Low-Level Liquid Waste Treatment System Technical Design in China

Author(s):  
Juan Zhao

Radioactive wastes are produced within the nuclear fuel cycle operations (uranium conversion and enrichment, fuel fabrication and spent fuel reprocessing). Evaporation is a proven method for the treatment of liquid radioactive waste providing both good decontamination and high concentration. Two technical designs of nuclear facilities for low-level liquid radioactive waste treatment are presented in the paper and the evaluation of both methods, as well. One method is two-stage evaporation, widely used in the People’s Republic of China’s nuclear facilities; another is two evaporator units and subsequently ion exchange, which is based on the experience gained from TIANWAN nuclear power plant. Primary evaporation and ion exchange ensure the treated waste water discharged to environment by controlling the condensate radioactivity, and secondary evaporation is to control concentrates in a limited salt concentration.

2004 ◽  
Vol 92 (7) ◽  
Author(s):  
F. Jan ◽  
M. Aslam ◽  
S. D. Orfi ◽  
A. Wahid

SummaryAfter upgrading the Pakistan Research Reactor-1, the amount of liquid waste and its increased radioactivity content necessitated a pre-disposal treatment to bring the activity down to disposal limits. Amongst several radionuclides in the waste,


Author(s):  
Jan Deckers ◽  
Paul Luycx

Abstract Since the very beginning of nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. An experimental furnace “Evence Coppée” was built in 1960 for treatment of LLW produced by the Belgian Research Centre (CEN.SCK). Regulatory this furnace has been modified, improved and equipped with additional installations to obtain better combustion conditions and a more efficient gas cleaning system. Based on the 35 years of experience gained by the operation of the “Evence Coppée”, a new industrial nuclear incineration installation was set into operation in May 1995, as a part of the Belgian Centralised Treatment/Conditioning Facility CILVA. Up to the end of 2000, the CILVA incinerator has burnt 703 tons of solid waste and 343 tons of liquid waste. This paper describes the type of waste and the allowable radioactivity, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the operation experience, capacity, volume reduction, chemical and radiological emissions and maintenance. The most important changes which improved safety, reliability and capacity are also mentioned. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialised in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste.


Author(s):  
Jia Lu ◽  
Yan Zhou

The Site Radwaste Treatment Facility (SRTF) was to treat the liquid radioactive waste with high concentration of electrolytes in CAP1400 plant. Unlike the forced-circulation or natural-circulation evaporator, the waste was purified by evaporation process using heat pump principle in SRTF. This process combined the benefits of heat pump technology and the separation function of evaporation. This paper gave a brief description of the complete evaporation process. The main equipments of the process included pre-heater, evaporator, demister, steam compressor, and distillate tank. The whole system and each unit operation in the process were elaborately simulated based on energy balance. The results can be further used for equipments selection and design. Through the whole discussion of the heat pump evaporation process, it showed the heat pump evaporation process has remarkable energy efficiency and great advantages in equipment layout compared to traditional evaporation treatment for liquid radioactive waste.


2012 ◽  
Vol 1475 ◽  
Author(s):  
Grazyna Zakrzewska-Trznadel ◽  
Marian Harasimowicz ◽  
Agnieszka Miskiewicz ◽  
Agnieszka Jaworska-Sobczak

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.


Author(s):  
David P. Field ◽  
Jim Stephens

Basic Technical Details: Displacement: 5000 tonnes; Width: 23.2m; Height: 6.6m; Length: 65m; Draught: 3.5m; Processing Throughput: 7000m3/year. In October 1993, the Governments of Japan and the Russian Federation signed an Intergovernmental Agreement to reduce the threat of nuclear weapons in the Former Soviet Union. Towards achieving this goal, the Japanese Government had initially allotted $100 million towards, which was increased to $200 million in 1999. The main objective of the Suzuran project is to process low-level liquid radioactive waste, which has been in storage for some years, and prevent it from being dumped into the seas shared by Japan and Russia. The construction and completion of the Suzuran, in the Russian Far East, is the brainchild of the Japanese Government, and is the first successful international project of its kind in Russia. Suzuran neatly solves the problem of making safe the liquid radioactive waste being derived from general purpose and missile nuclear submarines of the Russian Pacific Fleet as they are decommissioned and dismantled. The project was administered by the Technical Secretariat of the Japan-Russia Committee for Co-operation on Reducing Nuclear Weapons, who appointed Crown Agents as their agent and RWE NUKEM as their Technical Consultants to manage the project on a day to day basis and oversee the tender, construction and commissioning. This project is unique and complex in that it is, in reality, two projects. Firstly, the construction of a sea-going barge and, secondly, the construction of a complex radioactive liquid waste processing facility. Changes in the Russian Radiation Regulations during the course of the project, required the design to be altered significantly; for example, the facility had to be mounted within the structure of the vessel. Numerous regulators, design and testing institutes were involved throughout the project, to ensure it complied with both Russian and International regulations. Suzuran is the only floating complex that can operate independently for up to 30 days away from base. It is also exceptional in having the greatest throughput capacity of any project of its type and in being fully actively commissioned and licensed to operate, as part of the original contract. Other similar projects, which have a lower throughput and are land-based, have been handed over prior to completion of active commissioning. The international project was particularly complex since it involved not only Japan and Russia but also a Japanese-American contractor, who subcontracted the construction work to Russian shipyards. The Amurski Shipyard at Komsomolsk-na-Amur constructed the Vessel and the processing Facility was constructed in America and shipped to Russia where it was installed on the Barge. The Barge was then towed down the Amur River and down the Russian East Coast to Bolshoi Kamen where it was inactively and actively commissioned. The completed Barge was completed and is now operating, following a one-year warranty period. The project required everyone’s close co-operation and understanding. Particularly onerous was the need to comply with comprehensive Russian regulations, both for sea-going vessels as well as for nuclear facilities. This is a success story in itself. The official Handover ceremony of Suzuran was held in November 2000 and is now operating at the Far Eastern Shipyard, Zvezda. This paper will describe the history and process involved in establishing the Barge project for the treatment of Low Level Liquid Radioactive Waste.


2019 ◽  
Author(s):  
Alistair Holdsworth ◽  
Harry Eccles ◽  
daniel rowbotham ◽  
Adam Brookfield ◽  
David Collison ◽  
...  

Managing certain by-products of the nuclear fuel cycle, such as the radioactive isotopes of caesium: Cs-134, Cs-135 and Cs-137 is challenging due to their environmental mobility and radioactivity. While a great many materials can isolate Cs<sup>+</sup> ions from neutral or basic aqueous solutions via ion exchange, few of these, with the exception of ammonium phosphomolybdate (AMP), function effectively in acidic media. The use of AMP, and its porous composite in polyacrylonitrile (PAN) for management of Cs radioisotopes in various nuclear wastes have been known for decades and are well studied, yet the effects of radiation on the physiochemical properties of such composites have only received limited attention to date. In a previous publication, we demonstrated that a 100 kGy gamma irradiation dose has negligible effect on the ion exchange performance of AMP and AMP-PAN with respect to capacity or kinetics under the Cs<sup>+</sup> concentrations and acidity found in spent fuel recycling. As a continuation of this prior study, in this publication we explore the effects of gamma irradiation on the physiochemical properties of AMP and AMP-PAN using a range of characterisation methods. The effects of the same gamma dose on the oxidation state of Mo in AMP and AMP-PAN, the thermal degradation of both AMP and AMP-PAN, combined with a first study into the high-temperature degradation AMP, are reported. The implications of irradiation, its possible mechanism, the conditions present in SNF recycling, and for the end-of-life disposal or recycling of these materials are also discussed.


Author(s):  
Fouad Al-Musawi ◽  
Emad S. Shamsaldin ◽  
John R. Cochran

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.


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