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All sources NASA NTRS DOE OSTI

DOE OSTI2015

Investigations into the Effect of Current Velocity on Amidoxime-Based Polymeric Uranium Adsorbent Performance

The Fuel Resources Program at the U.S. Department of Energy’s (DOE), Office of Nuclear Energy (DOE-NE) is developing adsorbent technology to extract uranium from seawater. This technology is being developed to provide a sustainable and economically viable supply of uranium fuel for nuclear reactors (DOE, 2010). Among the key environmental variables to understand for adsorbent deployment in the coastal ocean is what effect flow-rates or linear velocity has on uranium adsorption capacity. The goal is to find a flow conditions that optimize uranium adsorption capacity in the shortest exposure time. Understanding these criteria will be critical in choosing a location for deployment of a marine adsorbent farm. The objective of this study was to identify at what linear velocity the adsorption kinetics for uranium extraction starts to drop off due to limitations in mass transport of uranium to the surface of the adsorbent fibers. Two independent laboratory-based experimental approaches using flow-through columns and recirculating flumes for adsorbent exposure were used to assess the effect of flow-rate (linear velocity) on the kinetic uptake of uranium on amidoxime-based polymeric adsorbent material. Time series observations over a 56 day period were conducted with flow-through columns over a 35-fold range in linear velocity from 0.29 to 10.2 cm/s, while the flume study was conducted over a narrower 11-fold range, from 0.48 to 5.52 cm/s. These ranges were specifically chosen to focus on the lower end of oceanic currents and expand above and below the linear velocity of ~ 2.5 cm/s adopted for marine testing of adsorbent material at PNNL.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2010

Concetration and Distribution of Depleted Uranium (DU) and Beryllium (Be) in Soil and Air on Illeginni Island at Kwajalein Atoll after the Final Land-Impact Test

Re-entry vehicles on missiles launched from Vandenberg Air Force base in California re-enter at the Western Test Range, the Regan Test Site (RTS) at Kwajalein Atoll. An Environmental Assessment (EA) was written at the beginning of the program to assess potential impact of DU and Be, the major RV materials of interest from a health and environmental perspective, for both ocean and land impacts. The chemical and structural form of Be and DU in RVs is such that they are insoluble in soil water and seawater. Thus, they are not toxic to plant life on the isalnd (no soil to plant uptake.) Similarly, due to their insolubility in sea water there is no uptake of either element by fish, mollusks, shellfish, sea mammals, etc. No increase in either element has been observed in sea life around Illeginnin Island where deposition of DU and Be has occured. The critical terrestrial exposure pathway for U and Be is inhalation. Concentration of both elements in air over the test period (1989 to 2006) is lower by a factor of nearly 10,000 than the most restrictive U.S. guideline for the general public. Uranium concentrations in air are also lower by factors of 10 to 100 than concentrations of U in air in the U.S. measured by the EPA (Keith et al., 1999). U and Be concentrations in air downwind of deposition areas on Illeginni Island are essentially indistinguishable from natural background concentrations of U in air at the atolls. Thus, there are no health related issues associated with people using the island.

45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEF↗

DOE OSTI2019

From Watt-Scale to Megawatt-Scale: Advances in Wave Energy Technologies for Offshore Applications

Potential applications for wave energy cover the spectrum from powering watt-scale maritime sensors to generating electricity at megawatt-scale. These applications include energy generation for: ocean observation, communications, autonomous underwater vehicles recharging, isolated community grids, aquaculture, underwater data centers, seawater desalination, ocean mining, disaster relief and recovery, and utility grids. Much of the focus to date has been on utility-scale systems for grid-connected applications. Furthermore, despite the effort to develop viable technologies and the attractiveness of the resource, wave energy has yet to achieve status as a mainstream renewable resource.

16 TIDAL AND WAVE POWER↗

DOE OSTI2010

Complete genome sequence of Coraliomargarita akajimensis type strain (04OKA010-24T)

Coraliomargarita akajimensis Yoon et al. 2007 the type species of the genus Coraliomargarita. C. akajimensis is an obligately aerobic, Gram-negative, non-spore-forming, non-motile, spherical bacterium which was isolated from seawater surrounding the hard coral Galaxea fascicularis. C. akajimensis organism is of special interest because of its phylogenetic position in a genomically purely studied area in the bacterial diversity. Here we describe the features of this organism, together with the complete genome sequence, and annotation. This is the first complete genome sequence of a member of the family Puniceicoccaceae. The 3,750,771 bp long genome with its 3,137 protein-coding and 55 RNA genes is a part of the Genomic Encyclopedia of Bacteria and Archaea project.

99 GENERAL AND MISCELLANEOUS↗

NASA NTRS1988

Mychonastes desiccatus Brown sp. nova (Chlorococcales, Chlorophyta)--an intertidal alga forming achlorophyllous desiccation-resistant cysts

An intertidal Chlorella-like alga Mychonastes desiccatus Brown sp. nova, capable of forming achlorophyllous desiccation-resistant cysts, has been grown in unialgal culture. This small alga was first isolated from a dried sample of a well-studied microbial mat. The mat, located at North Pond, Laguna Figueroa, San Quintin, Baja California, Mexico, is a vertically-stratified microbial community which forms laminated sediments. Morphology, pigment composition and G+C content are within the range typical for the genus Chlorella s. 1. Unlike other chlorellae, however, upon desiccation M. desiccatus forms an achlorophyllous, lipid-filled cyst (thick-walled resting stage) in which no plastid is evident. Rewetting leads to chloroplast differentiation, excystment and recovery of the fully green alga. During desiccation, sporopollenin is deposited within a thickening cell wall. Encystment cannot be induced by growth in the dark. The formation of desiccation-induced cysts allows the alga to survive frequent and intermittent periods of dryness. These chlorellae tolerate wide ranges of acidity and temperature; they both grow and form cysts in media in which sodium ions are replaced with potassium. Although the cysts tolerate crystalline salts, the cell grow optimally in concentrations corresponding from three-quarters to full-strength seawater.

NASA Discipline Exobiology↗

NASA NTRS1993

Spirosymplokos deltaeiberi nov. gen., nov. sp.: variable-diameter composite spirochete from microbial mats

Large (up to 100 micrometers long), loosely coiled, free-living spirochetes with variable diameters (from 0.4 to 3 micrometers in the same cell) were seen at least 40 times between August 1990 and January 1993. These spirochetes were observed in mud water and enrichment media from highly specific habitats in intertidal evaporite flats at three disjunct localities, one in Spain and two in Mexico. All three are sites of commercial saltworks. Associated with Microcoleus chthonoplastes the large spirochetes from Spain display phototaxis and a composite organization. Shorter and smaller-diameter spirochetes are seen inside both healthy and spent periplasm of larger ones. Small spirochetes attached to large ones have been observed live. From two to twelve spirochete protoplasmic cylinders were seen inside a single common outer membrane. A distinctive granulated cytoplasm in which the granules are of similar diameter (20-32 nanometers) to that of the flagella (26 nanometers) was present. Granule diameters were measured in thin section and in negatively-stained whole-mount preparations. Based on their ultrastructure, large size, variable diameter, number of flagella (3 to 6), and phototactic behavior these unique spirochetes are formally named Spirosymplokos deltaeiberi. Under anoxic (or low oxygen) conditions they formed blooms in mixed culture in media selective for spirochetes. Cellobiose was the major carbon source in 80% seawater, the antibiotic rifampicin was added, mat from the original field site was present and tubes were incubated in the light at from 18-31 degrees C. Within 1-2 weeks populations of the large spirochete developed at 25 degrees C but they could not be transferred to fresh medium.

Non-NASA Center↗

DOE OSTI2012

Covalently bonded three-dimensional carbon nanotube solids via boron induced nanojunctions

The establishment of covalent junctions between carbon nanotubes (CNTs) and the modification of their straight tubular morphology are two strategies needed to successfully synthesize nanotube-based three-dimensional (3D) frameworks exhibiting superior material properties. Engineering such 3D structures in scalable synthetic processes still remains a challenge. This work pioneers the bulk synthesis of 3D macroscale nanotube elastic solids directly via a boron-doping strategy during chemical vapor deposition, which influences the formation of atomic-scale elbow junctions and nanotube covalent interconnections. Detailed elemental analysis revealed that the elbow junctions are preferred sites for excess boron atoms, indicating the role of boron and curvature in the junction formation mechanism, in agreement with our first principle theoretical calculations. Exploiting this material s ultra-light weight, super-hydrophobicity, high porosity, thermal stability, and mechanical flexibility, the strongly oleophilic sponge-like solids are demonstrated as unique reusable sorbent scaffolds able to efficiently remove oil from contaminated seawater even after repeated use.

36 MATERIALS SCIENCE↗

DOE OSTI2011

Complete Genome Sequences of Krokinobacter sp. 4H-3-7-5 and Lacinutrix sp. 5H-3-7-4, polysaccharide-degrading members of the family Flavobacteriaceae

Two members of the family Flavobacteriaceae were isolated from deep sea sediments in Japan using artificial seawater and cellulose, xylan and chitin as sole carbon and energy source. Here, we present the finished genome sequence of Krokinobacter sp. 4H-3-7-5 and Lacinutrix sp. 5H-3-7-4 which both encode for putatively novel enzymes involved in cellulose, hemicellulose and chitin degradation.

59 BASIC BIOLOGICAL SCIENCES↗

DOE OSTI2018

Thermal Desalination as Cooling for a Supercritical Carbon Dioxide Brayton Cycle

Multi-effect distillation (MED) is commonly used for seawater desalination. MED offers numerous advantages over other existing thermal desalination systems. MED systems are commonly integrated with a steam-Rankine power cycle, for simultaneous production of power and freshwater. Low-pressure steam is extracted from the power cycle to act as a heat source for the MED. The operating temperature of the low-pressure steam must be high enough to drive the MED system. This necessitates an increase in the operating pressure on the power-cycle condenser, resulting in a decrease in power production. Hence, integration of MED with the steam-Rankine cycle is a parasitic load for the power plant. The supercritical carbon dioxide (sCO2) Brayton cycle is being pursued as a new power cycle because of its potential for higher energy efficiency and compact turbomachinery. The sCO2 exiting the low-temperature recuperator is quite hot and is cooled as a sensible-heat fluid before flowing back to the compressor. This heat is sufficiently hot to drive an MED system, rather than being rejected to the environment. Such a thermal integration could lead to simultaneous production of power and potable water without affecting the sCO2 Brayton cycle efficiency. The objective of the present study is to maximize the distillate production from MED without acting as a parasitic load. Optimal feed configuration for the MED is identified for maximizing the distillate concentration. Techno-economic analysis showed the cost of distillate for MED is about 30% lower than distillate produced by reverse osmosis (RO).

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

DOE OSTI2013

Current status of research and development program for characterizing fuel debris at Fukushima Daiichi NPS by JAEA

Japan Government and TEPCO submitted a research road map for decommissioning Fukushima Daiichi Nuclear Power Plant. Two projects about debris are in progress: 'Assessment of simulated fuel debris characteristics' and 'Development of technologies for the processing of fuel debris'. The major results concerning the first project are the following 4 points. First, it was suggested that typical phase of oxide of fuel debris is (U,Zr)O{sub 2} and that of metal is Fe{sub 2}(Zr,U) by thermodynamic calculation. Secondly, important properties of fuel debris for developing defueling tools were identified as shape, size, density, hardness, elastic modulus, fracture toughness, thermal conductivity, specific heat (heat capacity), and melting point. Thirdly, the influence of seawater salt and B{sub 4}C/SUS to characteristics of debris was found, such as deposition of magnesium oxide crystal on the surface of fuel debris. The Influence of Pu to thermal properties of fuel debris was found, such as the increase of melting point. Concerning the second project, the major results are the following. First, a draft of the whole image of scenarios was developed. Secondly, the alkaline resolution method using Na{sub 2}O{sub 2} is most likely to be applied as a part of analysis technologies. Thirdly, it was shown that a part of fuel debris rich in U might be soluble in nitric acid. Fourthly, it was shown that all pyrochemical processes examined have potential to be applied for treating fuel debris. The results of the projects will contribute to the decommissioning program.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2012

Multi-Phased, Post-Accident Support of the Fukushima Dai-Ichi Nuclear Power Plant - 12246

In the wake of the March 11 earthquake and tsunami and the subsequent flooding of several of the Fukushima Dai-Ichi reactors, Japan and the Japanese utility TEPCO faced a crisis situation with incredible challenges: substantial amounts of radioactive mixed seawater and freshwater accumulated in the basements of four reactor and other buildings on the site. This water held varying levels of contamination due to the fact that it had been in contact with damaged fuel elements in the cores and with other contaminated components. The overall water inventory was estimated at around 110,000 tons of water with contamination levels up to the order of 1 Ci/l. Time was of the essence to avoid overflow of this accumulated water into the ocean. AREVA proposed, designed and implemented a water treatment solution using a proven chemical coprecipitation process with ppFeNi reagent, which is currently in use for effluent treatment on several nuclear sites including AREVA sites. In addition to the extremely short schedule the other challenge was to adapt the chemical treatment process to the expected composition of the Fukushima water and, in particular, to evaluate the impact of salinity on process performance. It was also necessary to define operating conditions for the VEOLIA equipment that had been selected for implementation of the process in the future facility. The operation phase began on June 17, and by the end of July more than 30,000 tons of highly radioactive saltwater had been decontaminated - the Decontamination Factor (DF) for Cesium was ∼10{sup 4}. It allowed recycling the contaminated water to cool the reactors while protecting workers and the environment. This paper focuses on the Actiflo{sup TM}-Rad water treatment unit project that was part of the TEPCO general water treatment scheme. It presents a detailed look at the principles of the Actiflo{sup TM}-Rad, related on-the-fly R and D, an explanation of system implementation challenges, and a brief summary of operation results to date. AREVA's response to the Fukushima Dai-Ichi crisis was multi-phased: emergency aid and relief supply was sent within days after the accident; AREVA-Veolia engineering teams designed and implemented a water treatment solution in record time, only 3 months; and AREVA continues to support TEPCO and propose solutions for waste management, soil remediation and decontamination of the Fukushima Dai-Ichi site. Despite the huge challenges, the Actiflo{sup TM}-Rad project has been a success: the water treatment unit started on time and performed as expected. The performance is the result of many key elements: AREVA expertise in radioactive effluents decontamination, Veolia know-how in water treatment equipments in crisis environment, and of course AREVA and Veolia teams' creativity. The project success is also due to AREVA and Veolia teams' reactivity and high level of commitment with engineering teams working 24/7 in Japan, France and Germany. AREVA and Veolia deep knowledge of the Japanese industry ensured that the multi-cultural exchanges were not an issue. Finally the excellent overall project management and execution by TEPCO and other Japanese stakeholders was very efficient. The emergency water treatment was a key step of the roadmap towards restoration from the accident at Fukushima Dai-Ichi that TEPCO designed and keeps executing with success. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2012

Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312

Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2015

Uptake selectivity for different types of zeolites in the presence of boric acid - 15244

The development of selective adsorbents is very important subject for the effective multi-nuclide decontamination related to the severe accident of Fukushima NPP-1. Many removal methods have been developed to separate nuclide from decontaminated solutions containing multi-nuclide so far. From the standpoint of cost efficiency, stability for usage and safety handling, the decontamination methods using inorganic adsorbents are one of the most effective methods for the selective decontamination system. Thus, many researches related to inorganic adsorbents have been carried out after the accident; actually, in Fukushima NPP-1, zeolites are used to remove radioactive nuclides from decontaminated water as a main adsorbent in the circulating injection cooling system. However, the adsorption characteristics of zeolites in the presence of boric acid have not been clarified in detail. As for the decontamination in PWR[1], the adsorption properties should be examined in the presence of highly concentrated boric acid. Based on this background, the final objective of this study is to develop the decontamination methods in PWR-NPP by using various zeolites for multi-nuclide. In this study, the adsorption properties for eight kinds of zeolites (Zeolite A, Zeolite X, Zeolite Y, Zeolite L, Chabazite, Synthetic Mordenite, Natural Mordenite and Clinoptilolite) are evaluated in the presence of boric acid and seawater. The present study deals with (1) selective adsorption properties for single nuclide ion ({sup 137}Cs{sup +}, {sup 60}Co{sup 2+}, {sup 85}Sr{sup 2+} and {sup 152}Eu{sup 3+}), (2) preparation of Ag-loaded Natural Mordenite (Ag-NM) and uptake properties of I- ions, and (3) multi-nuclide decontamination properties of 26 elements (typical elements in Advanced Liquid Processing System (ALPS) in Fukushima NPP-1) for the above zeolites. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2018

Economic Feasibility Analysis and Engineering System Design Development of Novel Cesium Adsorbents - 18680

Potassium copper hexacyanoferrate-cellulose hydrogel composites (HCF-gels) and potassium copper hexacyanoferrate-embedded poly-citric acid hydrogel film (HPC) were synthesized. In Cs{sup +} removal experiments, HCF-gels exhibited exceptional Cs{sup +} adsorption capacities 2.06-2.32 mmol g{sup -1}. HPC showed a very high Cs{sup +} uptake of 667 mg/g KCuHCF. The adsorbents revealed stable and high Cs{sup +} removal efficiency across a wide pH range. Notably, the adsorbents could adsorb Cs{sup +} selectively in seawater containing Cs{sup +}. The combination of testing and radiation stability results indicated that the performance of the materials are maintained whether irradiated or not. The cost of the HCF-gels and HPC were estimated approximately 13.0055 $/kg and 38.2490 $/kg respectively. This is reasonable cost compared to commercialized Cs{sup +} adsorbents. New pool scrubbing system is designed for engineering system design to apply novel Cs{sup +} adsorbents under severe accident condition. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2016

Adsorption Modeling at the Front and Back Ends of the Nuclear Fuel Cycle

Adsorption is a diverse and complex physicochemical process that has many different applications in chemical, environmental, and nuclear sciences. For example, adsorption can be found at both the front and back ends of the nuclear fuel cycle for (i) capturing uranium from seawater to use as a new source of nuclear fuel and (ii) treatment of the off-gases produced when reprocessing used nuclear fuel. Accurate modeling of these processes is important for the design of efficient capture, recovery, and removal systems for the particular aqueous or gaseous species of interest. A set of algorithms and methods designed for flexibility and portability will greatly improve the ability to rigorously model such a complex set of systems. This approach allows more specific models to be built upon the more generic methods, which gives the overall modeling effort larger breadth and greater usability. Due to the complexity of adsorption processes, it is necessary to develop relatively complex mechanistic models to accurately predict the behavior of engineered adsorption systems. Capture and recovery systems designed for nuclear energy need to have a high level of accuracy to reduce uncertainties and aid in the implementation of separations technologies for efficient nuclear energy systems. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2016

Fuel Cycle Study to Developing a Viable Long Term Nuclear Power Scenario for the UK

Within the UK a closed fuel cycle has been in operation for decades but with the introduction of a new build programme to create 16 GWe capacity using LWR technology and with the closure of the UK's reprocessing industry, an open fuel cycle will be implemented beyond 2020. However, it is expected that 16 GWe nuclear capacity will not be enough for the UK to curb greenhouse gas emissions through increased demand for low carbon electricity, and tackle energy security. As such further nuclear expansion scenarios are being considered between 40 and 75 GWe by 2050. This study evaluates a viable 40 GWe UK nuclear scenario, evaluating the extent to which key drivers can impact a future UK nuclear energy strategy, including; the ability to sustain a relatively high nuclear capacity, fresh uranium availability, accumulation of spent fuel at decommissioning nuclear reactor sites and capacity requirements of future GDF host sites. The thermal reactor open fuel cycle is the de-facto standard around the world for many reasons including the reliance on extremely mature technology, significant operational experience and most importantly a relatively low cost. However, the premise that a thermal reactor open fuel cycle is the correct one to adopt long term is dependent on the notion that large quantities of UO{sub 2} spent fuel can eventually be disposed of in a geological disposal facility and the future availability of fresh uranium. The total amount of available uranium is unknown and if extraction from seawater proves to be economic and practical then any future concerns regarding supply disappear. Spent fuel disposability on the other hand has never been performed on a commercial scale and there is some uncertainty when and whether this can be achieved. This paper will follow from previous work already presented in 2013 [REF] which examined UK fuel cycles involving the transition to a closed fast reactor fleet by the end of this century. The revised scenarios now assume fast reactors are required later in the scenario, in-line with other countries. In addition, the new study has used physics methods originally developed by SKB to assess the physical size of the repository required to dispose of all intermediate and high level waste whilst ensuring temperature limits imposed by the engineered barriers and surrounding geology are adhered to. The disposition of less Am-241 in the repository will no doubt lead to a reduction in GDF footprint. However, this may not be important to GDF design and economics. The purpose of this paper is to also critically review the importance of and put into perspective a smaller GDF footprint and lower fissile inventory. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2019

Influence of Na and Ca Concentrations on Sr Adsorption Performance of Cs-Sr Simultaneous Adsorbent - 19315

Treating evaporation-concentrated liquid waste stored in tanks at Fukushima Daiichi Nuclear Power Station site with high radioactive Cs and Sr concentrations has been examined using Cs-Sr simultaneous adsorbent. The evaporation-concentrated liquid waste contains Na and Ca concentrations which are almost equal to or higher than their natural concentrations in seawater. In the Cs-Sr simultaneous adsorbent, Na and Ca compete with Sr adsorption. For the aforementioned reasons, the influence of Na and Ca concentrations on Sr adsorption performance of Cs-Sr simultaneous adsorbent was experimentally evaluated. The throughput of Sr adsorption was measured by column test in which Na and Ca concentrations were set as parameters. The results showed that higher concentrations of Na and Ca caused reduction of throughput of Sr adsorbent, and Ca concentration that showed a certain throughput was two or more orders of magnitude lower than Na concentration. This result reflected the selectivity of Cs-Sr simultaneous adsorbent was higher in the order of Sr > Ca > Na. Based on the results, treatment process of evaporation-concentrated liquid waste that consisted of dilution by water and then removal of Sr using Cs-Sr simultaneous adsorbent was investigated. The results suggested that the dilution of the evaporation-concentrated liquid waste improve the throughput of the Cs-Sr simultaneous adsorbent and leads to the reduction of the amount of Cs-Sr simultaneous adsorbent needed to treat the evaporation-concentrated liquid waste. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2016

Assessment of Reactor BN-350 Impact on the Environment During Its Operation Period

Fast neutron reactor BN-350 was designed for dual purposes: steam production and plutonium generation. The steam produced in the reactor was used to generate electricity (150 MW) and desalination of seawater (up to 120 000 tons/day). The BN-350 reactor began operating in July 1973 with a design lifetime of 20 years. After the end of the reactor design lifetime in July 1993, its further operation was managed on the basis of annual decisions taken to extend the operating life for one year. The reactor was in downtime beginning in December 1998 and on 22 April 1999 the RK Government Resolution no. 456 'About decommissioning of the BN-350 reactor in Aktau, Mangistau region' was adopted. Thus, the total actual reactor operational period was more than 25 years. In the framework of work under the approved 'Plan of priority measures for decommissioning of the BN-350 reactor in Aktau', the specialists of the Institute of Nuclear Physics (INP) and the Mangystau Nuclear Power Complex performed a radiation survey of the plant area, the sanitary protection zone and reactor BN-350 monitoring area. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗