Optimalisation by the Conditioning of Liquid and Solid Low- and Intermediate Radioactive Waste for Final Disposal in Slovakia

2003 ◽  
Author(s):  
Vladimir Remia´sˇ ◽  
Dusan Kra´sny
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Fiber Reinforced Concrete ◽  
Radioactive Waste Management ◽  
Waste Package ◽  
Final Disposal ◽  
Whole Process ◽  
Waste Container ◽  
Radioactive Waste Treatment

The radioactive waste treatment and conditioning are the most important step in radioactive waste management. In Slovak Republic the waste treatment and conditioning are including in the “Strategy of Radioactive waste management”. According to this “Strategy..” all sorts of low- and intermediate radioactive waste have to be conditioned to the fiber reinforced concrete container, i.e. “waste package”, only acceptable form for disposal in surface repository in Mochovce. In spite of good design of “Strategy..., in whole process should be occur some difficulty or difference. In the Radioactive Waste Treatment and Conditioning Center in Jaslovske Bohunice, built in 1999, the German treatment and conditioning technology together with French design of waste container was engaged. Presented paper summarized the practices during about 3 years operational period of conditioning radwaste in Jaslovske Bohunice. Till the presented results was achieved the harmonization of conditioning technology, particularly the cementation, has been necessary to accomplish with selected waste package. This aim had been reached after 1 years testing and analyzing with main fixed-target to find suitable formulation for radioactive grouting. The specific experiences had been received after 3 years operational period, which could be use for improving of whole process. In next time, the effects of conditioning process should be done especially in connection to the final disposal namely in term of economical efficiency. Based on present practice the great allowance indicated in area of concentration limits exploitation.

Radioactive Waste Management Challenges and Progress in Iraq

2011 ◽  
Author(s):  
Fouad Al-Musawi ◽  
Emad S. Shamsaldin ◽  
John R. Cochran
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Nuclear Research ◽  
Management Program ◽  
Nuclear Facilities ◽  
Radioactive Waste Management ◽  
The Government ◽  
Key Sites ◽  
Radioactive Waste Treatment

The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraq’s former nuclear facilities. The 18 former facilities at the Al-Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos and drums of uncharacterized radioactive waste and approximately 30 tanks that contain or did contain uncharacterized liquid radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility), Rashdiya (centrifuge facility) and Tarmiya (enrichment plant). The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraq’s centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the uncharacterized wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused sealed radioactive sources, and unknown quantities of NORM wastes from oil production in Iraq. This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program. The progress includes the establishment of a staffing structure, staff, participation in international training, rehabilitation of portions of the former Radioactive Waste Treatment Station at Al-Tuwaitha and the acquisition of equipment.

Radioactive Waste Treatment Technologies and Environment

2007 ◽  
Author(s):  
Ja´n Horva´th ◽  
Dusan Krasny
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Slovak Republic ◽  
Effective Management ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
Treatment Technologies ◽  
Radioactive Waste Treatment

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske´ Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented.

Development of nuclear criticality safety controls on intermediate-level waste packages

2012 ◽  
Vol 76 (8) ◽  
pp. 2949-2956 ◽  
Author(s):  
T. W. Hicks ◽  
P. Wood ◽  
D. Putley ◽  
T. D. Baldwin
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Neutron Transport ◽  
Intermediate Level ◽  
Fissile Material ◽  
Radioactive Waste Management ◽  
Waste Package ◽  
Operational Phase ◽  
Nuclear Criticality Safety ◽  
Enriched Uranium

AbstractIntermediate-level wastes (ILW) include substantial quantities of fissile material and controls are required to ensure that its storage, transport and disposal does not present a nuclear criticality hazard. This paper describes the Radioactive Waste Management Directorate's research to develop package fissile material limits (in the form of screening levels) for four different categories of ILW, defined according to uranium or plutonium composition: (1) irradiated natural and slightly enriched uranium (uranium containing up to 1.9 wt.% 235U); (2) low-enriched uranium (uranium containing up to 4 wt.% 235U); (3) high-enriched uranium (uranium containing up to 100 wt.% 235U); and (4) separated plutonium (plutonium containing up to 100 wt.% 239Pu).The derivation of package screening levels was supported by neutron transport calculations that addressed conditions during waste package transport to a geological disposal facility (GDF), during the GDF operational phase and after GDF closure. The analysis included consideration of combinations of events and processes that could result in fissile material accumulation and concentration after GDF closure, when waste packages have deteriorated sufficiently for fissile material to be mobilized. The results of the calculations have provided input to Radioactive Waste Management Directorate's decision making on setting waste package screening levels.

Liquid Low-level Radioactive Waste Treatment by Membrane Processes

2012 ◽  
Vol 1475 ◽  
Author(s):  
Grazyna Zakrzewska-Trznadel ◽  
Marian Harasimowicz ◽  
Agnieszka Miskiewicz ◽  
Agnieszka Jaworska-Sobczak
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Treatment ◽  
Liquid Radioactive Waste ◽  
Liquid Waste ◽  
Membrane Distillation ◽  
Integrated System ◽  
Nuclear Chemistry ◽  
Radioactive Waste Management ◽  
Membrane Processes

ABSTRACTThe first step in the processing of low- and medium-level liquid radioactive waste is the reduction in the volume of liquid containing small concentrations of radionuclides. Various methods for concentration of radioactive waste have been studied and developed at the Institute of Nuclear Chemistry and Technology, including membrane processes. Reverse osmosis was implemented at the Radioactive Waste Management Plant. Other methods such as ultrafiltration, membrane distillation, adsorption and different integrated processes were studied in the scope of national and international projects.This paper presents the results of research performed at Institute of Nuclear Chemistry and Technology in Warsaw concerning radioactive liquid waste treatment and the programs of implementation of these methods at nuclear centers producing such wastes, as well as the plans for the utilization of the knowledge and experience and designs of schemes for radioactive waste management in future nuclear power industry. The integrated system developed on the basis of research will be a prototype for further implementation.

Systematical Approach to the Radioactive Waste Management in Slovak Republic

2001 ◽  
Author(s):  
Milan Breza
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Solid Waste ◽  
Waste Treatment ◽  
Slovak Republic ◽  
Storage Tanks ◽  
Waste Streams ◽  
And Storage ◽  
Radioactive Waste Treatment

Abstract The aim of this paper is to inform of the world’s specialists about the systematical approach to the radioactive waste management in Slovak Republic (Slovakia). In Slovakia are in operation six preassurized light water reactors at NPPs V-1, V-2 in Jaslovske Bohunice and reactors 2×440 MWe in NPP Mochovce at present. The installed elektro-capacity produced from these reactors is 2640 MWe total. The first experimental NPP in the former Czechoslovakia was NPP A-1. It had used natural uranium as a fuel and heavy water as a moderator and CO2 as a cooling medium. The installed preformance of this NPP A-1 was 150 MWe and was in operation since 1972 to 1977. After two technological incidents former Czechoslovak government have decided to take out of this NPP A-1 from operation. According to former Soviet projects concerning for costructions of the above mentioned NPP in Jaslovske Bohunice Slovakia, to these project didn’t belong the projects for constructions of the technological units for the radioactive waste treatment, expect of the evaporating plant for the contaminated water concetration and storage tanks for the evaporated concentrates storage and storage possibilities for the contaminated solid waste storage. A comparable complicated situation was at NPP A-1, because all type of the radioactive waste streams content gama, beta and alfa radioanuclides as well. The second technological incident at NPP A-1 (with the some portion of the cooling medium CO2 leaking form the reactor vessel out) caused contamination for the NPP A-1 operating spaces by alfa radionuclides and alfa radionuclides penetrated in all waste streams at storage tanks, pipelines, vessels, etc. as well. During the beginning of the 80’s were realized some states R and D tasks that solved the systematical approach to the radioactive waste treatment in former Czechoslovakia. The main aim of the first etap was solved the all problems connected for the radioactive waste, treatment that are formed during NPPs of the VVER-440 type operation. It was necessary to secure the production of the electro energie. The most seriously priority had the tasks, that solved of the evaporator concentrates and solid waste treatment, especially burnable, pretratment. Simultaneuosly were solved the problems connected with the proposals, designings and realisations of the disposals for the long term storage of the treated RAW in the Czech and Slovak regions. In this presentation I have tried to deliver main information, that give of the survey for RAW treatment and their long term safety storage at disposal system in Mochovec - Slovakia.

scholarly journals Mesh generation for radioactive waste management tasks

2021 ◽  
Vol 14 (1) ◽  
pp. 87-95
Author(s):  
R. A. Butov ◽  
◽  
N. I. Drobyishevsky ◽  
E. V. Moiseenko ◽  
Yu. N. Tokarev ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Mesh Generation ◽  
Host Rock ◽  
Complex Objects ◽  
Radioactive Waste Management ◽  
Python Language ◽  
Size Number ◽  
Waste Container ◽  
Type Size

The article describes an approach to mesh generation allowing to address radioactive waste management tasks. The approach is based on representing an object as a set of simple geometric shapes (primitives). The characteristics of the mesh (type, size, number of elements) are controlled at a primitive level. The program allows to combine primitives using boolean operations to describe complex objects (for example, intrusions in host rock and their intersections with excavations). To describe nested objects (for example, a radioactive waste container in a borehole or a borehole in a host rock), the program implements a hierarchy of primitives. This approach can be used to generate meshes of objects with regular geometry and/or layered structures. The program is written in Python language. The mesh is created by editing the input files in JSON format.

scholarly journals IAEA compiling state of knowledge and developing high level guidance in radioactive waste management

2021 ◽  
Vol 1 ◽  
pp. 257-258
Author(s):  
Stefan Mayer ◽  
Rebecca Robbins
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Inventory Management ◽  
Cost Estimation ◽  
Waste Treatment ◽  
Stakeholder Involvement ◽  
Transfer Of Knowledge ◽  
Geologic Repository ◽  
Radioactive Waste Management ◽  
High Level

Abstract. One endeavour central to the International Atomic Energy Agency's (IAEA) mandate is compiling the international state of knowledge (SoK), supporting transfer of knowledge and establishing high level guidance for all peaceful applications of nuclear technologies, including those specific to radioactive waste management (RWM). Building on the current state of experiences and knowledge shared with us from IAEA Member States, we are developing a comprehensive suite of documents on the technologies and solutions having the potential to address RWM needs and steps. This information can be used as a baseline to guide RWM in other countries. In a first approach, the information is compiled and developed in a sequence of documents covering a range of topical domains. These include: RW: inventory; characterization; use of waste acceptance criteria throughout all RWM steps. RWM steps: a series of handbooks presenting approaches to waste treatment, conditioning and storage; special applications supporting small inventory management needs (e.g. through mobile facilities); considerations specific to management needs of postaccident radioactive waste. Endpoints: introduction to design approaches and disposal concepts; managing site investigations; global compendium of Underground Research Facilities (URF) RD&D; special considerations for small inventory disposal. Programmatic considerations: a generic roadmap to deep geologic repository (DGR) implementation; cost estimation and funding of a disposal programme; stakeholder involvement in disposal. To improve on efficiency and to prove our capacity to compile and transfer an evolving state of knowledge on topics relevant to RWM, the IAEA is building a collection of online interactive contents based on these publications. This online interactive content ultimately aims at containing all our key guidance topics and is intended to provide easier and more rapid access to detailed information. The format would also allow its content to be expanded with descriptions and analyses of topical case studies.

Sign in / Sign up

Export Citation Format

Share Document