Power Plants ◽  
Waste Treatment ◽  
Calorific Value ◽  
Heavy Metal Content ◽  
Particle Size Fractions ◽  
Measurement Results ◽  
Biological Waste Treatment

Significant development has taken place in the field of waste management recently in the preparation of the energetic exploitation of recyclable, non-hazardous municipal solid waste. With mechanical-biological waste treatment, 35-40% of the weight of this waste can be made appropriate for energetic exploitation, mainly for co-incineration in cement factories and power plants. The recoverability of waste derived fuel produced in mechanical-biological waste treatment plants highly depends on the burning and combustion technological properties of the mixture, and on its compounds influencing burning and different emissions. Waste recovery facilities do not take over fuel below a specific calorific value and over a given heavy metal, halogen and pollutant content. In our research we were looking for correlations in the particle size, calorific value, moisture-, ash- and heavy metal content of waste derived fuel. On the basis of the measurement results, the connection between the particle size fractions and the fuel properties can clearly be stated. The fractions of smaller particle size have higher moisture-, ash- and heavy metal content, while the fractions of bigger particle size have higher calorific value.

The Effect of Elevated Temperatures and Nuclear Radiation on the Properties of Biological Shielding Concrete

2016 ◽  
Vol 677 ◽  
pp. 8-16 ◽  
Author(s):  
Jaroslava Koťátková ◽  
Jan Zatloukal ◽  
Pavel Reiterman ◽  
Jan Patera ◽  
Zbyněk Hlaváč ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Elevated Temperatures ◽  
Nuclear Radiation ◽  
Containment Vessel ◽  
Negative Impacts

The paper reviews the so far known information about the properties of biological shielding concrete used in the containment vessel of nuclear power plants (NPP) and its behaviour when exposed to radiation. The damage of concrete caused by neutron and gamma radiation as well as by the accompanying generation of heat is described. However, there is not enough data for the proper evaluation of the negative impacts and further research is needed.

scholarly journals Using bentonite for NPP liquid waste treatment

2015 ◽  
Vol 5 (3) ◽  
pp. 38-43
Author(s):  
Dang Hanh Bui
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Waste Treatment ◽  
Liquid Waste ◽  
Radiation Workers ◽  
Water Waste

During operation, nuclear power plants (NPPs) release a large quantity of water waste containing radionuclides required treatment for protection of the radiation workers and the environment. This paper introduces processes used to treat water waste from Paks NPP in Hungary and it also presents the results of a study on the use of Vietnamese bentonite to remove radioactive Caesium from a simulated water waste containing Cs

AP1000 Operation Procedures System and Development

2010 ◽  
Author(s):  
Fang Wen
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Flow Process ◽  
Human Factor Engineering ◽  
Data Process ◽  
Operation Procedure ◽  
The Status ◽  
Procedure Classification ◽  
Plant Data ◽  
Westinghouse Electric

This paper makes a brief introduction on AP1000 operation procedure system, including procedure classification, function and composition. In addition, key points of work flow process and the advantages of AP1000 operation procedures are described, among which the application of CPS (computerized procedure system) on AP1000 operation area and human factor engineering are highlighted. CPS, as an advanced procedure system, which is relatively new to existing nuclear power plants in China, does not only have the function of electronic indication for procedures, but also have the ability to monitor plant data, process the data and then present the status of the procedure steps to the reactor operator. Moreover, based on current situation, this paper offers several suggestions on procedure development for Sanmen AP1000 nuclear power project, i.e. first, we can ensure the quality of operation procedures by preparing a precise writer’s guideline, a friendly-interfaced procedure template, an efficient work configuration and an appropriate schedule; then determine the way how we are going to use operation procedures in English version; finally realize CPS Chinesization and localization gradually by digesting and absorbing API 000 technology from Westinghouse Electric Company. This paper gives an intact and systematic discourse on AP1000 operation procedure system and its characteristics. Besides, the latter part of this paper focuses on development of AP1000 operation procedures for Sanmen nuclear power plant and it would be a worthwhile reference for newly-built AP1000 units in China.

Development of Computer Program for Estimating Decommissioning Cost

2011 ◽  
Author(s):  
Hak-Soo Kim ◽  
Jong-Kil Park
Keyword(s):  
Computer Program ◽  
Cost Estimation ◽  
Nuclear Power ◽  
Power Plants ◽  
Waste Treatment ◽  
Assessment Tool ◽  
Unit Cost ◽  
Cost Effective ◽  
Cost Estimating ◽  
Plant Area

The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning. To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co. Ltd, developed a decommissioning cost estimating computer program called “DeCAT-Pro”, which is Decommissioning Cost Assessment Tool – Professional. (Hereinafter called “DeCAT”) This program allows users to easily assess the decommissioning cost with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the conditions of radwaste disposal and transportation automatically.

scholarly journals Overview of nuclear waste treatment and management

2019 ◽  
Vol 118 ◽  
pp. 04037
Author(s):  
Jianquan Liu ◽  
Wentai Dai
Keyword(s):  
Nuclear Waste ◽  
Waste Disposal ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Waste Treatment ◽  
Nuclear Waste Disposal ◽  
High Energy ◽  
High Energy Density ◽  
Potential Threat

Nuclear energy is an efficient energy source. Nuclear fuel has the advantages of high energy density and convenient transportation and storage. After decades of tortuous development, nuclear energy has been well utilized in many ways, especially in the field of nuclear power generation. However, as the number of nuclear power plants continues to increase, the problem of nuclear waste disposal is becoming more and more serious. Nuclear waste disposal is a complex process. For nuclear waste treatment, people initially only temporarily deposit these nuclear wastes or dump them directly. However, as people’s awareness of nuclear waste increases, and the huge potential threat of nuclear waste is known, it is necessary to analyze the current characteristics of nuclear waste and its pollution status in order to find a better nuclear waste treatment and management method.

scholarly journals Liquid Low-Level Radioactive Waste Treatment Using an Electrodialysis Process

Membranes ◽  
2021 ◽  
Vol 11 (5) ◽  
pp. 324
Author(s):  
Agnieszka Miśkiewicz ◽  
Agnieszka Nowak ◽  
Jędrzej Pałka ◽  
Grażyna Zakrzewska-Kołtuniewicz
Keyword(s):  
Radioactive Waste ◽  
Organic Contaminants ◽  
Nuclear Power ◽  
Power Plants ◽  
Waste Treatment ◽  
Experimental Tests ◽  
Electrical Current ◽  
Low Level ◽  
Medical Radioisotope ◽  
Low Level Radioactive Waste

In this work, the possibility of using electrodialysis for the treatment of liquid low-level radioactive waste was investigated. The first aim of the research was to evaluate the influence of the process parameters on the treatment of model solutions with different compositions. Subsequent experimental tests were conducted using solutions containing selected radionuclides (60Co and 137Cs), which are potential contaminants of effluents from nuclear power plants, as well as components often found in waste generated from industrial and medical radioisotope applications. The results of the experiments performed on real radioactive waste confirmed that electrodialysis was a suitable method for the treatment of such effluents because it ensured high levels of desalination and rates of decontamination. The most important parameters impacting the process were the applied voltage and electrical current. Moreover, this research shows that the application of the ED process enables the separation of non-ionic organic contaminants of LLW, which are unfavorable in further stages of waste predisposal.

Air Pressure Test on Concrete with Nano-Cement

2019 ◽  
Vol 16 (2) ◽  
pp. 748-753
Author(s):  
Jemimah M. Carmichael ◽  
Prince G. Arulraj
Keyword(s):  
Particle Size ◽  
Tensile Strength ◽  
Nuclear Power ◽  
Power Plants ◽  
Air Pressure ◽  
Nano Particles ◽  
Hardened Concrete ◽  
Nano Materials ◽  
Split Tensile Strength ◽  
Pressure Test

Nanotechnology is an emerging area of research that has received a lot of attention for its ability to make use of the unique properties of nano-sized materials. The grain size of the nano particles will be in the order of 10–9 m (1–100 nm). Due to the very small particle size and extremely large specific surface area, nano particles have same remarkable properties. The use of nano materials for making concrete is of recent origin. Addition of nano materials in concrete can lead to significant improvements in the strength and durability of concrete. For nuclear power plants, concrete with high compressive strength, high split tensile strength, low porosity and high density are required. An attempt has been made to increase the compressive and split tensile strength of concrete by replacing a portion of cement with nano cement. M20, M30, M40 and M50 grades of concrete were cast. For each of these mixes, 10%, 20%, 30%, 40% and 50% of cement was replaced with nano- cement. Nano-cement was made by grinding the commercially available 53 grade pozzolona cement in the ball grinding mill. A scanning electron microscope was used to determine the particle size of the nano-cement produced. A hollow cylinder of the concrete was made with concrete containing nano materials. The Air pressure test was carried at on hardened concrete and the results were compared with that of normal cement concrete. The safe internal pressure for M50 concrete with 50% replacement of cement with nano-cement was found to be 13.3 kg/cm2, which 31.6% higher than that of the normal M50 concrete.

Sign in / Sign up

Export Citation Format

Share Document