Optimization Features in Management of Salaspils Research Reactor Decommissioning Waste

2003 ◽  
Author(s):  
A. Dreimanis
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Research Reactor ◽  
Optimal Solution ◽  
Environmental Safety ◽  
Radioactive Waste Disposal ◽  
Disposal Site ◽  
Radioactive Waste Management ◽  
Safety Control ◽  
Simplified Approach

Management of decommissioning waste is considered as complex task of seeking for optimal solution in the environment of various competing technical, safety and socio-economical factors. If from the formal mathematics viewpoint it is a multi-parameter optimization task, then for real conditions simplified approach for such problem should be applied. We propose to decompose this task into the set of optimization analysis for particular steps, and then in each step it is easier to find optimum. For the real case of management of radioactive waste arising from dismantling and decommissioning of Salaspils Research Reactor (SRR) we consider following main optimization steps: 1) the choice of the decommissioning concept — among three elaborated versions — with estimation of the foreseen radioactive waste amount for disposal, recycling and free release, taking into account also potential exposures and financial resources; 2) establishment of national radioactive waste management agency “RAPA” Ltd., ensuring common administration and maintenance of the shutdown SRR and radioactive waste (RW) disposal site — RAPA manages some decommissioning activities of SRR and shall actively participate together with envisaged decommissioning operator in this process also in future, but in all stages will keep full responsibility of waste management; 3) optimization of radioactive waste transportation: i) organizational aspects (packing, transportation time, schedule, route, etc.), ii) environmental safety control; 4) optimization arrangement of space for radioactive waste disposal: i) choice of the best strategy to ensure a new space, ii) optimization of the vault size — to be able accommodate decommissioning waste without being oversized; 5) strategy of treatment, conditioning and packing of solid decommissioning waste; 6) optimization of liquid decommissioning waste management — its conditioning together with the solid radioactive waste; 7) socio-economical optimization features: i) existing infrastructure for RW disposal, ii) financial compensation for local municipality, iii) international cooperation, technical and financial assistance by EU, IAEA, Sweden. The proposed optimization features used in the developing of Concept for radioactive waste management in Latvia for the period 2003–2010 (which corresponds to the approved decommissioning period of SRR) supplement existing separate optimization aspects of decommissioning waste management and could be considered as simplified integral set of factors for elaboration of optimal strategy for decommissioning waste management.

The Overview of Radioactive Waste Management Technology

2013 ◽  
Vol 448-453 ◽  
pp. 199-203
Author(s):  
Guo Hua Qiu
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Disposal ◽  
Reference Value ◽  
International Standards ◽  
Radioactive Waste Disposal ◽  
Radioactive Waste Management ◽  
Management Technology ◽  
Waste Classification

The Radioactive waste management technology is briefly introduced in this article based on related standards, guidelines and documents from IAEA. The radioactive waste management technology (RWM) includes related international standards and conventions, predisposal radioactive waste management, RWM for radioactive waste disposal, RWM for remediation, NORM and mining/milling waste. These management methods and valuable experience have important reference value to waste classification, waste disposal and management and related work in China.

Creation of system of final isolation (disposal) of radioactive waste in the Russian Federation

MRS Advances ◽  
2020 ◽  
Vol 5 (5-6) ◽  
pp. 275-282 ◽  
Author(s):  
Vsevolod Igin ◽  
Victor Krasilnikov
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Disposal ◽  
Russian Federation ◽  
Radioactive Waste Disposal ◽  
High Level Waste ◽  
Federal State ◽  
Radioactive Waste Management ◽  
Near Surface ◽  
High Level

Abstract:The paper provides generic overview of legal and regulatory framework of radioactive waste management activities held in Russian Federation and national operator responsibilities and accomplishments. It gives a short description of waste classification scheme used and plans for radioactive waste disposal. In particular the paper provides information on the plans of the FEDERAL STATE UNITARY ENTERPRISE "National operator for radioactive waste management" to construct and operate several near-surface disposal facilities for low and intermediate level waste with total capacity up to 550 000 cubic meter. The paper also provides detailed information on the steps of high-level waste disposal program including site-selection, construction phase of the underground research laboratory (URL) near the city of Zheleznogorsk, Krasnoyarsk Region and research program after the construction of the URL. The paper also describes Russian system and state policy in the field of RW management and gives recommendations for future implementers.

Radioactive Waste Disposal and Protection of the Future Public

2015 ◽  
Vol 6 (2) ◽  
pp. 86-95
Author(s):  
John Tauxe
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Management Practices ◽  
Radioactive Wastes ◽  
Radioactive Waste Disposal ◽  
Radioactive Waste Management ◽  
Natural Processes ◽  
Social Actions ◽  
The Future ◽  
Waste Management Practices

Much of humanity's solid waste will outlast the human race, and the waste generated by one generation must be endured and managed by future societies. Radioactive wastes are unique in that their regulation explicitly considers the protection of future generations. But radioactive waste management faces a serious quandary: how to balance the substantial expense of waste isolation against the uncertain mitigation of risks to hypothetical future humans. Most of this uncertainty stems not from natural processes, or from the projected performance of engineered materials, but rather from social actions and human behaviors. Given that these uncertainties become overwhelming when consider the future only a few centuries from now, how far into the future is it useful for us to attempt to assess risks? Government regulators are currently grappling with this question as they rewrite regulations in order to accommodate radioactive wastes that have the potential for unacceptable and perpetual human health risks. This paper discusses the issues surrounding the period of performance expected from radioactive waste management practices, and outlines central conditions for soundly addressing controversial problems.

The Radioactivity Analysis of 14C in the Graphite Samples From the Dismantled KRR-1&2 Sites by a High Temperature Furnace and a LSC

2007 ◽  
Author(s):  
Hee Reyoung Kim ◽  
Wanno Lee ◽  
Kun Ho Chung ◽  
Mun Ja Kang ◽  
Dong Gyu Lee ◽  
...  
Keyword(s):  
High Temperature ◽  
Radioactive Waste ◽  
Research Reactor ◽  
Radioactive Waste Disposal ◽  
Disposal Site ◽  
Low Level ◽  
High Temperature Furnace ◽  
Quenching Efficiency ◽  
Low Level Radioactive Waste ◽  
Temperature Furnace

The radioactivity of 14C of the graphite samples from the dismantled Korea Research Reactor 1&2 (the KRR-1&2) site was analyzed and proposed to be disposed of as a low level radioactive waste rather than self-disposed of. The graphite wastes, with a weight of seven tons, have been generated during the dismantling of a research reactor with a capacity of one MW from 1995 to 2006. The graphite was used as a moderator for the research reactor and so has been radioactivated by thermal neutron. It was thought that the graphite wastes mainly included a radioisotope of stable carbon, 14C, a pure beta emitter with a half life of 5,730 years and with a maximum decay energy of 156 keV. Therefore, it has been requested to see whether the dismantled graphite radioactive wastes including 14C can be self-disposed of or not. In the present study, the radioactivity of 14C in the graphite sample used in the research reactor was analyzed by using a commercialized high temperature furnace and a Liquid Scintillation Counter (LSC). The combustion temperature of the furnace was five hundred degrees centigrade and especially the temperature in the catalyst region was eight hundred degrees centigrade. The recovery from the furnace was 95% for 14C and the LSC had a quenching efficiency of approximately 66%. Carbosorb was used as a trapping solution for 14C. The radioactivity of 14C was measured by a LSC through the procedure of a pre-treatment such as the combustion of a sample in the temperature range of 500–800 degrees centigrade by a high temperature furnace, trapping of 14C into carbosorb and cocktailing it with a scintillator. The radioactivity was analyzed to have a concentration with a value of much more than a domestic legal limit for a self-disposal. And an individual effective dose rate estimation was also carried out. Finally, it is suggested that the graphite wastes from the dismantled research reactor should be disposed of at a low level radioactive waste disposal site and monitored.

An Overview on the National Radwastes Management Strategy in the Context of the Nuclear Program Development in Romania

2009 ◽  
Author(s):  
Panait Adrian ◽  
Maria Radu ◽  
Gheorghe Barariu ◽  
Gheorghe Negut ◽  
Cristian Litescu
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Radioactive Waste Disposal ◽  
National Strategy ◽  
National Agency ◽  
Radioactive Waste Management ◽  
Nuclear Program ◽  
The Government

At present the main radwaste generator is Cernavoda NPP with 2 × 700 MW units in operation. For the year 2016, the Plant is predicted to have 4 units in operation. The National Strategy for radioactive waste management was drafted by National Agency for Radioactive Waste (ANDRAD), the jurisdictional authority for coordinating spent nuclear fuel and radioactive waste management in Romania. Last year, the Government of Romania established that a new nuclear power plant would be build, so, with this future operational NPP, the quantity of waste will increase from the today evaluations. Therefore the national strategy for radioactive waste management should be reviewed accordingly. The paper presents some preliminary results obtained upon the R&D Programs related to the radioactive waste disposal facilities.

RADIOACTIVE WASTE MANAGEMENT IN HUNGARY: CHANGING APPROACHES AND CONFLICTS

2007 ◽  
Vol 09 (02) ◽  
pp. 185-209 ◽  
Author(s):  
ANNA VARI ◽  
ZOLTAN FERENCZ
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Financial Incentives ◽  
Nuclear Power ◽  
Public Information ◽  
Community Support ◽  
Host Community ◽  
Radioactive Waste Disposal ◽  
Radioactive Waste Management ◽  
Market Approach

One of the most interesting paradoxes of the application of nuclear energy in Hungary is that although the building, operation, and even the recent lifetime extension of the Paks nuclear power plant has not faced significant social opposition, attempts for siting radioactive waste disposal facilities have been accompanied by a number of social conflicts. The paper reviews the history of radioactive waste management in Hungary from the 1970s until recently. It is found that since the political transition of 1990, top-down technocratic approaches to facility siting have been replaced by the so-called "market approach", which put a strong emphasis on host community support. Most important elements of the latter approach include public information and the provision of generous financial compensation/incentives for host and neighbouring communities. However, analysis of recent Hungarian siting cases shows the weaknesses of the pure market approach, e.g., the lack of transparency and openness regarding national strategies, the lack of accountability, and the focus on financial incentives rather than sustainable development issues.

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